Inventory taking (инвентаризация)

Inventory taking of nuclear substances and radioactive wastes (Инвентаризация радиоактивных веществ и радиоактивных отходов) – process of determining actual presence of radioactive substances and RW in the organization and comparison with the data contained in the accounting documents. (NP-067-11)

Physical inventory taking (Инвентаризация физическая) – determining actual amounts of nuclear materials in the material balance area. (NP-025-2000).

IONIZING RADIATION (ИОНИЗИРУЮЩЕЕ ИЗЛУЧЕНИЕ) – radiation generated in the course of radioactive decay, nuclear transformations, deceleration of charged particles in the matter, creating oppositely charged ions when interacting with matter. (Federal Law No. 3-FZ “On radiation safety of public”)

Comment

A corresponding term in the IAEA Glossary is “Radiation” (Излучение).

isolating unit ((устройство Изолирующее) – pipeline fitting (valve, gate valve) designed for isolation of accident localization zone from environment. (NP-010-11)

justification of safety (of machinery and equipment) обоснование безопасности (машин и оборудования) – document, which contains risk analysis, as well as information from design, operational, process documents on minimum necessary safety measures for a machine and (or) equipment for all of the stages of its lifecycle, augmented with the results of risk assessment in operation after maintenance or repair. (Technical Specifications on safety of machinery and equipment)

JUSTIFICATION PRINCIPLE (ПРИНЦИП ОБОСНОВАНИЯ) – prohibition of all types of activities associated with the use of ionizing radiation sources, where the benefit for mankind and society does not exceed the risk of possible harm caused by radiation exposure in addition to natural background level. ((Federal Law No. 3-FZ “On radiation safety of public”)

Comment

A corresponding term in the IAEA Glossary is “Justification” (Обоснование).

karst (Карст) – a set of phenomena associated with effects of water (surface and underground) and consisting in dissolution of underground rock masses and formation of voids of different shapes and sizes, as well as in establishment of special nature of circulation of subsurface water and characteristic terrain relief and hydrographic system. (NP-064-05)

key measurement point (Ключевая точка измерений) – a location in the material balance area, where accounting and (or) verification measurements are performed. (Refined definition of NP-030-12)

LAND USE PLANNING (Территориальное планирование) – planning of development of territory, inclusively for establishing functional zones, determination of planned location of Federal objects, regional objects, or local objects. (“Town Building Code of the Russian Federation” No. 190-FZ)

lapping (Наплыв) – a defect in the form of metal that leaked during welding (overlaying) on the surface of welded components or beads made earlier and failed to fuse with it. (PNAE G-7-010-89)

LARGE EMERGENCY RELEASE (БОЛЬШОЙ АВАРИЙНЫЙ ВЫБРОС) – see EMISSION (ВЫБРОС).

lead material science organization (Головная материаловедческая организация) – see MATERIAL SCIENCE ORGANIZATION (МАТЕРИАЛОВЕДЧЕСКАЯ ОРГАНИЗАЦИЯ).

“LEAK BEFORE BREAK” CONCEPT (КОНЦЕПЦИЯ “ТЕЧЬ ПЕРЕД РАЗРУШЕНИЕМ”) – approach to designing pipelines based on the proven mechanism of crack development when a leak detectable by the instrument anticipated by the design occurs before it reaches critical size. (OPB-12)

leak of fuel element (Разгерметизация твэла) – fuel element damage with loss of integrity in the form of gaseous leak or direct contact of nuclear fuel with coolant. (NP-082-07, NP-080-07)

LEAK RATE (Значение утечки) – quantitative measure of leaktightness defined as mass or volume of fluid leaving the controlled volume at specified parameters within the time measurement unit. (NP-010-11)

Design leak rate (значение утечки проектное) – the leak rate specified for system (component) by its design documentation. (NP-010-11)

Actual leak rate (значение утечки фактическое) – the leak rate obtained through checking (testing) of system (component). (NP-010-11)

LEAKTIGHT CASK (ПЕНАЛ ГЕРМЕТИЧНЫЙ) – leaktight vessel designed for placement of SNF (spent fuel assemblies or spent fuel elements). (NP-035-02)

LEAKTIGHT CONTAINMENT (ГЕРМЕТИЧНОЕ ОГРАЖДЕНИЕ) – a set of components of a unit (including structures) shrouding the space around the reactor unit or other object containing radioactive materials and forming a boundary designed for precluding spreading of radioactive substances into environment in excess of the established limits. The space shrouded by the containment can consist of one or several leaktight rooms or compartments. (NP-010-11, NP-040-02)

leaktight room or compartment (Герметичное помещение) – a room or compartment of the plant located within the leaktight containment. (RB-044-09)

leaktight valve (Гермоклапан) – see VALVES (АРМАТУРА).

leaktightness (Герметичность) – ability of a component or system to contain liquid or gaseous substances, including aerosols, within the established boundaries. (NP-010-11, NP-068-05)

level 1 psa (ВАБ АС уровня 1) – see ANALYSIS (АНАЛИЗ).

level 2 psa (ВАБ АС уровня 2) – see ANALYSIS (АНАЛИЗ).

LEVEL OF DEVELOPMENT OF SCIENCE, TECHNOLOGY AND INDUSTRY, MODERN (УРОВЕНЬ РАЗВИТИЯ НАУКИ, ТЕХНИКИ И ПРОИЗВОДСТВА СОВРЕМЕННЫЙ) – see MODERN LEVEL OF DEVELOPMENT OF SCIENCE, TECHNOLOGY AND INDUSTRY (СОВРЕМЕННЫЙ УРОВЕНЬ РАЗВИТИЯ НАУКИ, ТЕХНИКИ И ПРОИЗВОДСТВА).

level of NEGLIGIBLE radiation risk (Уровень пренебрежимого риска радиационного) – risk level, below which risk is considered negligible and its further reduction is inexpedient. (PRB AS-99)

level, control (Уровень контрольный) – see CONTROL LEVEL (КОНТРОЛЬНЫЙ УРОВЕНЬ)

life (Ресурс) – total operation time of a valve from beginning of its operation or resumption of operation after maintenance to transition into limiting state. (NP-068-05)

LIFE CYCLE (Жизненный цикл)

Complete life cycle of a nuclear facility (жизненный цикл ОИАЭ полный) – siting, design and engineering (including surveys), manufacturing, construction (including installation, adjustment, commissioning), operation, modernization, maintenance, decommissioning (closure), transportation (shipment), handling, storage, disposal and ultimate disposal of nuclear facilities. (Federal Law No.170-FZ “On the use of nuclear energy)

Life cycle (Жизненный цикл)²⁰ – a period of time from the beginning of design of a machine and (or) equipment to the end of utilization, including the interdependent stages (design, manufacturing, storage, assembling, maintenance, operation, including modernization, repair, maintenance and servicing). (Technical Specifications on safety of machinery and equipment)

Life cycle of a building or structure (жизненный цикл здания или сооружения) – a period of time, within which engineering surveys, design, construction (including conservation), operation (and current maintenance), modernization, renovation and demolition of a building or structure are performed. (Federal Law No. 384-FZ “Technical Specifications on safety of buildings and structures”)

Life cycle of a nuclear facility (жизненный цикл ОИАЭ) – siting, design and engineering (including surveys), manufacturing, construction (including installation, adjustment and commissioning), operation, modernization, overhaul, decommissioning (closure), transportation (shipment), handling, storage, disposal and ultimate disposal of nuclear facilities (depending on the type of nuclear facility). (NP-090-11)

life, assigned (ресурс Назначенный) – see ASSIGNED LIFE (Назначенный ресурс).

LIFETIME EXTENSION (ПРОДЛЕНИЕ СРОКА ЭКСПЛУАТАЦИИ) – activities aimed at preparing a power unit for operation during extended lifetime. (NP-017-2000)

lift valve (Клапан подъемный) – see VALVES (АРМАТУРА).

lightning strike (Удар молнии) – natural phenomenon characterized by impact on the environment of electric discharge between clouds or between clouds and ground surface. (NP-064-05)

LIMITER SWITCH (Концевой выключатель) – a component providing information signals when the control rod reaches limiting positions or in case of disconnection of a control rod drive. (NP-086-12)

limiting state (предельное состояние)

Limiting state (of machine or equipment) (Предельное состояние (машины или оборудования)) – state of machinery and (or) equipment, at which their further operation is unallowable or inexpedient, or recovery of their operable state is impossible or inexpedient. (Technical Specifications on safety of machinery and equipment)

Limiting state of structural modules (Предельное состояние строительных конструкций) – state of structures and buildings, beyond which further operation of the building or structure is dangerous, unallowable, complicated or inexpedient, or restoration of operability of the building or structure is impossible or inexpedient. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

LIMITING STATE (СОСТОЯНИЕ предельное) – state of component, after which its further operation is unallowable or inexpedient, or restoration of its operability is impossible or inexpedient. (NP-017-2000)

LINEAR OSCILLATOR (ОСЦИЛЛЯТОР ЛИНЕЙНЫЙ) – linear oscillatory system with one degree of freedom characterized by oscillation period and decay. (NP-031-01)

linear spectral analysis method (МЕТОД АНАЛИЗА линейно-спектральный) – method of seismic resistance analysis, in which the seismic loads are determined from direct response spectra depending on the frequencies and forms of free oscillations of the analyzed structure. (NP-031-01)

liquid radioactive waste deep disposal site ((Полигон глубинного захоронения жидких радиоактивных отходов) – natural and engineered system designed for disposal of LRW, located within the territory defined by the design, including a subsoil plot - receiving horizon (reservoir bed), located within a mining allotment, and a set of facilities, systems and equipment for LRW handling. (NP-058-04)

LIQUIDATION OF POWER UNIT (ЛИКВИДАЦИЯ БЛОКА АС) – option of decommissioning involving stage-wise dismantling (immediate and delayed) and liquidation of equipment, systems, structures and buildings, removal of all radioactive wastes from the nuclear power unit site, and reclamation of the site for subsequent use. (NP-012-99)

list of stock quantities of radioactive substances and radioactive wastes (Список наличного количества радиоактивных веществ и радиоактивных отходов) – list of actually available RW and RS with indication of their quantities compiled based on the accounting documentation. (NP-067-11)

load (НАГРУЗКА) – mechanical force applied to buildings, structures and (or) their bases and determining their stress-deformed state. (Federal Law No. 384-FZ “Technical Specifications on safety of buildings and structures”)

LOCALIZATION OF POWER UNIT SYSTEMS AND COMPONENTS (ЛОКАЛИЗАЦИЯ СИСТЕМ И ОБОРУДОВАНИЯ БЛОКА АС) – isolation of systems and components of a nuclear plant limiting the release of radioactive substances and radiation into plant rooms and compartments and into environment by means of using the existing and creating additional physical barriers. (NP-012-99)

LOCALIZING SAFETY SYSTEMS (COMPONENTS) (ЛОКАЛИЗУЮЩИЕ СИСТЕМЫ (ЭЛЕМЕНТЫ) БЕЗОПАСНОСТИ) – see SAFETY SYSTEMS (COMPONENTS) (СИСТЕМЫ (ЭЛЕМЕНТЫ) БЕЗОПАСНОСТИ).

LONG-LIVED NUCLIDES (НУКЛИДЫ ДОЛГОЖИВУЩИЕ) – any mixture of long- and medium-lived radioactive aerosols that can be detected on aerosol filter during its exposure in gas flow for 24 hours with measurement made in 24 hours after the end of exposure. (NP-021-2000)

loss of containment leaktightness (Разгерметизация герметичного ограждения) – state of plant components on the boundary of accident localization zone, resulting in the leak from the containment (leaktight enclosure) in excess of the design limits in case of occurrence of initiator of design basis event, assuming that safety systems operate as designed. (NP-010-11)

loss of preferred power (Обесточивание энергоблока) – loss of AC power supply from all normal operation sources (operating and standby in-house power supply transformers) of a nuclear power unit. (NP-087-11)

LOW TOXICITY ALFA EMITTERS (Альфа-излучатели низкой токсичности) – natural uranium; depleted uranium; natural thorium; uranium-235 or uranium-238; thorium-232; thorium-228 and thorium-230, contained in ores or in the form of physical and chemical concentrates, or alpha-emitters with less than 10 days half-life. (NP-053-04)

Comment

This term is fully equivalent to the same term in the IAEA Glossary.

low-enriched uranium (Низкообогащенный уран) – see URANIUM (УРАН).

lower concEnTration limit of flame propagation (Нижний концентрационный предел распространения пламени) – minimum content of flammable substance in homogeneous mixture with oxidizing agent, at which flame can propagate on unlimited distance from the ignition source. (NP-010-11)

LRW CEMENTING (ЦЕМЕНТИРОВАНИЕ ЖРО) – embedding LRW into matrix cement material. (NP-019-2000)

LRW VITRIFICATION (ОСТЕКЛОВЫВАНИЕ ЖРО) – transfer of LRW into glass-like state. (NP-019-2000)

machine (машина) – an assembly of interdependent parts and units, at least one of which is operated with the aid of drives, circuits, controls, power sources, united together for a particular purpose (processing, reprocessing, transportation or packaging of material). (Technical Specifications on safety of machinery and equipment)

MAGNITUDE (МАГНИТУДА) – logarithm of maximum calculated amplitude of a record (in microns), which would be made by standard short-period torque seismograph (To = 0.8 s, V = 2800, h = 0.8) at a distance of 100 km from the epicenter of the earthquake. (RB-019-01)

main components of valve (Детали арматуры основные) – components (except gaskets and packing glands), a failure of which can cause loss of leaktightness of the valve with respect to the external space or the flow path. (NP-068-05)

MAIN CONTROL ROOM (БЛОЧНЫЙ ПУНКТ УПРАВЛЕНИЯ) – a part of nuclear power unit located in the specially designed compartments and intended for centralized automated process control performed by operating personnel and automatics. (OPB-12)

MAINTAINING OF OPERATORS’ QUALIFICATION LEVEL (ПОДДЕРЖАНИЕ УРОВНЯ КВАЛИФИКАЦИИ ОПЕРАТОРОВ) – maintaining skills and abilities of operators to control power unit by means of regular training exercises on full scope simulator in normal operation modes and abnormal operation modes, including pre-accident situations and accidents. (NP-003-97)

MAINTENANCE (ТЕХНИЧЕСКОЕ ОБСЛУЖИВАНИЕ) – set of measures to maintain operability and serviceability of object (systems and components) during intended use, in standby mode, during storage and transportation. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Maintenance” (Техническое обслуживание).

manual drive (Привод ручной) – transportable appliance for manual translocation of reactivity control means (NP-086-12)

manufacturer (Организация-изготовитель) – organization, manufacturing equipment and assembly units and (or) components of pipelines (equipment). (PNAE G-7-008)

MATERIAL AGEING PHENOMENA (УСТАЛОСТНЫЕ ЯВЛЕНИЯ В МАТЕРИАЛЕ) – change of mechanical and physical properties of material under long term action of cyclic stresses and deformations. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

material batch (Партия материала) – totality (portion) of nuclear material (product) contained in one or several accounting units or in process equipment, quantitative and (or) qualitative composition of which, for the purposes of accounting and control is determined based on single set of data and measurement results recorded in the accounting documents. (Refined definition of NP-030-12)

material science organization (Материаловедческая организация) – organization recognized by federal nuclear regulatory and management authorities to be competent to provide services related to selection of materials, welding, quality assurance of equipment and pipelines. (PNAE G-7-008-89)

Approval by the lead material science organization (Согласование головной материаловедческой организации) – positive conclusion of the lead material science organization produced at the request of operating utility or other organizations. (PNAE G-7-010-89)

Lead material science organization (Головная материаловедческая организация) – organization recognized by appropriate nuclear authority to be competent to render to operating utilities services related to selection of materials, welding, quality assurance of equipment and pipelines, review of design and technical documentation, nuclear and radiation safety analysis reports, and holding a license of the Regulatory authority for these activities. (Refined definition of PNAE G-7-010-89)²¹

material with low dissipation ability, radioactive (материал с низкой способностью к рассеянию Радиоактивный) – see RADIOACTIVE MATERIAL WITH LOW DISSIPATION ABILITY (Радиоактивный материал с низкой способностью к рассеянию (РМНР)).

MATERIAL WITH LOW SPECIFIC ACTIVITY (lsa MATERIAL) (Материал с низкой удельной активностью (материал НУА)) – radioactive material with naturally limited specific activity or radioactive material, to which limits of established average specific activity are applied. External protecting materials, surrounding the LSA material, are not to be taken into account while determining the average specific activity. (NP-053-04)

Comment

This term is fully equivalent to the same term in the IAEA Glossary “Low specific activity (LSA) material” (Материал с низкой удельной активностью (НУА)).

material, radioactive (материал Радиоактивный) – see RADIOACTIVE MATERIAL (Радиоактивный материал).

MATERIALS (Материалы) – steels and alloys in the form of blanks or semifinished products (forgings, pipes, sheets, rolled section steel, castings, etc.) and welding materials used for manufacturing equipment and pipelines for nuclear power facilities. (PNAE G-7-008)

MAXIMUM ALLOWABLE EMISSION (Предельно допустимый выброс) – see EMISSION (выброс).

MAXIMUM DESIGN LIMIT OF FUEL ELEMENT DAMAGE (Максимальный проектный предел повреждения твэлов) – see DESIGN LIMITS (ПРОЕКТНЫЕ ПРЕДЕЛЫ).

MAXIMUM NORMAL OPERATION PRESSURE Максимальное нормальное рабочее давление) – see PRESSURE (ДАВЛЕНИЕ).

MAXIMUM REACTIVITY MARGIN (Максимальный запас реактивности) – reactivity that can be introduced in the nuclear reactor in case of removal from the core of all reactivity control means and removable absorbers at a certain point of the campaign and for the nuclear reactor state with the maximum value of effective breeding coefficient. (NP-082-07)

MCR CONTOURS (КОНТУРЫ БПУ)

Non-operative contour of MCR (Неоперативный контур БПУ) – non-operative control panels located outside of the zone of continuous monitoring from the workplaces of MCR operators (outside of direct visibility area). (NP-003-97)

Operative contour of MCR (Oперативный контур БПУ) – operative control panels located within the zone of continuous monitoring from the workplaces of MCR operators (in direct visibility area). (NP-003-97)

MCR OPERATOR (OПЕРАТОР БПУ АС) – a member of plant operating personnel having undergone complete course of training and properly authorized to control a nuclear power unit. (NP-003-97)

means of access control (Средства контроля доступа) – technical components, intended for detection of unauthorized removal, use, translocation of NM or unauthorized access to NM. They are classified into visual monitoring systems and tamper evidence seals. (NP-030-12)

MEANS OF AUTOMATION (СРЕДСТВА АВТОМАТИЗАЦИИ) – totality of software, hardware, and firmware intended for creation of control systems. (NP-026-04)

means of individual protection (Средство индивидуальной защиты) – technical items, worn by people in order to prevent or minimize the influence of harmful and/or hazardous factors and to obtain protection against contamination. (NRB-99/2009, PRB AS-99)

means of reactivity control (Средства воздействия на реактивность) – technical means in the form of solid, liquid or gaseous absorbers (moderators, reflectors), change of state or position of which in the core or in the reflectors provides changes of reactivity of the reactor core. (NP-082-07)

measured reactivity (реактивность Измеренная) – reactivity measured by reactimeter based on neutron flux signal (neutron power) from one or several in-core or ex-core detectors. (RB-074-12)

Measurement (measurements) (Измерение (ИЗМЕРЕНИЯ))

Accounting measurements (измерения учетные) – measurement of parameters of nuclear materials, products, results of which are used for determining the information recorded in the accounting documents. (NP-030-12)

Direct measurement (прямое измерение) – measurement, in which the value of the measured parameters is obtained directly from an instrument. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

Measurement (измерение) – set of actions performed for determining quantitative value of a parameter. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

Reference (verificatation) measurements (измерения арбитражные (проверочные)) – measurement of quantitative parameters of nuclear materials or accounting units performed in case of identification of an anomaly. (NP-030-12)

measurement method (метод ИЗМЕРЕНИЙ) – see MEASUREMENT METHODOLOGY (МЕТОДИКА ИЗМЕРЕНИЙ).

MEASUREMENT METHODOLOGY (МЕТОДИКА ИЗМЕРЕНИЙ) – combination of specifically described actions, performance of which ensures obtaining the results of measurements with the established accuracy. (Refined text of definition from the Federal Law No. 102-FZ “On ensuring unification of measurements”)

mechanical restraINt of control rod (механический упор исполнительного механизма) – see RESTRAINT (УПОР).

mechanical safety (механическая безопасность) – see SAFETY (БЕЗОПАСНОСТЬ).

metal, deposited (металл Наплавленный) – see DEPOSITED METAL (Наплавленный металл).

METROLOGICAL requirements (Метрологические требования) – requirements to measurement characteristics (parameters), standard specimens, instruments affecting the results and accuracy of measurements, and conditions under which these characteristics (parameters) are to be guaranteed. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

Mandatory metrological requirements (метрологические требования обязательные) – metrological requirements established by legal acts and regulations of the Russian Federation and mandatory for compliance on the territory of the Russian Federation. (Federal Law No.102-FZ “On ensuring unification of measurements”)

metrological review (Метрологическая экспертиза) – analysis and assessment of accuracy of definition of and compliance with metrological requirements at the reviewed facility. Metrological review can be mandatory or voluntary. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

metrological service (Метрологическая служба) – structural subdivision of the central office of federal executive body and (or) its territorial branch, legal entity or structural part of legal entity or union of legal entities, employees of legal entity or individual entrepreneurs, organizing and (or) performing the activities aimed at ensuring unification of instrumentation and (or) providing services associated with ensuring unification. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

MICROZONING, SEISMIC (МИКРОРАЙОНИРОВАНИЕ СЕЙСМИЧЕСКОЕ) – see SEISMIC MICROZONING (СЕЙСМИЧЕСКОЕ МИКРОРАЙОНИРОВАНИЕ).

MINIMUM CUTSET (Минимальное сечение) – minimum set of basic events leading to loss of operability of a system or failure to perform a safety function, or unsafe end state. (RB-024-11)

MINIMUM SIGNIFICAN ACTIVITY (минимально значимая Активность (МЗА)) – see ACTIVITY (АКТИВНОСТЬ).

MINIMUM SIGNIFICAN SPECIFIC ACTIVITY (минимально значимая удельная Активность (МЗУА)) – see ACTIVITY (АКТИВНОСТЬ).

mixed oxide fuel (mox fuel) (топливо Уран-плутониевое (МОКС)) – nuclear fuel, in which nuclear materials in the form of uranium and plutonium oxides is used for fabrication of fuel elements and fuel assemblies. (NP-080-07)

mixture, stoichiometric (смесь Стехиометрическая) – see STOICHIOMETRIC MIXTURE (Стехиометрическая смесь).

MODELING LIMITS (ПРЕДЕЛЫ МОДЕЛИРОВАНИЯ) – boundary condition of the state of power unit from/to which modeling of process systems and unit as a whole is performed. (NP-003-97)

MODERN DIFFERENTIATED EARTH CRUST MOVEMENTS (Современные дифференцированные движения земной коры) – movements of the Earth’s crust in the form of relative displacement of Earth crust blocks, including tectonic creep. (NP-064-05)

MODERN LEVEL OF DEVELOPMENT OF SCIENCE, TECHNOLOGY AND INDUSTRY (СОВРЕМЕННЫЙ УРОВЕНЬ РАЗВИТИЯ НАУКИ, ТЕХНИКИ ИПРОИЗВОДСТВА) – complex of scientific and technical knowledge, design, technology and engineering developments in a certain area of science and technology supported by scientific research and practical experience and published in scientific and technical papers. (OPB-12)

monitoring (Мониторинг) – system of observation of processes (phenomenon, factor) of natural or technogenic origin, state of environment, facility, and assessment and forecast of changes and development thereof. (NP-064-05)

Comment

A corresponding term in the IAEA Glossary is “Monitoring” (Мониторинг).

Dynamic monitoring (мониторинг динамический) – systematic monitoring of dynamic parameters of structures performed in support of decision making on their further operation. (RB-045-08)

Environmental monitoring (Мониторинг окружающей среды) – system of surveillance and monitoring performed regularly per a specific program for assessment of the state of environment, analysis of processes occurring in it, and timely detection of any trends. (RB-045-08)

Comment

IAEA Glossary contains the same term “Environmental monitoring” (Мониторинг окружающей среды), however, it is only defined in relation to radioactivity sources.

Monitoring of hazardous natural processes and phenomena (Мониторинг опасных природных процессов и явлений) – system of regular surveillance and monitoring of development of hazardous natural phenomena and processes in environment and factors contributing to their occurrence and development. (RB-046-08)

monitoring channel (Канал контроля) – combination of detectors, communication lines, signal processing and (or) parameter representation systems designed to ensure monitoring function in accordance with the design. (NP-082-07)

Comment

A corresponding term in the IAEA Glossary is “Channel” (Канал).

MONITORING DETECTOR (ДЕТЕКТОР-МОНИТОР) – neutron-activation detector irradiated together with other detectors or sets of detectors, results of measurements of which are used to bring the results of measurements of different detectors to identical irradiation conditions in terms of spatial variable (e.g. in order to account for spatial variable of fast neutron field). (RB-018-01)

monitoring object (Объект мониторинга) – natural, technogenic or combined object or its part, within which regular environmental surveillance is performed according to a specific program in order to monitor the processes occurring in it to timely identify, assess, and predict their changes. (RB-044-09)

moniToring, radiation (Контроль радиационный) – see RADIATION MONITORING (радиационный Контроль).

moving parts of executive mechanism (Подвижные части исполнительного механизма) – components of the executive mechanism, moving together with the means of reactivity control. (NP-086-12)

mud streams (Сели) – short-term (on the average, 1 to 3 hours) destructive streams overloaded with stone and mud materials occurring during ample rainfalls or intensive snow melting in the mountainous regions, river basins and ravines with steep slopes of valley-lines (above 0.1). (NP-064-05)

mud volcanic activity (вулканизм грязевой) – phenomenon accompanied with ejection of mud and rock due to abnormally high inner pressure in gas fluidal massives. (NP-064-05)

NATIONAL RADIOACTIVE WASTE MANAGEMENT OPERATOR (Национальный оператор по обращению с радиоактивными отходами) – legal entity authorized by the effective Federal Law to perform activities associated with disposal of radioactive wastes and other radioactive waste management activities. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

natural and technogenic catastrophe (Катастрофа природная и техногенная) – a catastrophe accompanied by consequences of global or regional scale associated with infliction of irreparable damage to environment, multiple human casualties, direct economic losses and expenses associated with mitigation activities, caused by external natural or technogenic events. (NP-064-05)

natural radiation background (естественный Радиационный фон) – see BACKGROUND (ФОН).

NATURAL RADIATION EXPOSURE (ПРИРОДНОЕ ОБЛУЧЕНИЕ) – see RADIATION EXPOSURE.

NATURAL SOURCE OF RADIATION (природный Источник излучения) – see SOURCE (ИСТОЧНИК).

NATURAL uranium (Природный уран) – see URANIUM (УРАН).

nearest distance to fault surface (Расстояние кратчайшее до поверхности разлома) – a widely used measure of distance. As experience demonstrated, this yields minimum dispersion of empirical data. (RB-006-98)

NEGATIVE EFFECTS OF WATER (НЕГАТИВНОЕ ВОЗДЕЙСТВИЕ ВОД) – flooding, inundation, damage of banks of water bodies, swamp formation and other negative impacts on certain territories and objects. (“The Water Code of the Russian Federation” No. 74-FZ)

NEUTRON FLUENCE DETECTORS (ДЕТЕКТОРЫ ФЛЮЕНСА НЕЙТРОНОВ) – neutron-activation detector irradiated for extended periods of time (e.g. over a fuel campaign), and the half-life of the reaction products is comparable with the irradiation time. (RB-018-01)

nominal diameter (conventional flow path) (Диаметр номинальный (условный проход)) – inner diameter of a pipeline connected to a valve, corresponding to the nearest value in the adopted sequence of conventional diameters. (NP-068-05)

nominal thickness of main metal of overlayed component (product) (Номинальная толщина основного металла наплавленной детали (изделия)) – thickness of the main metal of component (product) identified in the drawings (not taking into account the allowances). (PNAE G-7-010-89)

nominal thickness of welded components (Номинальная толщина сваренных деталей) – thickness of the main metal of components in the vicinity of the weld identified in the drawings (not taking into account the allowances). (PNAE G-7-010-89)

non-fixed contamination OF surface (нефиксированное загрязнение поверхности) – same as REMOVABLE SURFACE CONTAMINATION (НЕСНИМАЕМОЕ ЗАГРЯЗНЕНИЕ ПОВЕРХНОСТИ).

non-irradiated thorium (Необлученный торий) – thorium containing no more than 10^-7 g of Uranium-233 per 1 g of Thorium-232. (NP-053-04)

non-irradiated uranium (Необлученный уран) – see URANIUM (УРАН).

NON-OPERATIVE CONTOUR OF MCR (НЕОПЕРАТИВНЫЙ КОНТУР БПУ) – see MCR CONTOURS (КОНТУРЫ БПУ).

NON-RADIATION INCIDENT (ПРОИШЕСТВИЕ НЕРАДИАЦИОННОЕ) – an incident associated with loss of control of radiation source due to equipment inoperability or personnel errors, natural catastrophes or other causes, which could result in unplanned exposure of people and (or) radioactive contamination of environment. (RB-012-2000)

non-removable RADIOACTIVE contamination OF surface (Неснимаемое радиоактивное загрязнение поверхности) – same as NON-REMOVABLE SURFACE CONTAMINATION (НЕСНИМАЕМОЕ ЗАГРЯЗНЕНИЕ ПОВЕРХНОСТИ).

non-removable surface contamination (Неснимаемое загрязнение поверхности) – see CONTAMINATION (ЗАГРЯЗНЕНИЕ).

normal operation (НОРМАЛЬНАЯ ЭКСПЛУАТАЦИЯ) – plant operation within the limits and conditions specified by the design. (OPB-12, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Normal operation” (Нормальная эксплуатация).

normal operation conditions (УСЛОВИЯ ЭКСПЛУАТАЦИИ НОРМАЛЬНЫЕ) – state of building or structure taken into account in the design, in which there are no factors precluding normal performance of functional or technological processes. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

NORMAL OPERATION CONTROL SYSTEMS (COMPONENTS) (УПРАВЛЯЮЩИЕ СИСТЕМЫ (ЭЛЕМЕНТЫ) НОРМАЛЬНОЙ ЭКСПЛУАТАЦИИ) – systems (components) forming and realizing control of normal operation systems (components) of a nuclear plant based on preset targets, criteria and limitations. (OPB-12, NP-026-04)

NORMAL OPERATION SYSTEMS (COMPONENTS) (СИСТЕМЫ (ЭЛЕМЕНТЫ) НОРМАЛЬНОЙ ЭКСПЛУАТАЦИИ) – systems (components) designed for normal operation. (OPB-12)

NUCLEAR ACCIDENT (ЯДЕРНАЯ АВАРИЯ) – see ACCIDENT (АВАРИЯ).

NUCLEAR AND RADIATION HAZARDOUS FACILITY SITE (ПЛОЩАДКА ЯРОО) – territory within the limits of guarded perimeter, on which main and auxiliary buildings and structures of the nuclear and radiation hazardous facility are located. (RB-019-01)

nuclear fuel storage (Хранение ядерного топлива) – storage of NF in the conditions providing its confinement in accordance with the design, with intention of subsequent withdrawal. (NP-061-05)

nuclear fuel storage facility (Хранилище ядерного топлива) – separate nuclear material storage facility or a structure within a reactor plant designed for storage of fresh or spent nuclear fuel. (NP-061-05)

Class 1 nuclear fuel storage facility (Хранилище ядерного топлива класса 1) – nuclear fuel storage facility, possibility of ingress of water or other moderator into which is precluded. (NP-061-05)

Class 2 nuclear fuel storage facility (Хранилище ядерного топлива класса 2) – nuclear fuel storage facility, possibility of flooding of which with water or other moderator is precluded, inclusively with the aid of engineered systems. (NP-061-05)

Class 3 nuclear fuel storage facility (Хранилище ядерного топлива класса 3) – fresh nuclear fuel storage facility, for which the requirements to class 1 and class 2 facilities are not complied with. Floating storage facilities are class 3. (NP-061-05)

nuclear fuel storage quota (Норма хранения ядерного топлива) – amount of NF that can be stored taking into account limitations for its location. (Refined definition of NP-061-05)

nuclear fuel transportation (Транспортирование ядерного топлива) – translocation of nuclear fuel with the aid of transportation and weight lifting machinery in accordance with the design process within the limits of nuclear facility. (NP-061-05)

NUCLEAR FUEL TRANSPORTATION AND STORAGE SYSTEM (СИСТЕМА ХРАНЕНИЯ И ТРАНСПОРТИРОВАНИЯ ЯДЕРНОГО ТОПЛИВА) – combination of systems (components) designed for NF storage and transportation. (NP-061-05)

nuclear fuel transportation quota (Норма транспортирования ядерного топлива) – amount of NF that is permitted for transportation taking into account limitations for its location. (Refined definition of NP-061-05)

nuclear fuel, fresh (топливо Свежее ядерное) – see FRESH NUCLEAR FUEL (Свежее ядерное топливо).

nuclear fuel, spent (топливо ядерное Отработавшее) – see SPENT NUCLEAR FUEL (Отработавшее ядерное топливо).

NUCLEAR HAZARDOUS ACTIVITIES (ЯДЕРНО-ОПАСНЫЕ РАБОТЫ) – activities involving nuclear plant systems or components important for safety (including tests, taking out of service for maintenance and commissioning), not described in the plant Technical Specifications and operating procedures. (OPB-12)

NUCLEAR INSTALLATION (ЯДЕРНАЯ УСТАНОВКА) – see NUCLEAR INSTALLATIONS (ЯДЕРНЫЕ УСТАНОВКИ).

nuclear INSTALLATIONS (ядерныЕ УСТАНОВКИ) – structures and complexes with nuclear reactors, including nuclear power stations, ships and other watercrafts, spacecrafts, aircrafts, other transportation and transportable vehicles, structures and complexes with research, test, industrial nuclear reactors, critical and subcritical nuclear test facilities, structures, complexes, testing grounds and facilities with nuclear explosives for peaceful purposes, other facilities, structures, complexes containing nuclear materials, facilities for manufacturing, usage, reprocessing, transportation of nuclear fuel and nuclear materials. (Federal Law No. 170-FZ “On the use of nuclear energy”, NP-025-2000, NP-030-12)

Comment

A corresponding term in the IAEA Glossary is “Nuclear facility” (Ядерная установка).

nuclear material and radioactive substance storage facilities (Пункты хранения ядерных материалов и радиоактивных веществ) – stationary objects and structures other than nuclear reactor installations or radiation sources, designed for storing radioactive substances and nuclear materials, storage or disposal of radioactive wastes. (Federal Law No. 170-FZ “On the use of nuclear energy”)

nuclear material in bulk form (материал Ядерный В БАЛК-ФОРМЕ) – see NUCLEAR MATERIALS (ЯДЕРНЫЕ МАТЕРИАЛЫ).

nuclear material losses (Потери ядерных материалов) – decrease of the amount of NM in the MBA due to release of liquid or gaseous products, losses due to accidents or misplacement. (NP-030-12)

nuclear material, actual amount (количество ядерного материала Фактически наличное) - see ACTUAL AMOUNT OF NUCLEAR MATERIAL (Фактически наличное количество ядерного материала).

nuclear materials (ЯдерныЕ материалЫ) – materials, containing or capable of reproducing fissile materials (substances). (Federal Law No. 170-FZ “On the use of nuclear energy”, NP-025-2000, NP-030-12, NP-053-04)

Comment

The IAEA Glossary contains a similar term “Nuclear material” (Ядерный материал), but it is more prescriptively defined.

Nuclear material in the bulk form (материал ядерный в балк-форме) – NM, containing in a product, which is not an accounting unit. (NP-030-12)

nuclear objects (Объекты использования атомной энергии) – nuclear facilities, radioactivity sources, nuclear and radioactive material storage facilities, radioactive waste storage facilities, fuel assemblies of nuclear reactors, spent nuclear fuel, nuclear materials, radioactive materials, radioactive wastes. (NP-064-05)

NUCLEAR PLANT (REACTOR PLANT) DESIGNERS (РАЗРАБОТЧИКИ ПРОЕКТА АС (РУ)) – organizations developing design of the nuclear plant (reactor) and providing engineering and scientific support at all stages of the lifecycle of the nuclear plant (reactor). (OPB-12)

NUCLEAR PLANT (АТОМНАЯ СТАНЦИЯ) – structures and complexes with nuclear reactors, necessary systems, components and equipment for energy generation in the prescribed operating modes and conditions, located within the territory defined by design and staffed with necessary personnel (employees). (OPB-12)

Comment

IAEA Glossary does not provide definition of a nuclear plant (nuclear station). It is included into definition of “Nuclear installation” (Ядерной установки).

District heating nuclear plant (атомная станция теплоснабжения) – nuclear plant designed for generating heat for district heating and hot water supply. (OPB-12)

Nuclear power plant (атомная станция электрическая) – nuclear plant designed for electricity generation. (OPB-12)

Power and industrial nuclear station (атомная станция энерготехнологическая) – nuclear plant designed for electricity generation and for industrial purposes. (OPB-12)

NUCLEAR PLANT ADMINISTRATION (АДМИНИСТРАЦИЯ АС) – managers and other officials granted by the operating utility with rights, obligations and responsibilities at the stages of construction, commissioning, operation and decommissioning of a nuclear plant. (OPB-12)

Comment

The IAEA Glossary contains a corresponding term “Senior management” (Старшее административное руководство), though it is defined differently. It is a person or a group of persons performing management and control functions and assessments in the organization at the top level.

NUCLEAR PLANT CONSTRUCTION (СООРУЖЕНИЕ АС) – process of erecting buildings and structures of the plant, including a complex of construction activities, equipment installation activities, auxiliary, transportation and other activities. (OPB-12)

nuclear plant operating state (состояние АС Эксплуатационное) – normal operation state of a plant, characterized by a unique set of attributes (operation mode, plant parameters, state of systems, etc.). (Refined definition of RB-044-09)

NUCLEAR PLANT SAFE OPERATION LIMIT (ПРЕДЕЛ БЕЗОПАСНОЙ ЭКСПЛУАТАЦИИ АС) – see DESIGN LIMITS (ПРОЕКТНЫЕ ПРЕДЕЛЫ).

NUCLEAR PLANT SAFE OPERATION LIMIT (ПРЕДЕЛ БЕЗОПАСНОЙ ЭКСПЛУАТАЦИИ АС) – see DESIGN LIMITS (ПРОЕКТНЫЕ ПРЕДЕЛЫ).

NUCLEAR PLANT SITE (ПЛОЩАДКА АС) – territory within the limits of guarded perimeter, on which main and auxiliary buildings and structures of the plant are located. (NP-031-01, NP-032-01)

Comment

A corresponding term in the IAEA Glossary is “Site area” (Территория площадки).

NUCLEAR PLANT SITE VICINITY (РАЙОН размещения АС) – territory, including plant site, on which natural or technogenic phenomena, processes and factors capable of affecting nuclear plant safety are possible. (NP-031-01)

nuclear plant state with damaged radioactivity source (Состояние АС с повреждением источника радиоактивности) – totality of end states with damage of radioactivity source grouped based on the attributes of the plant state with damage of radioactivity source affecting the degree of damage of the source, containment integrity, probability, composition and magnitude of emergency release. (RB-044-09)

nuclear power plant construction locality (ПУНКТ СТРОИТЕЛЬСТВА АТОМНОЙ СТАНЦИИ) – territory within the area considered for nuclear power plant siting, where several sites can be located, for which the geographic and situational conditions, including: mutual location of the plant and towns or cities, major industrial enterprises or other objects, water supply conditions, transportation conditions, social, demographic, agricultural and industrial conditions have similar characteristics. (Requirements to content and scope of surveys and analysis during plant siting. Item 4.1 SP PNAE-87)

NUCLEAR POWER UNIT (БЛОК АС) – a part of nuclear power plant performing nuclear plant function in the scope defined by the design. (OPB-12)

Nuclear power unit under design (проектируемый блок ас) – a nuclear power unit at the stage of design and/or construction. (RB-032-04)

NUCLEAR POWER UNIT DECOMMISSIONING OPTION (ВАРИАНТ вывода из эксплуатации блока АС) – one of the methods of step-by-step achievement of the defined end state of the unit in the course of its decommissioning. The main nuclear power unit decommissioning options are the following: dismantling of the unit, and entombment (burial) of the unit. (NP-012-99)

NUCLEAR POWER UNIT DECOMMISSIONING PROGRAM (ПРОГРАММА вывода из эксплуатации блока АС) – document, containing description of the end state after completion of all decommissioning activities, main organizational and technical measures to implement the selected decommissioning option, sequence and schedule of decommissioning, and list of major activities on each decommissioning stage. (NP-012-99)

object with surface radioactive contamination (Объект с поверхностным радиоактивным загрязнением) – solid object, which, not being radioactive, has radioactive contamination of its surface. (NP-064-05)

ON-SITE TRANSPORTATION AND PACKAGING SET – a set of technical facilities used for housing fresh or spent NF, ensuring nuclear and radiation safety and safeguarding of the NF during storage and transportation within the site of the nuclear facility. (NP-061-05)

OPEN RADIONUCLIDE SOURCE (Открытый РАДИОНУКЛИДНЫЙ ИСТОЧНИК) – see SOURCE (ИСТОЧНИК).

OPERATING CONDITIONS (ЭКСПЛУАТАЦИОННЫЕ УСЛОВИЯ) – conditions specified in the design in terms of numbers, characteristics, state of operability and maintenance of systems (components) required for operation without violation of operating limits. (OPB-12)

operating conditions, normal (НОРМАЛЬНЫЕ УСЛОВИЯ ЭКСПЛУАТАЦИИ) – see NORMAL OPERATING CONDITIONS (УСЛОВИЯ ЭКСПЛУАТАЦИИ НОРМАЛЬНЫЕ).

OPERATING UTILITY (ЭКСПЛУАТИРУЮЩАЯ ОРГАНИЗАЦИЯ) – organization founded in accordance with the legislation of the Russian Federation and recognized by appropriate management authority in the area of use of nuclear energy to be capable of operating nuclear plants and performing, on its own or with the aid of other organizations, activities associated with siting, design, construction, operation and decommissioning of nuclear plants, as well as nuclear material and radioactive substance handling and management activities. In order to perform these activities, the utility must have appropriate license issued by the Regulatory authority. (OPB-12, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Operating organization” (Эксплуатирующая организация).

OPERATION (ЭКСПЛУАТАЦИЯ) – all the activities aimed at safely achieving the purposes for which the nuclear plant was built, including power operation, startup, shutdown, testing, maintenance, repairs, refueling, in-service inspection and other associated activities. (OPB-12, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Operation” (Эксплуатация).

OPERATION LIMITS (ЭКСПЛУАТАЦИОННЫЕ ПРЕДЕЛЫ) – see DESIGN LIMITS (ПРОЕКТНЫЕ ПРЕДЕЛЫ).

OPERATION WITH DEVIATIONS (ЭКСПЛУАТАЦИЯ С ОТКЛОНЕНИЯМИ) – operation of a nuclear plant with violations of operating limits and conditions, but without violations of safe operation limits or conditions. (OPB-12)

Comment

This term partly corresponds to the IAEA Glossary term “Anticipated operational occurrence” (Oжидаемое при эксплуатации событие). However, they are not fully equivalent. OPB-12 provides clear boundaries for “operation with deviations”. It includes states with violations of operating limits and conditions, but without violations of safe operation limits or conditions. In the IAEA Glossary, “Anticipated operational occurrence” is defined through its expected frequency (at least once in lifetime), absence of serious damage of safety related systems, and prevention of development of such event into design basis accident with the aid of existing design features. Therefore, these two classes of events cannot be equivalent. In case of “Anticipated operational occurrence”, safe operation limits on process parameters can be violated. According to definition, it cannot happen during “operation with deviations”. The state of the plant, in which safe operation limits on process parameters are violated, but safe operation limits on radiation parameters are not, is classified as “pre-accident situation” in the OPB-12. The range of states including both “operation with deviations” and “pre-accident states” is equivalent to the range of “anticipated operational events”.

operational rate of movement (Скорость перемещения рабочая) – velocity of movement of reactivity control actuator during changes of reactivity of the reactor for power control purposes during normal operation. (NP-086-12)

OPERATIONS, TRANSPORTATION AND PROCESS (операции Транспортно-технологические) – see TRANSPORTATION AND PROCESS OPERATIONS (Транспортно-технологические операции).

OPERATIVE CONTOUR OF MCR (ОПЕРАТИВНЫЙ КОНТУР БПУ) – see MCR CONTOURS (КОНТУРЫ БПУ).

OPERATIVE TECHNICAL ACCOUNTING (Оперативно-технический учет) – accounting of products in a technological process based on measurements of certain parameters of the product, supervision of operations and transfers between participants of the process. (NP-030-12)

OPERATOR TRAINING (ПОДГОТОВКА ОПЕРАТОРОВ) – initial training or requalification of operators with operating experience. (NP-003-97)

OPTIMIZATION PRINCIPLE (ПРИНЦИП ОПТИМИЗАЦИИ) – maintaining individual exposure doses and numbers of exposed individuals at the minimum achievable and attainable level taking into account social and economic factors during use of any source of ionizing radiation. (Federal Law No. 3-FZ “On radiation safety of public”)

Comment

A corresponding term in the IAEA Glossary is “Optimization of protection (and safety)” (Оптимизация защиты (и безопасности).

organization, material science (организация Материаловедческая) – see MATERIAL SCIENCE ORGANIZATION (Материаловедческая организация).

ORGANIZATION, OPERATING NUCLEAR POWER PLANT (ОРГАНИЗАЦИЯ, ЭКСПЛУАТИРУЮЩАЯ АС) – see OPERATING UTILITY (ЭКСПЛУАТИРУЮЩАЯ ОРГАНИЗАЦИЯ).

OVERPACK (Транспортный пакет) – enlarged cargo unit made up of several unit loads (packages) with the aid of different packaging methods and means, enabling automation of handling, loading, unloading and warehouse operations. Packaging means include: planar pans, stacking pallets, pallet crates, bin pallets, flexible or rigid binding (straps, ribbons, films, nets), wiring, slick lines and other fixtures. (NP-053-04)

Comment

A corresponding term in the IAEA Glossary is “Overpack” (Транспортный пакет).

OXYDIZERS (ОКИСЛИТЕЛИ) – substances and materials capable of reacting with flammable substances causing combustion and increasing intensity of combustion (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

package (Упаковка) – packaging set with radioactive content prepared for transportation. (NP-053-04)

Comment

A corresponding term in the IAEA Glossary is “Packaging” (Упаковка).

package group (Группа упаковок) – a set of packages that can be stored (transported) without any restrictions on mutual location. (NP-061-05)

Packaging of radioactive waste (Упаковка радиоактивных отходов) – packaging set (container) with RW prepared for transportation, and/or storage, and/or disposal. (NP-002-04, NP-019-2000, NP-020-2000)

packaging set (УПАКОВОЧНЫЙ КОМПЛЕКТ) – set of components required for housing and confining radioactive content. Packaging set can contain one or several containers, sorbents, spacer components, components for radiation protection, cooling, thermal insulation, shock absorbers. It can be in the form of a crate, box or similar containers, a cargo container, reservoir or intermediate bulk container. (NP-053-04)

parametErization of seismic motions of ground (Параметризация сейсмического движения грунта) – description of a seismogram by a set of numeric parameters. There are three independent parameters of seismic oscillations, each of which can be scaled without change of values of other parameters. These parameters are level of impact, predominant frequency of oscillations, and duration of oscillations. All other parameters are closely correlated with the main ones. (RB-006-98)

parts of executive mechanism, movING (части исполнительного механизма Подвижные) –see MOVING PARTS OF EXECUTIVE MECHANISM (Подвижные части исполнительного механизма).

PASSIVE SYSTEM (ELEMENT) (ПАССИВНАЯ СИСТЕМА (ЭЛЕМЕНТ)) – a system (element), functioning of which is related only to the event causing its operation and is independent on operation of any other active system (component), e.g. control system, power source, etc. (OPB-12)

Note: In terms of design attributes, passive systems (elements) are divided into passive systems (elements) with mechanical moving parts (e.g. check valve) and passive systems (element) without movable mechanical parts (e.g. pipelines, vessels, etc.)

Comment

A corresponding term in the IAEA Glossary is “Passive component” (Пассивный компонент). However, between these concepts, and between the concepts of “active system (component)” adopted in the Russian regulatory system and IAEA standard there is a significant difference. In the IAEA Glossary, there is a term “active component” that corresponds to the Russian term “active system (element)”, and operation of which depends on such factors as actuation, mechanical movement and power supply. There are several differences here. Firstly, "component” in the IAEA Glossary is simply a discrete part of a system, i.e. it is the most generic definition. The term “element" in the OPB-12 has special definition, and is not therefore fully equivalent to the term “component”. Secondly, the property of activity in the Russian regulations is not only a property of an element, but also of the system the element is a part of. Thirdly, unlike in the IAEA standards, in the Russian rules and regulations existence of mechanical motion is not an attribute of activity. It depends on the source of the movement – external source of energy or the event causing translocation. In the latter case, the system (element) is considered passive, like in the case of a check valve.

penetration (sealed) (Проходка (герметичная)) – component of containment designed to enable entry of pipelines, air conduits, electric cables, ion chamber channels, movable parts of valve drives, etc. into the accident localization zone (maintaining leaktightness of the leaktight enclosure). (NP-010-11)

period of potential hazard of radioactive wastes (Период потенциальной опасности радиоактивных отходов) – period, after which specific radioactivity of the nuclides contained in the RW decreases to the levels, justifying their exemption from radiation safety regulations and standards. (NP-058-04, Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

personnel (Персонал) – individuals working with technogenic sources of radiation (group A), or working at a radiation facility or within its sanitary protection zone and affected by technogenic sources of radiation (Group B). (NRB-99/2009, PRB AS-99)

Operative personnel of nuclear plant (Персонал АС оперативный) – operating personnel from among the plant employees on shift and allowed to control plant operation processes. (NP-003-97)

Operating personnel of nuclear plant (Персонал АС эксплуатационный) – plant employees performing its operation. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Operating personnel” (Эксплуатационный персонал ).

Security personnel (Персонал физической защиты) – individuals performing the function of safeguarding and physical protection of RS and RW during transportation. (NP-073-11)

PERSONNEL ERROR (ОШИБКА ПЕРСОНАЛА) – single inadvertent erroneous action while controlling equipment or single omission of correct action, or single inadvertent erroneous action during maintenance or repair of plant systems and components. (OPB-12)

phase characteristics (Характеристики фазовые) – phase angles (phase spectra), characterizing phase shifts of seismic oscillations for different frequencies. (RB-006-98)

physical barrier (Физический барьер) – see BARRIER (барьер).

physical barrier DURING DECOMMISSIONING OF A POWER UNIT (Физический барьер ПРИ ВЫВОДЕ ИЗ ЭКСПЛУАТАЦИИ БЛОКА АС) – see BARRIER (барьер).

PHYSICAL protection LEVEL (Уровень физической защиты) – result of assessment of potential radiation hazard and possible consequences of unauthorized actions against cargo containing radioactive substances or radioactive source. (NP-073-11)

PHYSICAL SEPARATION (РАЗДЕЛЕНИЕ ФИЗИЧЕСКОЕ) – use of barriers or spatial segregation to prevent damaging factors from one systems or components of the nuclear plant to other systems or components. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Physical separation” (Физическое разделение).

pilot operated relief valve (Устройство импульсно-предохранительное) – a component performing the function of relief valve consisting of interacting main and pilot valves (the latter can be in-built or externally mounted). (NP-068-05)

PILOT OPERATION (ОПЫТНО-ПРОМЫШЛЕННАЯ ЭКСПЛУАТАЦИЯ) – stage of plant commissioning between connection to the grid and acceptance for commercial operation. (OPB-12)

pilot valve (Клапан импульсный) – see VALVES (АРМАТУРА).

pipeline (Трубопровод) – set of components and assembly units consisting of pipes, tubes and their parts (headers, T-joints, nozzles, taps, chokes). (PNAE G-7-008)

pneumatic distributor (Пневмораспределитель) – a component for controlling pneumatic drive operation.

PNEUMATIC DRIVE (Пневмопривод) – drive, using energy of compressed air. (NP-068-05)

PNEUMATIC valve (Пневмоарматура ) – see VALVES (АРМАТУРА).

PORE (ПОРА) – round shape gas-filled cavity in the metal of weld or deposited metal. (PNAE G-7-010-89)

position indicator (Датчик положения) – an instrument generating output signal with information about the position of a control rod. (NP-086-12)

POWER TERMINAL GLANDS (ЭЛЕКТРОВВОД) – appliance for entering cables into electric drives. (NP-086-12)

POWER UNIT DECOMMISSIONING DESIGN (ПРОЕКТ вывода из эксплуатации блока АС) – document developed based on the decommissioning program and integrated engineering and radiological survey of the unit, defining specific decommissioning activities, technology of their performance, sequence, and necessary human, financial and material resources for each stage of decommissioning. (NP-012-99)

POWER UNIT STARTUP (ПУСК БЛОКА АС)

Initial criticality (Физический пуск блока АС) – stage of commissioning of a nuclear power unit including loading nuclear fuel into the core, reaching critical state of the reactor and performing the necessary physical experiments and measurements at the power level, at which heat is removed from the reactor through natural heat losses (dissipation). (OPB-12)

Power startup of a unit (Энергетический пуск блока АС) – stage of commissioning between attaining initial criticality and beginning of pilot operation. (OPB-12)

POWER UNIT UNDER DESIGN (Проектируемый блок АС) – see NUCLEAR POWER UNIT (БЛОК АС).

PRE-ACCIDENT CONDITION (ПРЕДАВАРИЙНАЯ СИТУАЦИЯ) – state of nuclear plant, characterized by violation of safe operation limits or conditions, which did not evolve into accident. (OPB-12, NP-003-97)

predicable attributes (признаки Атрибутивные) – attributes of an object that can be visually or instrumentally checked. (NP-030-12)

pre-installation test facility (Стенд предмонтажных проверок) – facility for adjustment, regulation and testing of actuators. (NP-086-12)

PREPARATION FOR POWER UNIT DECOMMISSIONING (ПОДГОТОВКА к выводу из эксплуатации блока АС) – complex of organizational and technical measures, both before and after ultimate shutdown of the unit, preceding decommissioning of the unit and performed under the unit operation license. (NP-012-99)

PRESCRIPT (ПРЕДПИСАНИЕ) – a document, properly issued by authorized representatives of the Russian nuclear safety regulatory authority to the authorities of nuclear power industry organizations containing mandatory requirements to eliminate safety deficits and prescribing the deadline for implementation of the requirements. (RD-03-43-98)

presence of radioactive wastes and radioactive materials, actual (наличие радиоактивных веществ и радиоактивных отходов Фактическое)) – see ACTUAL PRESENCE OF RADIOACTIVE WASTES AND RADIOACTIVE MATERIALS (Фактическое наличие радиоактивных веществ и радиоактивных отходов).

pressure (Давление)

Maximum normal operating pressure (максимальное нормальное рабочее давление) – maximum pressure exceeding atmospheric pressure at the sea level that can occur in the leaktight packaging system over one year assuming ambient temperatures and sun radiation, without venting or pressure relief, external cooling or control measures during transportation. (NP-053-04)

Comment

This term is fully equivalent to the same term in the IAEA Glossary - “Maximum normal operating pressure” (Максимальное нормальное рабочее давление).

Operating pressure (давление рабочее) – maximum excess pressure of a fluid in a pipeline or component during normal operation, taking into account hydrostatic pressure. (NP-068-05)

Rated pressure (for leaktight containment) (давление расчетное (для герметичного ограждения)) – excess pressure of the media within the accident localization zone determined by the designer organization, under which strength of the containment is ensured and the leaks from the enclosure do not exceed the design limits. (NP-010-11)

Rated pressure (давление расчетное) – maximum excess pressure of a fluid in a pipeline or component used for selection of dimensions of components critical for strength, at which normal operation at the rated temperature is allowed. (NP-068-05)

PRE-STARTUP ADJUSTMENT ACTIVITIES (ПРЕДПУСКОВЫЕ НАЛАДОЧНЫЕ РАБОТЫ) – stage of commissioning of a power unit, during which constructed and installed plant systems and components are brought into the state of readiness for operation with verification of compliance with design criteria and requirements. The stage ends with readiness of the unit for initial criticality. (OPB-12)

PRIMARY CIRCUIT (ПЕРВЫЙ КОНТУР) – see REACTOR COOLANT CIRCUIT (PRIMARY CIRCUIT) (КОНТУР ТЕПЛОНОСИТЕЛЯ РЕАКТОРА (ПЕРВЫЙ КОНТУР)).

PRIMARY EVENT (первичное СОБЫТИЕ) – same as BASIC EVENT (БАЗИСНОЕ СОБЫТИЕ).

PRIMARY FRAGMENTS (ПЕРВИЧНЫЕ ОСКОЛКИ) – see FRAGMENTS (ОСКОЛКИ).

primary means of firefighting (ПЕРВИЧНЫЕ СРЕДСТВА ПОЖАРОТУШЕНИЯ) – means of firefighting used at the initial stage of development of fire. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

principle of two (three) persons (ПРАВИЛО ДВУХ (ТРЕХ) ЛИЦ) – group work principle (inclusively, during opening and security check of rooms) based on the requirement of simultaneous presence at one workplace or in one room of at least two (three) individuals in order to minimize the risk of unauthorized actions. (NP-034-01)

PROBABILISTIC MODEL OF A NUCLEAR POWER PLANT (Вероятностная модель АС) – interrelated set of mathematical models of accident sequences, systems, components, personnel actions, as well as databases with probabilistic parameters of initiating events, system and component reliability, common cause failures, personnel reliability and other initial data required for assessment of probabilistic parameters of the plant safety performance. (RB-032-04, RB-024-11)

PROBABILISTIC SAFETY ANALYSIS (ВЕРОЯТНОСТНЫЙ АНАЛИЗ безопасности) – see ANALYSIS (АНАЛИЗ).

probabilistic safety performance parameter (Вероятностный показатель безопасности) – the value of radioactivity source damage probability, or the value of probability of release of radioactive substance into environment. (RB-032-04)

probability of fault-free operation (Вероятность безотказной работы) – probability of occurrence of no failures of a component (facility) within the given operation time. (NP-068-05)

PROCESS FLUID (ТЕХНОЛОГИЧЕСКАЯ СРЕДА) – substances and materials circulating in process equipment (process system). (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

PROCESS VENTS (СДУВКИ ТЕХНОЛОГИЧЕСКИЕ) – vapor mixtures, gases and (or) aerosols removed from the process equipment components. (NP-021-2000)

proportional valve (Клапан пропорциональный) – see VALVES (АРМАТУРА).

PROTECTION (ЗАЩИТА) – control functions aimed at preventing:

a) damage, failures or destruction of the protected equipment or automation devices;

b) operation of faulty equipment or automation devices;

c) undesirable personnel actions as regards control. (NP-026-04)

Comment

The IAEA Glossary defines the term “Protection” (Защита) only in the sense of radiation protection. In the sense of control function, this term is only used in combination with other words. For example, “Protection System” (система защиты) or “Protective Action” (Защитное действие).

Emergency protection (Аварийная защита)

• safety function consisting in fast transfer of the nuclear reactor to subcritical state and maintaining subcriticality;

• a set of safety systems performing emergency protection function. (NP-082-07)

Comment

This term (equivalent to the meaning in the first bullet) corresponds to the term “Scram” (Аварийный останов) or “Rapid Emergency Shutdown” (Быстрый аварийный останов) in the IAEA Glossary.

защита) or “Radiological Protection” (Радиологическая защита).

Engineered protection (инженерная защита) – a set of engineered systems protecting people, buildings or structures, territories on which construction, maintenance and operation of building or structure will be performed, against hazardous natural phenomena and processes and (or) technogenic impacts, terrorist threats, as well as prevention and (or) mitigation or consequences of hazardous natural phenomena and processes and (or) technogenic impacts or terrorist threats. (Federal Law No. 384-FZ “Technical Specifications on safety of buildings and structures”)

Engineered protection of nuclear facility against external impacts (инженерная защита объекта использования атомной энергии от внешних воздействий) – a complex of measures, means of protection, space-and-planning solutions, organizational and technical measures aimed at ensuring stability and safety of a nuclear facility, protection of its buildings, structures, systems, components, employees, and at prevention of accidents associated with discharge of radionuclides into atmosphere or effluent of radionuclides into hydrosphere or geoshpere caused by external impact of natural and (or) technogenic origin, as well as at prevention or mitigation of social and economic damage. (NP-064-05)

Engineered protection of nuclear facility site (инженерная защита территории объекта использования атомной энергии) – a set of measures and means aimed at preventing or mitigating negative effects of hazardous hydrometeorological, geological or engineering-geological phenomena, processes and factors on the nuclear facility site. (NP-064-05)

Physical protection (Физическая защита) – a combination of organizational measures, engineered systems and actions of the security personnel aimed at preventing theft of nuclear materials or acts of sabotage against such materials and vehicles for their transportation. (NP-053-04)

Comment

A corresponding term in the IAEA Glossary is “Physical protection” (Физическая защита).

Physical protection of a nuclear plant (Физическая защита АС) – engineered and organizational measures to ensure safe-keeping of nuclear and radioactive materials existing at the plant, to prevent unauthorized access to the plant territory or to nuclear material and radioactive substances, and to timely detect and terminate acts of sabotage or terrorism jeopardizing the plant safety. (OPB-12)

See the previous comment.

Protection of personnel (employees) (защита работников (персонала)) – a set of technical and organizational measures providing for the required level of safety of personnel directly involved in operation of a nuclear facility. (NP-064-05)

Comment

A corresponding term in the IAEA Glossary is “Radiation Protection” (радиационная

Warning protection (предупредительная защита) – a function performed by normal operation control system of the nuclear power unit in order to prevent actuation of emergency protection and (or) violation of safe operation limits and conditions. (NP-082-07)

protection and control train (Комплект аппаратуры AЗ) – instrumentation and controls of protection and control system, performing plant control and monitoring function in the scope, specified by the plant design. (NP-082-07)

protection chamber (Защитная камера) – a room, specially equipped for dismantling, cutting, investigation and other operations performed remotely with SNF. (NP-061-05)

protection feature (Устройство предохранительное)²² – a feature protecting components of electromechanical executive mechanism against electrical overload. (NP-086-12)

PROTECTION SAFETY SYSTEMS (COMPONENTS) (ЗАЩИТНЫЕ СИСТЕМЫ (ЭЛЕМЕНТЫ) БЕЗОПАСНОСТИ) – see SAFETY SYSTEMS (COMPONENTS) (СИСТЕМЫ (ЭЛЕМЕНТЫ) БЕЗОПАСНОСТИ).

protective barriers (ЗАЩИТНЫЕ БАРЬЕРЫ ) – see БАРЬЕР (BARRIER).

PROTOTYPE UNIT (ЭНЕРГОБЛОК-ПРОТОТИП) – specific unit of a power plant taken as a reference for development of full scope simulator, with the use of the unit design, startup and operating documentation. (NP-003-97)

PUBLIC (Население) – all individuals, including personnel not involved in operations with ionizing radiation sources. (NRB-99/2009, PRB AS-99)

QUALIFICATION (КВАЛИФИКАЦИЯ) – level of training of plant personnel, including basic special education, professional knowledge, skills, and experience, ensuring quality and safety of operation of nuclear power plant. (OPB-12)

QUALITY (КАЧЕСТВО) – combination of properties and characteristics of services and equipment, determining their ability to satisfy the established requirement according to their purpose. (RB-003-98)

quality assurance (Обеспечение качества) – a part of coordinated organization management and control activities intended to create confidence that quality requirements shall be satisfied. (NP-090-11)

Comment

This term corresponds to the IAEA Glossary term “Quality assurance (QA)” (Обеспечение качества (ОК)).

quality assurance program (Программа обеспечения качества) – document defining a set of organizational and technical quality assurance measures affecting nuclear facility safety. (Refined definition of NP-090-11)

Comment

This term corresponds to the IAEA Glossary term "Quality assurance (QA)” (Обеспечение качества (ОК)).

quality policy (Политика в области качества) – general intentions and lines of activities of organization in the area of quality, officially formulated by senior management. (NP-090-11)

quota (Квота) – part of the dose limit established by the rules for limiting public exposure from gaseous and aerosol emissions and liquid effluents from nuclear power plant. (PRB AS-99)

RADIATION ACCIDENT (РАДИАЦИОННАЯ АВАРИЯ) – see ACCIDENT (АВАРИЯ).

radiation exposure effects (Эффекты облучения)

Deterministic effects of exposure (детерминированные эффекты облучения) – clinically identifiable harmful biological effects caused by ionizing radiation, with respect to which existence of a threshold is assumed below which there is no effect, and above which its severity is a function of the dose. (NRB-99/2009)

Stochastic effects of exposure (стохастические эффекты облучения) – harmful biological effects caused by ionizing radiation having no dose threshold of occurrence, probability of occurrence of which is proportional to the dose, and severity of which is independent of the dose. (NRB-99/2009)

Comment

A corresponding term in the IAEA Glossary is “Стохастический эффект” (Stochastic effect).

radiation EXPOSURE, medical (медицинское Облучение) – see MEDICAL RADIATION EXPOSURE (Облучение медицинское).

radiation hazard sign (Знак радиационной опасности) – a sign that attracts attention to objects of potential or actual hazard of harmful influence of ionizing radiation on humans. The sign is a warning one. (PRB AS-99)

RADIATION HAZARDOUS ACTIVITIES (Радиационно-опасные работы) – work in the conditions of actual or potential radiation hazard, when radiation conditions at the location of the activities are such that, under standard exposure condition, individual effective dose for an employee can exceed 20 mSv per year. (PRB AS-99)

radiation hygienic passport of organization (Паспорт организации радиационно-гигиенический) – document, characterizing radiation safety state in the organization and containing recommendations for its enhancement. (PRB AS-99)

radiation level (Уровень излучения) – corresponding dose rate expressed in milliSivert per hour. (NP-053-04)

RADIATION MONITORING (радиационный Контроль) – obtaining information about radiation situation in the organization, environment, and about levels of exposure of people (includes dosimetric and radiometric monitoring). (NRB-99/2009, PRB AS-99)

Radiation object (Объект радиационный) – a physical object (structure, building, enclosed complex of buildings) where handling of technogenic sources of ionizing radiation is carried out. (NRB-99/2009)

radiation protection program (Программа радиационной защиты) – program of measures to ensure planning and accounting radiation protection actions applied systematically during transportation of radioactive materials. (NP-053-04)

Comment

A corresponding term in the IAEA Glossary is “Radiation protection program” (Программа радиационной защиты). However, the definition of the IAEA Glossary does not specify the nature of actions the term applies to, and in particular, transportation of radioactive materials.

radiation risk (радиационный РИСК) – see RISK (РИСК).

RADIATION SAFETY OF PUBLIC (Радиационная безопасность населения) – see SAFETY (БЕЗОПАСНОСТЬ).

radiation sources (Радиационные источники) – see SOURCE (ИСТОЧНИК).

radioactive contamination (радиоактивное Загрязнение) – presence of radioactive substances on the surface, inside materials, in the air, in the human organism or in other location in the amount exceeding the levels established by sanitary rules. (NRB-99/2009, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Contamination” (Радиоактивное загрязнение).

radioactive content (Радиоактивное содержимое) – radioactive substance together with any radioactive or activated solids, liquids or gases in packaging. (NP-053-04)

radioactive exposure (Облучение) – impact of ionizing radiation on humans. (NRB-99/2009, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Exposure” (Облучение).

Emergency exposure (Облучение аварийное) – exposure caused by radiological accident. (NRB-99/2009)

Comment

A corresponding term in the IAEA Glossary is “Emergency exposure” (Аварийное облучение).

External exposure (Облучение внешнее) – exposure of human body organs or tissues caused by incoming radiation. (PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “External exposure” (Внешнее облучение).

Internal exposure (Облучение внутреннее) – exposure of human body organs or tissues caused by intake of radionuclides. (PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Internal exposure” (Внутреннее облучение).

Medical exposure (Облучение медицинское) – exposure to ionizing radiation of:

a) patients undergoing diagnostic or therapeutic medical procedures;

b) individuals (except medical personnel), who knowingly and voluntarily assist in patient care in hospitals or at home;

c) individuals undergoing medical tests due to their professional occupation or as a part of juridical medical procedures;

d) individuals undergoing prophylactic medical tests or investigations. (NRB-99/2009)

Comment

A corresponding term in the IAEA Glossary is “Medical exposure” (Медицинское облучение).

Natural exposure (Облучение природное) – exposure caused by natural sources of radiation. (NRB-99/2009, PRB AS-99)

Occupational exposure (Облучение профессиональное) – exposure of personnel during operations with ionizing radiation sources. (NRB-99/2009)

Comment

A corresponding term in the IAEA Glossary is “Occupational exposure” (профессиональное облучение).

Planned increased exposure (Повышенное планируемое облучение) – planned exposure of personnel in the doses exceeding the established main limits in order to prevent development of radiation accident or mitigate its consequences. (NRB-99/2009)

Production exposure (Облучение производственное) – exposure of employees caused by all technogenic and natural sources of ionizing radiation during production activities. (NRB-99/2009, PRB AS-99)

Technogenic exposure (Облучение техногенное) – exposure from technogenic sources in normal and emergency conditions, except for medical exposure of patients. (NRB-99/2009, PRB AS-99)

RADIOACTIVE MATERIAL (Радиоактивный материал) – nuclear material and (or) radioactive substance. The term is used in the NP-053-04 as a generalizing one, when there is no difference in requirements to transportation of radioactive substances and nuclear materials. Products based on radioactive materials are also understood as such materials. (Refined definition of NP-053-04)

Comment

A corresponding term in the IAEA Glossary is “Radioactive material” (Радиоактивный материал).

Low dispersible radioactive material (Радиоактивный материал с низкой способностью к рассеянию (РМНР)) – solid radioactive materials not in the form of powder, or hermetically sealed solid radioactive material with limited dispersion ability consistent with the requirements of the present rules to low dispersible radioactive materials. (NP-053-04)

Comment

A corresponding term in the IAEA Glossary is “Low dispersible radioactive material” (Радиоактивный материал с низкой способностью к рассеянию).

Special form radioactive material (Радиоактивный материал особого вида (РМОВ)) – non-scattering solid or hermetically sealed radioactive material consistent with the requirements of NP-053-04 to special form radioactive materials. (NP-053-04)

Comment

A corresponding term in the IAEA Glossary is “Special form radioactive material” (Радиоактивный материал особого вида).

radiOACTIVE source (Радиоактивный источник) – see SOURCE (ИСТОЧНИК).

radioactive substance and radioactive waste accounting (Учет радиоактивных веществ и радиоактивных отходов) – determination of accounting information on RS and RW, production and maintenance of accounting and reporting documentation. (NP-067-11)

radioactive substance and radioactive waste control (Контроль радиоактивных веществ и радиоактивных отходов) – monitoring of presence and translocations of RW and radioactive materials, including control of access to them, equipment and information, surveillance of RW and radioactive materials, verification of authorized placement and translocations of RW and radioactive materials. (NP-067-11)

radioactive substances of defense purpose (Радиоактивные вещества оборонного назначения) – see substance (substances) (ВЕЩЕСТВА (ВЕЩЕСТВО)).

radioactive surface contamination (Радиоактивное загрязнение поверхности) – presence of radioactive materials of technogenic origin on the surface of transportation vehicles, cargo containers, packaging and other objects in the amounts exceeding 0.4 Bq/sm² for beta, gamma and alpha sources with low toxicity and 0.04 Bq/sm² for all other alpha sources. (NP-053-04)

RADIOACTIVE WASTE CONDITIONING (Кондиционирование радиоактивных отходов) – processes bringing radioactive wastes into physical form and state appropriate for ultimate disposal in accordance with the acceptance criteria. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

Comment

A corresponding term in the IAEA Glossary is “Conditioning” (Кондиционирование).

Liquid (solid) radioactive waste conditioning (Кондиционирование жидких (твердых) радиоактивных отходов) – transfer of RW to the forms suitable for safe storage and (or) transportation, and (or) disposal. Conditioning can include transfer of LRW (SRW) into a stable form, placement of LRW (SRW) into containers or packaging. (NP-058-04, NP-072-06, NP-002-04)

RADIOACTIVE WASTE CONTAINER (Контейнер для радиоактивных отходов) – vessel (component of packaging set) used for RW collection and (or) transportation, and (or) disposal. (NP-058-04) (NP-002-04)

Comment

A corresponding term in the IAEA Glossary is “Container, Waste” (Контейнер отходов)

radioactive waste disposal system (Система захоронения радиоактивных отходов) – combination of the natural geological formation, structures for ultimate disposal of solid or liquid radioactive wastes and the disposed wastes. (NP-058-04)

radioactive waste management (Обращение с радиоактивными отходами) – all types of activities associated with collection, transportation, reprocessing, conditioning and (or) disposal of RW. (NP-002-04, NRB-99/2009, PRB AS-99, Federal Law No.190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

Comment

This term corresponds to the IAEA Glossary term “Waste management, radioactive" (Обращение с отходами, радиоактивными).

Gaseous radioactive waste management (Обращение с газообразными радиоактивными отходами) – types of activities, associated with collection, hold-up, filtration, adsorption (reprocessing) of GRW. (NP-058-04)

Liquid (solid) radioactive waste management (Обращение с жидкими (твердыми) радиоактивными отходами) – types of activities associated with collection, transportation, reprocessing, conditioning and (or) disposal of LRW (SRW). (NP-058-04)

RADIOACTIVE WASTE MANAGEMENT OPERATOR, NATIONAL (оператор по обращению с радиоактивными отходами Национальный) – see NATIONAL RADIOACTIVE WASTE MANAGEMENT OPERATOR (Национальный оператор по обращению с радиоактивными отходами).

RADIOACTIVE WASTE MANAGEMENT organization, specialized (оператор по обращению с радиоактивными отходами Национальный) – see SPECIALIZED RADIOACTIVE WASTE MANAGEMENT ORGANIZATION (Специализированная организация по обращению с радиоактивными отходами).

RADIOACTIVE WASTE MANAGEMENT QUALITY ASSURANCE (ОБЕСПЕЧЕНИЕ качества при обращении с РАО) – planned and systematically performed activities aimed at all the RW handling and management activities affecting nuclear and radiation safety being performed in compliance with the requirements of federal rules and reulations and other regulatory documents, and the results of such activities being compliant with the existing requirements. (NP-019-2000, RB-003-98)

radioactive waste management system (Системы обращения с радиоактивными отходами) – process systems designed for collection and (or) storage, and (or) reprocessing, and (or) conditioning, and (or) transportation of RW. (NP-002-04)

RADIOACTIVE WASTE REGISTRY (Реестр радиоактивных отходов) – systematic compilation of documented information about radioactive wastes obtained as a result of primary registration of radioactive wastes and their locations, as well as information about the radioactive wastes transferred to the national operator. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

radioactive waste reprocessing (Переработка радиоактивных отходов) – process operation associated with change of aggregate state and (or) reduction of volume, and (or) change of physical properties of RW during their preparation for storage or disposal. (NP-002-04, RB-014-2000, Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

Liquid radioactive waste reprocessing (Переработка жидких радиоактивных отходов) – process operation associated with change of aggregate state and (or) reduction of volume, and (or) change of physical or chemical properties of LRW. (NP-058-04, NP-019-2000)

Solid radioactive waste reprocessing (Переработка твердых радиоактивных отходов) – process operations associated with change of form and decrease of volume of SRW. (NP-058-04, NP-019-2000)

RADIOACTIVE WASTE STORAGE (DISPOSAL) FACILITIES (ПУНКТЫ ХРАНЕНИЯ (ЗАХОРОНЕНИЯ) РАДИОАКТИВНЫХ ОТХОДОВ)

Deep radioactive waste disposal facility (Пункт глубинного захоронения радиоактивных отходов) – a radioactive waste disposal facility including a structure located at the depth of more than one hundred meters from the ground surface. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

Long term radioactive waste storage facility (Пункт долговременного хранения радиоактивных отходов) – radioactive waste storage facility, operating lifetime of which is defined by the design, but no decommissioning activities or actions are prescribed. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

Near-surface radioactive waste disposal facility (Пункт глубинного захоронения радиоактивных отходов) – a radioactive waste disposal facility including a structure located on the ground surface or at the depth of no more than one hundred meters from the ground surface. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

Radioactive waste disposal facility (Пункт захоронения радиоактивных отходов) – stationary object (objects) and (or) structure (structures) designed for disposal of radioactive wastes located within the territory defined by the design and equipped with all the necessary systems and components for RW handling. (NP-058-04, Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

Special radioactive waste conservation facility (Пункт консервации особых радиоактивных отходов) – natural or technogenic object containing special radioactive wastes, having safety barriers isolating radioactive wastes from the environment during the design lifetime of the facilities. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

Special radioactive waste storage facility (Пункт размещения особых радиоактивных отходов) – natural or technogenic object containing special radioactive wastes non-isolated from the environment, or a facility containing radioactive waste, period of isolation of which was not established. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

Temporary radioactive waste storage facility (Пункт временного хранения радиоактивных отходов) – radioactive waste storage facility, operating lifetime of which is defined by the design, as well as decommissioning activities and actions. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

radioactive waste storage (Хранение радиоактивных отходов) – temporary storage of radioactive wastes in the tanks (repositories) providing radiation protection and confinement of RW with intention of their subsequent withdrawal. (NP-058-04, NP-002-04)

Comment

A corresponding term in the IAEA Glossary is “Storage” (Хранение).

radioactive waste storage facility (Хранилище радиоактивных отходов) – stationary object (facility), designed for storing radioactive wastes, located within the territory defined by the design and equipped with systems and tools required for RW handling. (NP-058-04)

radioactive waste storage facility (Хранилище радиоактивных отходов)²³ – engineered facilities for temporary storage of RW with possibility of subsequent withdrawal for transportation to disposal sites. (NP-002-04)

radioactive wastes (Отходы РАДИОАКТИВНЫЕ) – substances in any aggregate states, materials, products, equipment, objects of biological origin, radionuclide sources, contaminated environmental objects, contaminated soil containing radionuclides in the amounts exceeding the levels prescribed by radiation safety standards, which cannot be further used. (NP-058-04, NP-002-04, NP-019-2000, NP-020-2000, RB-023-02, NRB-99/2009)

Comment

A corresponding term in the IAEA Glossary is “Wastes, radioactive” (Отходы, радиоактивные).

Gaseous radioactive wastes (Отходы газообразные радиоактивные) – RW in the form of aerosols, noble gases, vapors of iodine and its compounds. (NP-002-04)

Liquid radioactive wastes (Отходы жидкие радиоактивные) – RW in liquid form (water or organic solutions) or in the form of pulps, containing dissolved or suspended radionuclides. (NP-002-04)

Radioactive wastes generated during mining and processing ores of radioactive materials and other minerals (Отходы радиоактивные, образующиеся при добыче и переработке руд радиоактивных веществ и других полезных ископаемых) – rock, ore, enrichment and leaching wastes, slums, process solutions and contaminated materials, equipment, soil containing radionuclides in the amounts exceeding the levels specified by radiological safety standards, which are not further usable, extracted from underground and placed in the tail storages or rock depositaries. (NP-058-04)

Comment

This term corresponds to the IAEA Glossary term “Mining and milling waste (MMW)” (Отходы добычи и переработки (ОДП)).

Solid radioactive wastes (Отходы твердые радиоактивные) – RW in the solid form. (NP-002-04)

Solidified radioactive wastes (Отходы отвержденные радиоактивные) – LRW transferred into solid form. (NP-002-04)

radioactive wastes (радиоактивные Отходы) – see WASTES, RADIOACTIVE (Отходы радиоактивные)

rate of EMISSION, effluent (Мощность выброса, сброса) – radioactive emission or effluent per unit of time. (PRB AS-99)

RATE OF NEUTRON FLUENCE ACCUMULATION (СКОРОСТЬ НАКОПЛЕНИЯ ФЛЮЕНСА БЫСТРЫХ НЕЙТРОНОВ) Ф – time-averaged accumulation rate of fast neutrons (e.g. campaign or irradiation period) reduced to the nominal level of reactor thermal power. (RB-018-01)

rated height of angular weld (Расчетная высота углового шва) – length of the perpendicular dropped from the junction point of welded components to the direct line connecting the edges of the surface in one cross section or on a tangent to the surface of the welded joint parallel to the above specified line. (PNAE G-7-010-89)

rated rarefaction (for leaktight enclosure) (Разрежение расчетное (для герметичного ограждения)) – vacuumetric pressure of media within the accident localization zone, specified by the designer organization, under which strength of the leaktight enclosure is guaranteed. (NP-010-11)

rated temperature (Температура расчетная)²⁴ – value of temperature of media in the accident localization zone, or temperatures of the components of leaktight enclosure (containment) specified by design (architect engineering) organization, at which operability of the containment is ensured. (NP-010-11)

reactimeter (Реактиметр) – instrument (measuring complex), recording changes of neutron flux (neutron power) with the aid of detectors located inside or outside of the core and performing initial signal processing in order to obtain measured reactivity based on the previously known law or algorithm. The complex can include statistical processing of primary data, accounting for the background current of the detectors for obtaining final reactivity values. (RB-074-12)

reactivity (Реактивность) – measure of difference of neutron breeding factor from 1.

where k_эф1,2 – effective breeding coefficients of initial and final states; r is also known as calculated reactivity. Effective breeding coefficients are determined from the solution of the stationary problem with the aid of software models of the reactor core, and represent the ratio of total generation of neutrons to total absorption and escape of them. (RB-074-12)

Comment

A corresponding term in the IAEA Glossary is “Reactivity, ρ” (Реактивность, ρ).

reactivity coefficient (Коэффициент реактивности) – reactivity effect relative to the magnitude of change of a corresponding parameter, assuming that other parameters are constant. (RB-074-12)

reactivity control rod (Орган воздействия на реактивность) – a component, containing solid parts, change of location of which enables change of reactivity in the reactor core (NP-086-12)

reactivity effect (Эффект реактивности) – changes of reactivity caused by change of one of parameters of the reactor unit, e.g. power, average temperature of fuel or coolant, concentration of liquid absorber (boric acid), xenon concentration. The interval of changes of the parameter, and, wherever necessary, spatial distribution function are to be specified. (RB-074-12)

Comment

A corresponding term in the IAEA Glossary is “Reactivity, ρ” (Реактивность, ρ).

reactivity, obtained as a result of analytical modeling (Реактивность, полученная в результате расчетного моделирования измерения) – reactivity, obtained by analytical modeling of reactimeter, parameters of which are recommended to select so that they coincide with the parameters of the reactimeter used for actual measurements. The following conditions are recommended to comply with. Distribution of neutron flux (neutron power) in the core is calculated with the aid of software for joint modeling of non-stationary distribution of full scale neutron field and heat generation. The values of neutron flux in the locations of ex-core detectors of the reactimeter are recommended to be calculated with the aid of software with known uncertainty. (RB-074-12)

REACTOR COOLANT CIRCUIT (PRIMARY CIRCUIT) (КОНТУР ТЕПЛОНОСИТЕЛЯ РЕАКТОРА (ПЕРВЫЙ КОНТУР)) – circuit, including the pressurizer system, designed for coolant circulating through the reactor core in the operating modes and conditions specified by the design. (OPB-12)

reactor core damage, severe (повреждение активной зоны реактора Тяжелое) – see REACTOR CORE DAMAGE, SEVERE (Тяжелое повреждение активной зоны реактора).

REACTOR CORE REFUELING (Перегрузка активной зоны) – nuclear hazardous activities associated with loading, unloading and translocation of fuel (fuel assemblies), control rods and other components affecting reactivity for the purpose of maintenance, replacement or removal. (Refined definition of NP-082-07)

REACTOR PLANT (РЕАКТОРНАЯ УСТАНОВКА) – complex of systems and components of a nuclear plant designed for transforming nuclear energy into heat, including reactor and systems directly associated with it and necessary for its normal operation, emergency cooling, emergency protection and maintaining safe state, conditional to performance of auxiliary and support functions by other systems of the plant. Boundaries of the reactor islet are defined for each nuclear plant in the design. (OPB-12, NP-082-07)

Comment

A corresponding term in the IAEA Glossary is a broader term “Nuclear facility” (Ядерная установка), covering all types of nuclear facilities.

REACTOR POWER HISTORY (ИСТОРИЯ МОЩНОСТИ РЕАКТОРА) – changes of total thermal power of the reactor in time with respect to rated power. (RB-018-01)

reactor shutdown system (Система остановки реактора) – system designed for transferring reactor to subcritical state and maintaining subcriticality with the aid of reactivity control means. (NP-082-07)

REAL TIME SCALE (РЕАЛЬНЫЙ МАСШТАБ ВРЕМЕНИ) – modeling of dynamic processes with the same interrelations between time, sequence, duration, rate and acceleration, as in real process. (NP-003-97)

recession between BEADS (Углубление между валиками) – longitudinal depression between two neighboring beads (evaluated by maximum depth). (PNAE G-7-010-89)

RECORDING (РЕГИСТРАЦИЯ) – information function, purpose of which is to record the information on a carrier allowing its storage. (NP-026-04)

RED LINES (КРАСНЫЕ ЛИНИИ) – lines designating the existing or planned (modified, added) boundaries of common use territories, boundaries of land allotment on which electric power transmission lines, communication lines (including cable lines), pipelines, motorways, railroads or other similar facilities (objects) are located. (“Town Building Code of the Russian Federation” No. 190-FZ)

REDUNDANCY PRINCIPLE (ПРИНЦИП РЕЗЕРВИРОВАНИЯ (ИЗБЫТОЧНОСТИ)) – principle of reliability enhancement by means of using several systems and components (identical or different) for performing the intended safety function regardless of the state, including failures, of any of them. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Redundancy” (Избыточность).

REFERENCE LEVEL (контрольный Уровень) – a value of monitored doze, dose rate, radioactive contamination established for operative radiation monitoring purposes in order to maintain the achieved level of radiation safety and enable further decrease of exposure of personnel and general public, as well as radioactive contamination of environment. (NRB-99/2009, PRB AS-99)

Comment

The IAEA Glossary contains the same term “Reference level” (Контрольный уровень). However, it is defined in a broader and more generic sense.

REFERENCE STANDARD of a unit (Эталон единицы величины) – appliance designed for reproduction, storage and transfer of measurement unit of a parameter. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

REFINEMENT OF GENERAL SEISMIC ZONING (УТОЧНЕНИЕ ОСР) – complex of geological, geophysical, geodynamic and seismological activities performed to identify geodynamic zones, active faults, zones of possible earthquake origin and determine their parameters, justify nuclear plant siting within the limits of a uniform block of earth crust without active faults, refinement of seismicity of the area and determination of parameters of SSE and DBE at the plant site for average ground types (NP-031-01)

refueling (Перегрузка) – see reactor core refueling (Перегрузка активной зоны).

regulating valve (Клапан регулирующий) – see VALVES (АРМАТУРА).

REGULATORY AUTHORITY (РЕГУЛИРУЮЩИЙ ОРГАН) – federal executive authority authorized, according to the Russian legislation, to perform state safety regulatory functions and supervise the use of nuclear energy, and acting as regulatory authority in terms of the Nuclear Safety Convention. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Regulatory Authority” (Регулирующий орган).

REMOTE CONTROL (УПРАВЛЕНИЕ ДИСТАНЦИОННОЕ) – control of an object from a distance, which can be performed manually or automatically. (NP-026-04)

removable RADIOACTIVE contamination OF surface (снимаемое радиоактивное загрязнение поверхности) – same as REMOVABLE SURFACE CONTAMINATION (СНИМАЕМОЕ ЗАГРЯЗНЕНИЕ ПОВЕРХНОСТИ).

removable surface contamination (снимаемое загрязнение поверхности) – see CONTAMINATION (ЗАГРЯЗНЕНИЕ).

renovation (Реконструкция)

Renovation of capital construction objects (Реконструкция объектов капитального строительства) (except for linear objects) – change of parameters of a capital construction object, its parts (height, number of floors, surface areas, volumes), including addition of superstructures, reconstruction, expansion of a capital construction object, replacement and (or) restoration of load-bearing structures, except for replacement of individual components of such structures for identical ones or for the ones with enhanced parameters. (“Town Building Code of the Russian Federation” No. 190-FZ)

Renovation of linear facilities (Реконструкция линейных объектов) – change of parameters of linear facilities or their parts (sections) leading to change of class, category and (or) initially assigned functional parameters (power, lifting ability, etc.), and requiring change of the boundaries of land allotments or protected zones of such facilities. (“Town Building Code of the Russian Federation” No. 190-FZ)

REPAIR (РЕМОНТ) – set of actions aimed at recovering operability or functions of object (system or component) and/or restoration of its residual life. (OPB-12, PRB AS-99)

Major repair of linear facilities (ремонт линейных объектов капитальный) – change of parameters of linear facilities or their parts (sections) not leading to change of class, category and (or) initially assigned functional parameters (power, lifting ability, etc.), and requiring change of the boundaries of land allotments and (or) protected zones of such facilities. (“Town Building Code of the Russian Federation” No. 190-FZ)

Major repair of capital construction objects (ремонт объектов капитального строительства капитальный) (except for linear objects) – replacement and (or) recovery of structural elements of capital construction object or parts of such structures, except for load bearing structural components, replacement and (or) recovery of engineering and technical support systems and engineering and technical support networks of capital construction objects or their components, replacement of individual components of load-bearing structures, except for replacement of individual components of such structures for identical ones or for the ones with enhanced parameters, and (or) restoration of such components. (“Town Building Code of the Russian Federation” No. 190-FZ)

reporting data (Отчетные данные) – information about products and nuclear materials, directly (without recalculations) used for generating reporting documents for the MBA or reporting zone of an organization. (NP-030-12)

required evacuation time (ВРЕМЯ ЭВАКУАЦИИ НЕОБХОДИМОЕ) – time since the moment of occurrence of fire, within which people must be evacuated into safe area without harm to their life and health caused by hazardous factors of the fire. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

reserve of the federal management body for RADIOACTIVE waste management, special (резерв органа государственного управления в области обращения с радиоактивными отходами Специальный) – see SPECIAL RESERVE OF THE FEDERAL MANAGEMENT BODY FOR RADIOACTIVE WASTE MANAGEMENT (Специальный резерв органа государственного управления в области обращения с радиоактивными отходами).

reservoir (Резервуар) – container, cistern car or tank wagon or vessel with the volume of at least 450 liters for liquids, powders, granules or mixtures and at least 1000 liters for gases. A reservoir must be transportable by land or water, able to be drained and filled without removal of structural components, equipped with stabilizing elements and transportation fixtures, and able to be lifted in the filled state. (NP-053-04)

residual life (ресурс Остаточный) – total operation time of a valve from the moment of inspection of its technical condition to transition into limiting state. (NP-068-05, NP-017-2000)

resistance of system (component) to external impacts (Стойкость системы (элемента) при внешних воздействиях) – ability of system (component) to maintain its functions and parameters over the prescribed period of time in normal operation and under natural or technogenic external impacts (seismic resistance, vibration resistance, corrosion resistance, etc.) within the limits specified by design specifications and technical conditions for system operation. (NP-064-05)

RESPONSE (REACTION) SPECTRUM (СПЕКТР ответа (реакции)) – combination of absolute values of maximum response accelerations of linear oscillator under the impact represented by accelerogram taking into account eigen frequency and decay parameter of the linear oscillator. (NP-031-01)

Floor response spectrum (Спектр ответа поэтажный) – set of absolute values of maximum response accelerations of linear oscillator for a given floor impact accelerogram. (NP-031-01)

Generalized response (reaction) spectrum (Спектр ответа (реакции) обобщенный) – spectrum, obtained by means of processing response spectra for a set of real (analogue) accelerograms corresponding to given probability of exceedence. (NP-031-01)

Narrow band spectra (Спектры узкополосные) – response spectra with the width of less than Rs=0.5 comprising 1/3 of all the population of data available worldwide. (RB-006-98)

Normal spectra (Спектры нормальные) – response spectra having logarithmic width close to normal: Rs =0.5-0.8 comprising 1/3 of all the population of data available worldwide. (Refined definition from RB-006-98)

Wide band spectra (Спектры широкополосные ) – response spectra with the width of more than Rs=0.8 comprising 1/3 of all the population of data available worldwide. (RB-006-98)

restraint (Упор) – limiter of stroke of executive mechanism movable parts. (NP-086-12)

REUSED MATERIALS (МАТЕРИАЛЫ повторного использования) – materials obtained during decommissioning of a nuclear power unit, the amount (or activity) of radionuclides contained in which does not exceed the limits specified by federal nuclear rules and regulations, and which are limitedly or unlimitedly usable for industrial or commercial applications. (NP-012-99)

REVIEW, METROLOGICAL (экспертиза Метрологическая) – see METROLOGICAL REVIEW (МЕТРОЛОГИЧЕСКАЯ ЭКСПЕРТИЗА).

REVISION OF QUALITY ASSURANCE PROGRAM (ПЕРЕСМОТР ПРОГРАММЫ ОБЕСПЕЧЕНИЯ КАЧЕСТВА) – review of quality assurance program for confirmation of its compliance with regulatory requirements and identification of possibilities for its improvement. (RB-003-98)

rheological propertY of materials (РЕОЛОГИЧЕСКОЕ СВОЙСТВО МАТЕРИАЛОВ) – manifestation of irreversible residual deformations and plasticity or creep under effects or loads and (or) impacts. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

risk (Риск) – combination of probability of damage and severity of the damage in the form of negative consequences (destruction, damage of a building, structure, system, component, violations in operation of nuclear facilities, accidents at nuclear facilities and associated hazards of damage inflicted to health and life of people and/or damage to environment (revised definition of NP-064-05)

Comment

A corresponding term in the IAEA Glossary is “Risk” (Риск).

Allowable fire risk (Пожарный риск допустимый) – fire risk, level of which is accepted and justified taking into account social and economic conditions. ((Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

Fire risk (Пожарный риск) – measure of possibility of realization of fire hazard of protection object and its consequences for people and property. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

Individual fire risk (Пожарный риск индивидуальный) – fire risk that can cause human casualties as a result of influence of harmful factors of fire. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

Radiation risk (радиационный риск) – probability of occurrence of any harmful effect of radiation for the exposed individual or his (her) children. (NRB-99/2009, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Radiation risks” (Радиационные риски).

Social risk of fire (Пожарный риск социальный) – level of hazard, causing death of a group of people caused by hazardous factors of fire. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

ROOM (ПОМЕЩЕНИЕ) – a part of volume of building or structure having a specific purpose and surrounded by structural elements. (Federal Law No. 384-FZ “Technical Specifications on safety of buildings and structures”)

Room with continuous presence of people (Помещение с постоянным пребыванием людей) – room, in which continued presence of people for more than two hours is anticipated. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

room microclimatE (МИКРОКЛИМАТ ПОМЕЩЕНИЯ) – climatic conditions in the room or compartments determined by combination of temperature, humidity and air velocity effecting human organism. (Federal Law No. 384-FZ “Technical Specifications on safety of buildings and structures”)

ROUTE OF EVACUATION (ПУТЬ ЭВАКУАЦИИ) – see EVACUATION ROUTE (ЭВАКУАЦИОННЫЙ ПУТЬ).

SAEFTY DEFICIT (ДЕФИЦИТ безопасности) – lack of a certain safety function in comparison with the scope defined by the current rules and regulations on the use of nuclear energy. (NP-017-2000)

safe (accountable) distance (Расстояние безопасное (учитываемое)) – distance from the source of hazard to a nuclear facility, beyond which possible external impact of natural or technogenic nature upon it can be neglected. (NP-064-05)

SAFE AREA (БЕЗОПАСНАЯ ЗОНА) – area in which people are protected from hazardous factors of fire, in which hazardous factors of fire are absent or are within the allowable limits. (Federal Law No.123-FZ “Technical Specifications on fire safety requirements”)

SAFE CHARACTERISTICS OF BUILDING OR STRUCTURE (ХАРАКТЕРИСТИКИ БЕЗОПАСНОСТИ ЗДАНИЯ ИЛИ СООРУЖЕНИЯ) – qualitative and quantitative parameters and properties of structural elements, base, materials, engineering and technical support network and systems, by means of which compliance of the building or structure with safety requirements is achieved. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

SAFE FAILURE (БЕЗОПАСНЫЙ ОТКАЗ) – see FAILURES (ОТКАЗЫ).

safe geometry (геометрия Безопасная) – geometric parameters of equipment for NF storage and transportation precluding occurrence of self-sustained chain reaction in normal operation, abnormal operation and design basis accidents. (NP-061-05)

SAFE OPERATION CONDITIONS (УСЛОВИЯ БЕЗОПАСНОЙ ЭКСПЛУАТАЦИИ) – minimum conditions identified in the design in terms of number, characteristics, operability status, maintenance and testing requirements for systems (components) important for safety, under which compliance with safe operation limits and/or safety criteria is ensure. (OPB-12, PRB AS-99)

SAFE SHUTDOWN EARTHQUAKE (МАКСИМАЛЬНОЕ РАСЧЕТНОЕ ЗЕМЛЕТРЯСЕНИЕ) – see EARTHQUAKE (ЗЕМЛЕТРЯСЕНИЕ).

SAFE STORAGE OF NUCLEAR POWER UNIT (СОХРАНЕНИЕ ПОД НАБЛЮДЕНИЕМ БЛОКА АС) – stage of power unit decommissioning, completion of which implies preservation of structures, components and buildings on the plant site for extended period, until content of radioactive materials in them decreases to specified values at the expense of natural decay. (NP-012-99)

SAFETY

Fire safety of the protected object (Пожарная безопасность объекта защиты) – state of the protected object characterized by prevention of possibility of fire development and of impact of hazardous factors of fire upon people and property. (Federal Law No.123-FZ “Technical Specifications on fire safety requirements», “Code of practice. Nuclear power stations. Fire safety requirements”. SP 13.13130.2009)

Mechanical safety (Механическая безопасность) – state of structural elements and bases of building or structure, in which there is no unallowable risk associated with damage to life and health of people, property of individuals or legal entities, state or municipal property, environment, health and life of animals and plants due to collapse or loss of stability of building, structure, or part thereof. (Federal Law No. 384-FZ “Technical Specifications on safety of buildings and structures”)

Nuclear plant nuclear and radiation safety (безопасность АС, ядерная и радиационная) – ability of nuclear plant to limit radiation impact on personnel, public and environment during normal operation and during deviations from normal operation including design basis accidents within the established limits, to mitigate the impact in case of beyond design basis accidents, and to decrease probability of accident occurrence. (OPB-12)

Comment

The IAEA Glossary provides definitions of two terms – “Nuclear safety” (Ядерная безопасность) and “Radiation protection” (Радиационная защита). In the Russian regulatory documents, including OPB-12, when safety of a potentially hazardous object, such as nuclear plant, is discussed, it is defined through properties of the object not to create hazard for personnel, public and environment, or to maintain the hazard within the prescribed boundaries. If safety of someone exposed to hazard is meant, it is defined as state of his or her protection. In the IAEA Glossary the term “Nuclear safety” (Ядерная безопасность) is defined as reaching certain operational states, preventing accidents or mitigating their consequences to ensure protection of personnel, environment and public against unallowable radiation hazard, i.e. the activities making the object safe. In this sense, definitions of the IAEA Glossary and OPB-12 can be considered equivalent. Radiation protection (радиационная защита) is defined in the IAEA Glossary as protection of people against ionizing radiation and radioactive substances, i.e. activities aimed at achieving the state of protection, defined by the Russian regulatory documents. The IAEA Glossary specifies that extension of the concept of “radiation protection” to environment is questionable.

Radiation safety of public (радиационная безопасность населения) – state of protection of present and future generations of people against harmful effects of ionizing radiation on their health. (NRB-99/2009, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Radiation protection” (радиационная защита) or “Radiation protection or Radiological protection” (Радиационная защита или радиологическая защита).

Radioactive waste disposal safety (безопасность системы захоронения радиоактивных отходов) – property of RW disposal system to maintain radiation impact on public over the entire period of persistence of potential hazard from RW within the limits prescribed by radiation safety codes and standards. (NP-058-04)

Radioactive waste handling safety (безопасность при обращении с радиоактивными отходами) – state of protection of employees (personnel), public and environment against unallowable radiation impact during RW management and handling activities. (NP-058-04)

SAFETY CRITERIA (КРИТЕРИИ БЕЗОПАСНОСТИ) – values of parameters and (or) characteristics of the nuclear plant, based on which its safety is demonstrated. The criteria are defined by regulatory documents or plant design (in the latter case, the criteria must be consistent with the regulatory requirements). (OPB-12)

SAFETY CULTURE (КУЛЬТУРА БЕЗОПАСНОСТИ) – characteristics of activities in the organizations, along with psychological and qualificational preparedness of all individuals involved in safety related activities, in the presence of which the task of ensuring plant safety as having the highest priority receives attention commensurate with its importance. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Safety culture” (Культура безопасности).

SAFETY FUNCTION (ФУНКЦИЯ БЕЗОПАСНОСТИ) – specific goal and actions enabling its achievement, aimed at preventing and limiting consequences of accidents, which are failed to be prevented by normal operation systems. (OPB-12)

Comment

A partly corresponding term in the IAEA Glossary is “Safety function” (Функция безопасности). However, the IAEA Glossary interprets safety function as a specific goal to be achieved to ensure safety during accidents, but also in other cases, in particular, in normal operation.

SAFETY ORIENTED MANAGEMENT (УПРАВЛЕНИЕ В ЦЕЛЯХ БЕЗОПАСНОСТИ) – administrative system implemented by the operating utility integrating all the elements of administrative management in such a way that the processes and actions that can affect nuclear plant safety are arranged and performed in coordination with other requirements, including requirements to supervisors, to health protection, to personnel actions, economics, environmental protection, nuclear material accounting and control, physical security and quality in order to ensure that other requirements do not have detrimental effects on plant safety. (OPB-12)

Comment

This term is related to the IAEA Glossary term “Integrated management system (for facilities and activities)” (Комплексная система управления (для установок и деятельности)).

safety performance index, PROBABILISTIC (показатель безопасности Вероятностный) – see PROBABILISTIC SAFETY PERFORMANCE INDEX (ВЕРОЯТНОСТНЫЙ ПОКАЗАТЕЛЬ БЕЗОПАСНОСТИ).

SAFETY REQUIREMENTS APPLICABLE DURING THE USE OF NUCLEAR ENERGY (ТРЕБОВАНИЯ К ОБЕСПЕЧЕНИЮ БЕЗОПАСНОСТИ ПРИ ИСПОЛЬЗОВАНИИ АТОМНОЙ ЭНЕРГИИ) – totality of the requirements established by the legislation of the Russian Federation, federal nuclear rules and regulations, conditions of the licenses (permits)* issued by the Russian regulatory authority and its territorial offices for the right to perform specific types of activities, decrees of the regulatory authority and other regulatory and legal documents, compliance with which is to be supervised by Russian regulatory authority and its territorial offices. (RD-03-43-98)

SAFETY SYSTEM (СИСТЕМА БЕЗОПАСНОСТИ) – see SAFETY SYSTEMS (COMPONENTS) (СИСТЕМЫ (ЭЛЕМЕНТЫ) БЕЗОПАСНОСТИ).

SAFETY SYSTEMS (COMPONENTS) (СИСТЕМЫ (ЭЛЕМЕНТЫ) БЕЗОПАСНОСТИ) – systems (components) designed for performing safety functions during design basis accidents. (OPB-12)

Note: Safety systems (components) are subdivided by the nature of functions into protection, localization, support and control systems.

Comment

A corresponding term in the IAEA Glossary is “Safety system” (Система безопасности). A difference is that according to OPB-12, safety systems are designed for performing safety functions, whereas the IAEA Glossary defines that safety systems perform the following specific tasks: safe reactor shutdown, residual heat removal, and limitation of consequences of anticipated operational events and design basis accidents. Ambiguity of the latter definition is obvious, since the same tasks are performed by normal operation systems. There is another difference. According to definition of safety systems provided in the OPB-12, they include four types of systems depending on the nature of performed safety functions: protection, localization, support and control safety systems. IAEA Glossary defines only three types of systems. Protection and localization systems in the terminology of OPB-12 are combined in the IAEA Glossary into a single group of safety actuation systems. Control safety systems are titled protection systems, and include only a part of control systems related to the nuclear reactor. Other parts of the control systems are not distinguished as a separate group, but included into safety actuation systems. Definitions of support safety systems in the IAEA Glossary and in the OPB-12 are identical.

Protection safety systems (components) (Защитные системы (элементы) безопасности) – systems (components) designed to prevent or limit damage of nuclear fuel, fuel cladding, equipment and pipelines containing radioactive substances. (OPB-12)

Comment

This term is related to the IAEA Glossary term “Safety actuation system” (Исполнительная система безопасности) that combines localization and protection systems in the Russian terminology.

Control safety systems (Управляющие системы (элементы) безопасности) – systems (components) designed for initiation of safety systems, and for controlling them during performance of the intended functions. (OPB-12, NP-026-04)

Comment

This term is related to the IAEA Glossary term “Protection system” (Система защиты), as far as reactor control systems are concerned. However, the Russian definition of control safety systems includes controls of all safety systems, rather than those of reactor only.

Localization safety systems (components) (Локализующие системы (элементы) безопасности) – systems (components) intended to prevent or limit spreading of radioactive substances and ionizing radiation generated during accidents beyond the design boundaries and their release into environment. (NP-010-11)

Comment

This term is related to the IAEA Glossary term “Safety actuation system” (Исполнительная система безопасности) that combines localization and protection systems in the Russian terminology.

Support safety systems (components) (Обеспечивающие системы (элементы) безопасности) – systems (components) intended to provide other safety systems with energy, process fluid or to establish conditions required for their proper operation. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Safety system support features” (Средства поддержки систем безопасности).

SANITARY AIRLOCK (Саншлюз) – a room between the zones of a radiation facility intended for preliminary decontamination and exchange of additional means of individual protection. (PRB AS-99)

Temporary airlock (Саншлюз временный) – a fenced site intended for replacement of additional means of individual protection (PRB AS-99)

SANITARY CHECKPOINT (Санпропускник) – a set of rooms and compartments intended for changing clothes and footwear, personnel decontamination, monitoring of radioactive contamination of skin, means of individual protection and clothing. (PRB AS-99)

sanitary protection zone (санитарно-защитная ЗОНА) – see ZONE (ZONES) (ЗОНА (ЗОНЫ)).

scaling (Чешуйчатость) – lateral or rounded (oblong rounded in case of automated submerged arc welding) depressions on the bead surface formed due to non-homogeneity of solidification of weld pool (evaluated by maximum depth).(PNAE G-7-010-89)

scenario (Сценарий) – logical sequence of interrelated states of object or complex technical system possible under external impacts. (RB G-05-039-96)

scenario of states of object or complex technical system (Сценарий состояний объекта или сложной технической системы) – logical sequence of interrelated states of object or complex technical system possible under external impacts of natural and/or technogenic origin included into design bases of nuclear facility. (NP-064-05)

SEALED RADIONUCLIDE SOURCE (ЗАКРЫТЫЙ РАДИОНУКЛИДНЫЙ ИСТОЧНИК) – see SOURCE (ИСТОЧНИК).

SEALING ELEMENTS (of RW storage facility) (ЭЛЕМЕНТЫ запечатывающие (хранилище РАО)) – elements of RW storage facility, with which the access routes and utility lines used during operation of the facility are filled during decommissioning activities. (RB-011-2000)

SEALING SYSTEM (OF PACKAGING) (Система герметизации (упаковки)) – part of the packaging system designed to confine radioactive contents during transportation. (NP-053-04)

seasonal flood (Половодье) – a phase of river water regime with long term significant increase of water content in the river causing gradual increase of water level, repeated annually in the same season. (NP-064-05)

secondary fragments (Вторичные осколки) – see FRAGMENTS (ОСКОЛКИ).

seiChes (Сейши) – oscillations of water level in a closed or semi-closed water body under the influence of disturbance forces of atmospheric, oceanic or seismic origin. (NP-064-05)

seismic deformations, residual (сейсмодеформации, остаточные) – deformations of earth crust in the form of cracks, stepwise settlements, fault-bend folds, soil eruptions, sediments, earth waves resulting from passage of seismic waves. (NP-064-05)

SEISMIC EXPLOSIVE WAVES (СЕЙСМОВЗРЫВНЫЕ ВОЛНЫ) – see WAVE (WAVES) (ВОЛНА (ВОЛНЫ)).

SEISMIC HAZARD (СЕЙСМИЧЕСКАЯ ОПАСНОСТЬ) – maximum seismic impact of the specified recurrence frequency at the site of a nuclear or radiation hazardous facility. (RB-019-01)

SEISMIC INSULATION OF A STRUCTURE (BUILDING) (Сейсмоизоляция сооружения (здания)) – a set of engineered structures, usually installed in the foundation of the structure or building to decrease oscillations of the building caused by seismically induced oscillations of ground surface, as well as systems and components designed to control (shift) the eigen frequencies of oscillation of the structure or building into desirable range of values. (NP-064-05)

SEISMIC INTENSITY (БАЛЛЬНОСТЬ) – intensity of seismic impact measured on the MSK-64 scale. (RB-019-01)

SEISMIC INTENsITY (Интенсивность сейсмическая) – integral macroseismic measure of a seismic impact determined based on the statistics of damage of reference buildings, reaction of objects, people, parameters of ground movements, parameters of the focus of earthquake and distance from the observation point, measurements on the daylight surface. (RB-006-98)

SEISMIC MICROZONING (СЕЙСМИЧЕСКОЕ МИКРОРАЙОНИРОВАНИЕ) – a complex of specialized activities intended to predict the influence of the specifics of subsurface structure, composition, properties and state of ground formations, watercut properties, and relief upon the parameters of ground surface oscillations on the plant site. (NP-031-01)

SEISMIC OSCILLATION OF GROUND FOR DESIGN BASES (КОЛЕБАНИЕ СЕЙСМИЧЕСКОЕ ГРУНТА ДЛЯ ПРОЕКТНЫХ ОСНОВ) – seismograms and reaction spectra (accelerograms , velocigrams , displograms X), corresponding to the impacts typical of the given site in case of SSE or DBE for 50%- and 84% probability levels. (RB-006-98)

SEISMIC RESISTANCE (Сейсмопрочность) – ability of a component to maintain strength, integrity and leaktightness during and after earthquakes. (NP-068-05)

SEISMIC RESISTANCE OF NUCLEAR PLANT COMPONENTS (СЕЙСМОСТОЙКОСТЬ ЭЛЕМЕНТОВ АС) – ability of plant components to perform intended functions during and after earthquakes according to the design. (NP-031-01)

SEISMIC STUDIES FOR A NUCLEAR PLANT (СЕЙСМОЛОГИЧЕСКИЕ ИССЛЕДОВАНИЯ ДЛЯ АС) – a set of measures aimed at refining of general seismic zoning of the area and seismic microzoning of alternative sites in order to refine the knowledge of seismicity of the area based on the general seismic zoning maps and to determine DBE and SSE parameters. (NP-031-01)

SEISMICITY (СЕЙСМИЧНОСТЬ) – totality of the earthquake origins in space and time. (RB-019-01)

Dispersed (background) seismicity (Сейсмичность рассеянная (фоновая)) – background earthquakes are low magnitude earthquake (usually with the МЈ 4), which are hard to associate with known seismicity generating structures. It is conservatively assumed that background earthquakes can occur in any location on the territory in question. Recurrence frequency of earthquakes postulated for the entire territory is, on the average, five times lower than the real value. Thus, assessment of seismic hazard associated with background earthquakes consists in identifying the existence of epicenters of micro-earthquakes in the immediate vicinity of the site. (Refined definition from RB-006-98)

Nuclear plant seismicity (Сейсмичность площадки АС) – intensity of possible seismic impacts of DBE and SSE at the plant site measured on the MSK-64 scale. (NP-031-01)

seismogram synthesis (Синтезирование сейсмограмм) – mathematical modeling of seismograms (accelerograms, velocigrams, displograms) consistent with the expected values of major parameters of oscillations (level, width of pulse) and spectrum (predominant frequency and its logarithmic width). (RB-006-98)

seismotectonic fissure displacements (Сейсмотектонические разрывные смещения) – rupture displacements of parts of earth crust along seismogenic faults and breaks reaching air surface in the areas with high seismicity (above 8 points), including pulsations, shifts, overthrusts, crushes, uplifts and other fissure displacements. (NP-064-05)

SELF ASSESSMENT (САМООЦЕНКА) – analysis, performed by administration of a nuclear power plant or operating utility in order to assess compliance with the requirements associated with plant safety, efficiency and adequacy of management to safety objectives. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Self-assessment” (Самооценка). It should be, however, noted that in the Russian regulatory bases the concept of “self assessment” is formulated only in relation to nuclear power plant or operating utility management.

self loosening (Самоотвинчивание) – self-induced loosening of fixture elements during operation of actuators. (NP-086-12)

self regulating organizations in the are of engineering surveys, civil engineering, construction, renovation and capital maintenance of capital construction objects (организации в области инженерных изысканий, архитектурно-строительного проектирования, строительства, реконструкции, капитального ремонта объектов капитального строительства СаморегулируЕмые) – non-profit organizations registered in the state registry of self-regulating organizations that are based on membership of individual entrepreneurs and (or) legal entities performing engineering surveys and providing services associated with design, civil engineering, construction, renovation and capital maintenance of capital construction objects. (“Town Building Code of the Russian Federation” No. 190-FZ)

self sustained nuclear fission chain reaction (Самоподдерживающаяся цепная ядерная реакция деления) – process of fission of radionuclides, in which the number of neutrons generated in the process of nuclear fission over a certain period of time is equal to or greater than the number of neutrons leaving the system through escape or absorption over the same period of time. (Refined definition of NP-053-04)

SERVICE LIFE (Срок службы) – calendar duration of operation from beginning of operation of a valve or resumption of operation after maintenance to transition of the valve to limiting state. (NP-068-05)

set, packaging (комплект Упаковочный) – see packaging set (УПАКОВОЧНЫЙ КОМПЛЕКТ)

SEVERE ACCIDENT PRECURSOR (ПРЕДВЕСТНИК ТЯЖЁЛОЙ АВАРИИ) – deviation from design parameters or characteristics identified during operation or realized during an operational event, which did not result in a severe accident but provided evidence for significant weakness in design of component or unit, operation of the unit, or was a part of emergency sequence that could have caused a severe accident. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Accident precursor” (Событие - предшественник аварии). However, its definition in the IAEA Glossary does not reflect the meaning of the term adopted in other IAEA documents, e.g. IAEA-TECDOC-1417.

SEVERE BEYOND DESIGN BASIS ACCIDENT (ТЯЖЁЛАЯ ЗАПРОЕКТНАЯ АВАРИЯ) – see ACCIDENT (АВАРИЯ).

SEVERE CORE DAMAGE (Тяжелое повреждение активной зоны реактора) – beyond design basis accident with damage of fuel elements in the core. (Refined definition from NP-082-07)

SHIPPING PACKAGE SET (Транспортный упаковочный комплект) – see PACKAGE SET (КОМПЛЕКТ УПАКОВОЧНЫЙ).

Shock wave, air (ударная волна Воздушная) – see AIR SHOCK WAVE (ВОЗДУШНАЯ УДАРНАЯ ВОЛНА).

SHOT METAL (Брызги металла) – a defect in the form of solidified droplets of metal on the surface of welded or surfaced components. (PNAE G-7-010-89)

shrinkage cavity (Усадочная раковина)) – defect in the form of cavity or indentation formed during shrinkage of solidifying molten metal, usually in the locations where welding process was interrupted or ended. (PNAE G-7-010-89)

shutter (Затвор) – a set of mobile (spool, disk, wedge, deflector, plunger, etc.) and immobile parts of isolating or regulating component of the valve, changing the flow cross section. (NP-068-05)

significance (Значимость) – quantitative characteristic of influence of individual parameters of probabilistic model on the results of PSA. (RB-024-11)

significance level (УРОВЕНЬ ОТВЕТСТВЕННОСТи) – a characteristic of building or structure determined based on the scope of economic, social and environmental consequences of its destruction. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

SIMULATOR, FULL SCOPE (ТРЕНАЖЕР ПОЛНОМАСШТАБНЫЙ) - see FULL SCOPE SIMULATOR OF POWER UNIT (ПОЛНОМАСШТАБНЫЙ ТРЕНАЖЕР ЭНЕРГОБЛОКА АС).

SINGLE FAILURE PRINCIPLE (ПРИНЦИП ЕДИНИЧНОГО ОТКАЗА) – principle, according to which a system must perform intended functions in case of any initiating event requiring its actuation assuming failure of any single active component or passive component with moving parts in the system independent of the initiating event. (OPB-12)

Comment

This term corresponds to IAEA Glossary term “Single failure criterion” (Критерий единичного отказа). Between the definitions of these terms in the Russian regulatory system, there is a notable difference, namely, the Russian definition refers to a single failure, independent of the initiating event, of any active component or passive component with movable parts, operation of which is required in case of the initiating event. IAEA standard requires taking into account any single failure, including those of passive components unless extremely small probability of its failure was demonstrated with high degree of credibility.

SITE OF THE NUCLEAR POWER UNIT UNDER DECOMMISSIONING (ПЛОЩАДКА выводимого из эксплуатации блока АС) – a part of the plant site with buildings and structures, boundaries of which are defined by the design of a power unit under decommissioning. Buildings, structures and systems shared with other units are not considered a part of the site of power unit under decommissioning. (NP-012-99)

SITING (ВЫБОР ПЛОЩАДКИ) – process of selection of an appropriate site for a nuclear facility, including assessment and definitions of criteria for design bases. (RB-022-01)

Comment

This term is fully equivalent to the same term in the IAEA Glossary.

slug inclusion (Шлаковое включение) – see INCLUSION (ВКЛЮЧЕНИЕ).

smoke protection (Система противодымной защиты) – complex of organizational measures, configuration solutions, engineered systems and hardware designed to prevent or limit the hazard of smoke accumulation in buildings and structures during fires, as well as impact of hazardous factors of fire upon people and property. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”, “Code of practice. Nuclear power stations. Fire safety requirements”. SP 13.13130.2009)

software (Программное средство) – a program (code), complex of programs, library of constant, independent software module or combination thereof. (RB-061-11)

SOFTWARE APPLICANT (Заявитель ПС) – a legal entity or an individual submitting software for review. (RB-061-11)

software verification method (Методология верификации ПС) – combination of tools and methods used for software verification. (RB-061-11)

soil liquefaction (Разжижение грунта) – process resulting in loss of rigidity and mechanical strength of soils saturated with water under dynamic loads (earthquakes, explosions, vibration). (NP-064-05)

solidification of radioactive wastes (Отверждение радиоактивных отходов) – transfer of LRW into solid state in order to minimize the possibility of migration of radionuclides into environment. (NP-002-04)

solifluxion (Солифлюкция) – slow movement of moist finely dispersed or silt soils (at the rate of 3-8 cm per year) down the slopes resulting from repeated heaving during freezing and settling during thawing, along with gravity action. Each freeze-thaw cycle results in translocation of the upper layer of soil sediments. (NP-064-05)

SOURCE (Источник)

Emergency explosion source (источник аварийных взрывов) – a facility containing explosive substances or mixtures (explosives, gas-air mixtures, fuel-air mixtures), which is therefore classified as potentially hazardous. (Refined definition of RB G-05-039-96)

Ignition source (источник зажигания) – a source of energy impact initiating combustion process. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

Ionizing radiation source (источник ионизирующего излучения) – radioactive substance or product emitting or capable of emitting ionizing radiation, which is regulated by sanitary codes and standards. (NRB-99/2009, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Source” (Источник).

Natural source of radiation (природный источник излучения) – a source of ionizing radiation of natural origin, to which the requirements of the present sanitary codes and standards apply. (NRB-99/2009)

Comment

A corresponding term in the IAEA Glossary is “Natural source” (Природный (естественный) источник).

Radiation sources (Радиационные источники) – systems, instruments, components or products unrelated to nuclear facilities, containing radioactive substances or generating ionizing radiation. (Federal Law No. 170-FZ “On the use of nuclear energy”)

Comment

A corresponding term in the IAEA Glossary is “Radioactive source” (Радиоактивный источник).

Radioactive source (Радиоактивный источник) – plant system or component, containing nuclear fuel or radioactive substances. (RB-024-11)

Comment

A corresponding term in the IAEA Glossary is “Radiation source” (Радиационный источник). However, according to the definition of IAEA Glossary, such a source cannot contain materials of fuel cycle of research or power reactors.

Radioactivity source (источник радиоактивности) – plant system or component containing nuclear fuel or radioactive substances. (RB-032-04)

Sealed radionuclide source (Закрытый радионуклидный источник) – source of ionizing radiation, design of which precludes release of the radionuclides contained in it into environment assuming the operating conditions and ageing it is designed for. (NP-030-12, NP-067-11, NRB-99/2009)

Comment

A corresponding term in the IAEA Glossary is “Sealed source” (Закрытый источник).

Spent sealed source of ionizing radiation (источник ионизирующего излучения закрытый отработавший) – a source of ionizing radiation which is no longer usable and design of which precludes release of the radionuclides contained in it into environment. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

Technogenic radioactivity source (техногенный источник излучения) – source of ionizing radiation, which is specially created for intended use or is a by-product of some intentional activities. (NRB-99/2009)

Unsealed radionuclide source (Открытый радионуклидный источник) – source of radiation, during use of which the radionuclides contained can be released into environment. (NP-067-11, NRB-99/2009)

Comment

A corresponding term in the IAEA Glossary is “Unsealed source” (Открытый источник).

special conditions (Специальные условия) – provisions and conditions, developed and properly authorized by relevant ministries and departments, which are to be complied with during transportation of radioactive material cargo if it is not fully compliant with the rules adopted for each type of transportation. Compliance with these conditions must ensure at least the same level of safety, as compliance with the requirements of the Rules. (NP-053-04)

special reserve of the federal management body in the area of radioactive waste management (Специальный резерв органа государственного управления в области обращения с радиоактивными отходами) – fund for financing the expenses for disposal of radioactive wastes of organization performing the functions of the federal management body in the area of radioactive waste management. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

special type material, radioactive (материал особого вида Радиоактивный) – see SPECIAL TYPE RADIOACTIVE MATERIAL (Радиоактивный материал особого вида (РМОВ)).

SPECIALIZED RADIOACTIVE WASTE MANAGEMENT ORGANIZATION (СПЕЦИАЛИЗИРОВАННАЯ ОРГАНИЗАЦИЯ ПО ОБРАЩЕНИЮ С РАДИОАКТИВНЫМИ ОТХОДАМИ) – legal entity performing work and rendering services associated with collection, sorting, reprocessing, conditioning, transportation, and storage of radioactive wastes, operation, decommissioning or closure of radioactive waste storage facilities. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

SPECIFIC ACTIVITY OF ISOTOPE (Удельная активность изотопа) – see ACTIVITY (АКТИВНОСТЬ).

specific data (Специфические данные) – see DATA (ДАННЫЕ).

specific soils (грунты Специфические) – soils, the properties and characteristics of which change in time on the timescale comparable with the lifetime of facility. These include permafrost soils, subsiding, dilating, weak, salty, alluvial or artificial soils. (NP-064-05)

SPECTRUM OF DYNAMIC RESPONSE FACTORS (СПЕКТР коэффициентов динамичности) – non-dimensional spectrum obtained by division of the values of response spectrum by maximum acceleration of the ground. (NP-031-01)

spectrum width (Ширина спектра) – difference of logarithms of the left and right slopes of spectrum at the level of 0.5 of maximum. Logarithmic width of spectrum weakly depends on magnitude of earthquake and on average is close to Rs = 0.65. This property decreases the uncertainty of extrapolation of weak impacts into the area of stronger impacts. (RB-006-98)

SPENT FUEL ASSEMBLIES OF NUCLEAR REACTOR (ТЕПЛОВЫДЕЛЯЮЩИЕ СБОРКИ ЯДЕРНОГО РЕАКТОРА ОБЛУЧЕННЫЕ) – fuel assemblies irradiated in the nuclear reactor and removed from it, containing spent nuclear fuel. (Federal Law No. 170-FZ “On the use of nuclear energy”)

SPENT FUEL ASSEMBLY OF A NUCLEAR REACTOR (СБОРКА ЯДЕРНОГО РЕАКТОРА ОБЛУЧЕННАЯ ТЕПЛОВЫДЕЛЯЮЩАЯ) – see SPENT FUEL ASSEMBLIES OF NUCLEAR REACTOR (ТЕПЛОВЫДЕЛЯЮЩИЕ СБОРКИ ЯДЕРНОГО РЕАКТОРА ОБЛУЧЕННЫЕ)

spent fuel pool (Бассейн выдержки отработавшего ядерного топлива) – structure, forming a part of nuclear facility or nuclear material storage facility, designed for temporary storage of spent nuclear fuel under water or other liquid environment. (NP-061-05)

Comment

This term is mentioned in the definition of the IAEA Glossary term “Wet storage” (Мокрое хранение).

SPENT NUCLEAR FUEL (Отработавшее ядерное топливо) – nuclear fuel, irradiated in the reactor core and ultimately removed from it. (NP-061-05, NP-067-11)

Comment

A corresponding term in the IAEA Glossary is “Spent fuel” (Отработавшее топливо).

spent nuclear fuel storage facility, dry (хранилище отработавшего ядерного топлива Сухое) – see DRY STORAGE OF SPENT NUCLEAR FUEL (Сухое хранилище отработавшего ядерного топлива).

stability of nuclear facility under external impacts (Устойчивость объекта использования атомной энергии при внешних воздействиях) – property of the facility, characterized by resistance of buildings, structures, systems and components important for its safety, of its protection barriers, and by safety of the facility for public and environment under any kind of external impacts. (NP-064-05)

stability of protection object during fire (УСТОЙЧИВОСТЬ ОБЪЕКТА ЗАЩИТЫ ПРИ ПОЖАРЕ) – ability of object to maintain structural integrity and (or) functions under influence of hazardous factors of fire and secondary manifestations of hazardous factors of fire. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

stack of packages or fuel assemblies (Штабель упаковок или тепловыделяющих сборок) – set of packages or fuel assemblies allowable for storage conditionally to compliance with the established limitations on mutual location of packages or fuel assemblies. (NP-061-05)

stage of decommissioning of nuclear power unit (ЭТАП вывода из эксплуатации блока АС) – a set of organizational and technical measures and activities performed within a specific period of time, aimed at achieving a state of unit decommissioning prescribed by decommissioning program and design for the end of that period. (NP-012-99)

STANDARD SPECIMEN (СТАНДАРТНЫЙ ОБРАЗЕЦ) – specimen of substance (material) with one or several values characterizing composition or properties of the substance (material) established based on test results. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

standard specimen type (Тип стандартных образцов) – a group of standard specimens having the same purpose, produced of the same substance (material) per the same technical documentation. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

STATE OF FULL SCOPE SIMULATOR, CURRENT (СОСТОЯНИЕ ПМТ ТЕКУЩЕЕ) – see CURRENT STATE OF FULL SCOPE SIMULATOR (ТЕКУЩЕЕ СОСТОЯНИЕ ПМТ).

STATE REFERENCE STANDARD OF A UNIT (эталон единицы величины Государственный) – federally owned reference standards of a unit. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

Primary state reference standard of a unit (Эталон единицы величины государственный первичный) – state reference standard of a unit providing reproducibility, storage and transfer of unit value with the highest accuracy in the Russian Federation, properly recognized in this quality and used as a primary reference standard on the territory of the Russian Federation. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

STOCHASTIC EFFECTS OF RADIATION (стохастические Эффекты облучения) – see RADIATION EXPOSURE EFFECTS (ЭФФЕКТЫ ОБЛУЧЕНИЯ)

stoichiometric mixture (Стехиометрическая смесь) – air-gas mixture (fuel-air mixture), in which per every mole of combustible substance there is a required number of moles of oxygen for oxidation, i.e., chemical reaction proceeds completely to the end. (RB G-05-039-96)

STORAGE SLOT (ГНЕЗДО ХРАНЕНИЯ) – a leaktight element designed for housing one or several leaktight containers. (NP-035-02)

stroke (Ход рабочий) – amplitude of movement of reactivity control rod between the limiting operating positions. (NP-086-12)

structural element (СТРОИТЕЛЬНАЯ КОНСТРУКЦИЯ) – part of building or structure with certain load bearing, enveloping and (or) decorative functions. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

STRUCTURAL FIRE HAZARD CLASS OF BUILDINGS, STRUCTURES AND FIRE COMPARTMENTS (КЛАСС КОНСТРУКТИВНОЙ ПОЖАРНОЙ ОПАСНОСТИ ЗДАНИЙ, СООРУЖЕНИЙ И ПОЖАРНЫХ ОТСЕКОВ) – classifier of buildings, structures or fire compartments, determined based on the level of involvement of structural elements in development of fire and formation of hazardous factors of the fire. Federal Law No.123-FZ “Technical Specifications on fire safety requirements”)

substances (substance) (вещества (ВЕЩЕСТВО))

Explosive substances (вещества взрывчатые) – chemical compounds or mixtures capable of fast exothermal chemical reactions under external stimulus (mechanical impact, heat, etc.). (RB G-05-039-96)

Military grade radioactive substances (Радиоактивные вещества оборонного назначения) – radioactive substances used or intended for use in weapons or military equipment and spare parts, as well as special items containing radionuclides and intended for maintenance and repair of weapons and military equipment. (NP-067-11)

Radioactive substance (Вещество радиоактивное) – a substance emitting ionizing radiation not attributed to nuclear materials. (NP-053-04, NP-034-01, NRB-99/2009, Federal Law No. 170-FZ “On the use of atomic energy”, NP-025-2000, NP-030-12)

Comment

A corresponding term in the IAEA Glossary is “Radioactive material” (Радиоактивный материал). However, it is defied more broadly and does not contain the reservation “not attributed to nuclear materials”.

SUCCESS CRITERION (Критерий успеха) – minimum amount of operable components of systems and (or) operator actions sufficient for successful performance of safety functions. (RB-024-11)

suffusion processes (Суффозионные процессы) – processes of loosening of mellow soils by underground water with suffusion of finely dispersed fractions or entire soil mass. In the course of these processes, suffusion cavities are formed with resulting sinking and settling of ground surface above them. (NP-064-05)

support of nuclear facility operation (Сопровождение эксплуатации ОИАЭ) – monitoring and implementation of compensatory measures to ensure stability and safety of nuclear facility under external impacts. (NP-064-05)

SUPPORTING SAFETY SYSTEMS (COMPONENTS) (ОБЕСПЕЧИВАЮЩИЕ СИСТЕМЫ (ЭЛЕМЕНТЫ) БЕЗОПАСНОСТИ) – see SAFETY SYSTEMS (COMPONENTS) (СИСТЕМЫ (ЭЛЕМЕНТЫ) БЕЗОПАСНОСТИ).

surface water body storage of liquid radioactive wastes (Поверхностный водоем-хранилище жидких радиоактивных отходов) – stationary structure of open type designed for collecting and storing low and medium activity radioactive wastes and located within the limits of the territory of nuclear facility defined by the design. (NP-058-04)

SUSTAINABLE DEVELOPMENT OF TERRITORIES (Устойчивое развитие территорий) – ensuring, during town building activities, safety, and favorable conditions for human life, limitation of negative influence of commercial and other activities upon environment, protection and rational use of natural resources in the interests of the present and future generations. (“Town Building Code of the Russian Federation” No. 190-FZ)

SYSTEM (СИСТЕМА) – set of components designed for performing intended functions. (OPB-12, NP-024-2000)

Comment

A corresponding term in the IAEA Glossary is “System” (Система).

System (Система) – a complex of machines and (or) equipment which are structurally and (or) functionally connected to perform intended functions. (Technical Specifications on safety of machinery and equipment)

SYSTEM IMPORTANT FOR SAFETY (СИСТЕМА, ВАЖНАЯ ДЛЯ БЕЗОПАСНОСТИ) – see SYSTEMS (COMPONENTS) IMPORTANT FOR SAFETY (СИСТЕМЫ (ЭЛЕМЕНТЫ), ВАЖНЫЕ ДЛЯ БЕЗОПАСНОСТИ).

system operability (Работоспособность системы) – ability of a system to perform intended functions during assigned period of time in the prescribed operation limits and conditions. (NP-064-05)

SYSTEM TRAIN (КАНАЛ СИСТЕМЫ) – part of system performing the system function in the designed scope. (OPB-12)

SYSTEM, ACTIVE (СИСТЕМА АКТИВНАЯ) – see ACTIVE SYSTEM (COMPONENT) (АКТИВНАЯ СИСТЕМА (ЭЛЕМЕНТ)).

SYSTEM, INDEPENDENT (СИСТЕМА НЕЗАВИСИМАЯ) – see INDEPENDENT SYSTEMS (COMPONENTS) (НЕЗАВИСИМЫЕ СИСТЕМЫ (ЭЛЕМЕНТЫ)).

SYSTEM, PASSIVE (СИСТЕМА ПАССИВНАЯ) – see PASSIVE SYSTEM (COMPONENT) (ПАССИВНАЯ СИСТЕМА (ЭЛЕМЕНТ)).

systematic component of calculation uncertainty (Методическая компонента погрешности расчета) – uncertainty associated with calculation methodology, approximation used, its numeric realization or preparation of core neutronic constants. (RB-061-11)

SYSTEMS (COMPONENTS) IMPORTANT FOR SAFETY (СИСТЕМЫ (ЭЛЕМЕНТЫ), ВАЖНЫЕ ДЛЯ БЕЗОПАСНОСТИ):

• normal operation systems (components), failure of which violates normal operation of the plant or prevents recovery from violation of normal operation of the plant, if the conditional probability of development of this failure into severe beyond design basis accident is 10^-6 or more;

• plant systems (components), failure of which results in exceedence of established values of allowable effluents or discharges of radioactive substances, or allowable levels of contamination of plant rooms and compartments;

• safety systems (components);

• systems (components) intended for accident management during first 72 hours after occurrence of the initiating event of the accident, (or during other time interval specified in the plant design, but no less than 72 hours);

• radiation monitoring systems (components). (OPB-12)

Comment

This term is related to the IAEA Glossary term “Item Important to Safety” (Устройство, важное для безопасности). It is formulated through another term – “Safety group” (Группа безопасности), which does not exist in the system of Russian regulatory documents. This term is used to designate a set of components necessary for each specific initiating event in order not to exceed the limits established for anticipated operational events and design basis accidents. According to OPB-12, safety systems (components) as well as normal operation systems (components) failure of which violates normal operation of the plant or prevents recovery from violation of normal operation of the plant and can lead to severe beyond design basis accidents are classified as systems (components) important for safety. According to the IAEA Glossary definition, Items important to safety are the items included into safety groups, e.g. safety systems, and the items, failures or malfunctions of which can result in radiation exposure of plant personnel or public. In this part, the definitions of systems (components) important for safety (систем (элементов), важных для безопасности) given in OPB-12 and definition of Item important to safety (устройств, важных для безопасности) given in the IAEA Glossary are equivalent, since the definitive attributes include both safety systems and other items, failure or malfunction of which can result in radiological consequences. There are, however, differences. Normal operation systems (components) are classified as systems (components) important for safety only if the conditional probability of development of this failure into severe beyond design basis accident is 10-6 or more. Besides that, systems (components) intended for accident management during first 72 hours after occurrence of the initiating event of the accident (or during other time interval specified in the plant design, but no less than 72 hours) are also classified as being important for safety, although in the classification of importance for safety these systems (components) are classified as the lowest, 4th class.

tailing dump (Хвостохранилище) – stationary structure of open type designed for collecting and storing low-activity liquid and solid radioactive wastes and located within the territory defined by the nuclear facility design. (NP-058-04)

tAP (Кран) – see VALVES (АРМАТУРА).

technical client (Технический заказчик) – an individual acting on the professional basis or legal entity authorized by the developer to make contracts on behalf of the developer for engineering surveys, preparation of design documentation, construction, renovation, major maintenance of capital construction objects, produce task orders for the above specified activities, provide the individuals or entities performing engineering surveys and (or) preparing design documentation, performing construction activities, renovation, major maintenance of capital construction objects, with materials and documents necessary for performance of their obligations; approve design documentation, sign documents necessary for obtaining permits for commissioning of the capital construction objects, and perform other functions in accordance with the present Code. Developer can perform the function of technical client himself. (“Town Building Code of the Russian Federation” No. 190-FZ)

TECHNICAL REQUIREMENTS TO INSTRUMENTATION (Технические требования к средствам измерений) – requirements defining specifics of design of instrumentation (without limitations to their technical improvement) in order to maintain their metrological characteristics in the course of operation of instrumentation, to ensure credibility of measurement results, to prevent unauthorized adjustments and interference, and requirements ensuring safety and electromagnetic compatibility of instrumentation. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

technical state (СОСТОЯНИЕ техническое) – combination of properties and qualities of component (object as a whole) subject to changes during manufacturing or operation, characterized in certain moment in time by the attributes specified by technical documentation and (or) determined based on the results of reliability (lifetime) management of components. (NP-017-2000, NP-024-2000)

technical systems and components with measurement functions (системы и устройства с измерительными функциями Технические) – technical systems and components, performing, in addition to their main function, measurement functions. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

TECHNOGENIC EXPOSURE (техногенное Облучение) - see EXPOSURE, TECHNOGENIC (Облучение техногенное).

TECHNOGENIC EXTERNAL IMPACT (техногенное ВНЕШНЕЕ Воздействие) – see IMPACT (ВОЗДЕЙСТВИЕ).

TECHNOGENIC IMPACT (ТЕХНОГЕННОЕ ВОЗДЕЙСТВИЕ) – see IMPACT (ВОЗДЕЙСТВИЕ).

TECHNOGENIC SOURCE OF RADIATION (техногенный Источник излучения) – see SOURCE (ИСТОЧНИК).

TECHNOGENICALLY CHANGED RADIATION BACKGROUND (ТЕХНОГЕННО ИЗМЕНЕННЫЙ РАДИАЦИОННЫЙ ФОН)) – see BACKGROUND (ФОН).

tectonic creep (Тектонический крип) – process characterized by slow relative movements of earth crust blocks along tectonically active faults and fissures. (NP-064-05)

temporary placement of nuclear fuel (размещение ядерного топлива Временное) – placement of NF in the locations allowable by the design, outside of storage facilities. (NP-061-05)

TEMPORARY STORAGE OF LRW (ВЫДЕРЖКА ЖРО) – storage of LRW with the purpose of decreasing radioactivity and heat generation due to decay of short-lived radionuclides. (NP-019-2000)

TERRITORIES CONTAMINATED BY RADIONUCLIDES (ЗАГРЯЗНЕННЫЕ РАДИОНУКЛИДАМИ ТЕРРИТОРИИ) – territories (land and water bodies in the industrial, sanitary protection zones and monitored zones) of the nuclear facilities, on which radioactive substances are present in the amount exceeding the minimum values established by federal rules and regulations on the use of nuclear energy, and this amount of radioactive substances can cause radioactive exposure. (NP-034-01)

TERRITORIES CONTAMINATED BY RADIONUCLIDES (ТЕРРИТОРИИ, ЗАГРЯЗНЕННЫЕ РАДИОНУКЛИДАМИ) – see RADIONUCLIDE CONTAMINATED TERRITORIES (ЗАГРЯЗНЕННЫЕ РАДИОНУКЛИДАМИ ТЕРРИТОРИИ).

tests (Испытания)

Integral tests (испытания интегральные) – integrated test of the containment (leaktight enclosure) for strength and leaktightness resulting in confirmation of its design characteristics (actual leak being within the design limits, and ability to withstand the loads defined in the design for design basis accidents). (NP-010-11)

Integrated tests of full scope simulator (комплексные испытания пмт) – a process of testing technical properties, algorithms and software of the full scope simulator as a whole in the entire range of modeled operation modes and functions in order to verify compliance of the simulator with the technical specifications, requirements of the current rules and regulations, adequacy of functions and training capabilities of the simulator, and adequacy of the processes modeled in it to experimental and analytical data for the prototype unit. (NP-003-97)

Local (individual) tests (испытания локальные (индивидуальные)) –tests of components of localizing safety systems confirming the design characteristics of leaktightness of the components. (NP-010-11)

Tests of standard specimens or instruments for type certification purposes (испытания стандартных образцов или средств измерений в целях утверждения типа) – activities aimed at determining metrological and technical parameters of standard specimens or instruments of a certain type. (Federal Law No.102-FZ “On ensuring unification of measurements”)

thermocarst (Термокарст) – processes of melting of ice formations contained in frozen soils or melting through strongly disperse soils resulting in settlements and cavity formation. (NP-064-05)

thickness of main metal of OVERLAID component (product), nominal (толщина основного металла наплавленной детали (изделия) Номинальная) – see NOMINAL THICKNESS OF MAIN METAL OF OVERLAYED COMPONENT (PRODUCT) (Номинальная толщина основного металла наплавленной детали (изделия)).

thorium, non-irradiated (торий Необлученный) – see NON-IRRADIATED THORIUM (НЕОБЛУЧЕННЫЙ ТОРИЙ).

threat to radioactive substances and radioactive sources during transportation (Угроза РВ и РИ при транспортировании) – potential possibility for sabotage action by intruders against radioactive substances and radioactive sources, or theft of radioactive substances and radioactive sources during transportation. (NP-073-11)

threshold effect (Пороговый эффект) – substantial stepwise decrease of safety status of power unit caused by small changes of parameters. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Cliff edge effect” (Пороговый эффект).

TIME SCALE, REAL (МАСШТАБ ВРЕМЕНИ РЕАЛЬНЫЙ) – see REAL TIME SCALE (РЕАЛЬНЫЙ МАСШТАБ ВРЕМЕНИ).

TORNADO (Смерч) – strong and highly destructive atmospheric vortex of small size (diameter up to 1000 m), air in which spins at high velocity (up to 100 m/s), which occurs in storm clouds and protrudes downwards, often reaching ground surface in the form of dark could sleeve or trunk with the diameter of tens or hundreds of meters. It has a limited lifespan and travels together with the cloud. It consists of rapidly rotating air, particles of moisture, sand, dust and other inclusions. It is characterized by high wind velocity in the cone, rarefaction in the middle of the vortex, and hazard of impact of flying objects lifted by the wind. (NP-064-05)

TORNADO INTENSITY CLASS (КЛАСС интенсивности смерча) – a universal characteristic that determines the main dynamic parameters of a tornado vortex. It is defined per Fujita F-scale based on qualitative and quantitative attributes of the tornado. (RB-022-01)

town buildiNg activities (Градостроительная деятельность) – activities associated with development of territories, including towns and other settlements, performed in the form of territory planning, town building zoning, design and architectural engineering, construction, renovation and maintenance of buildings and structures. (“Town Building Code of the Russian Federation” No. 190-FZ)

townbuilding zoning (зонирование Градостроительное) – zoning of municipal territories for the purpose of defining territorial zones and determining urban development specifications. (“Town Building Code of the Russian Federation” No. 190-FZ)

traceability (Прослеживаемость) – a property of reference standard of a unit or measurement system, consisting in documentally confirmed relation to the primary state reference standards of the corresponding measurement unit in the form of direct comparison of reference standards, gauging or calibration of instruments. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

transfer of conservation facility for especially hazardous radioactive wastes into rad waste storage facility (Перевод пункта консервации особых радиоактивных отходов в пункт захоронения радиоактивных отходов) – change of status of especially hazardous radioactive waste facility allowable in case of availability of safety barriers insulating radioactive wastes from the environment for the period of their potential hazard. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

transfer of MEASUREMENT unit value (Передача единицы величины) – reduction of a unit of measurement stored in the instrument to the unit, reproduced by reference standard of this value or standard specimen. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

transfer of the special radioactive waste placement facility into special radioactive waste conservation facility (Перевод пункта размещения особых радиоактивных отходов в пункт консервации особых радиоактивных отходов) – change of status of radioactive waste storage facility associated with completion of actions associated with creation of safety barriers in the facility in accordance with the design. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

transport index (Транспортный индекс) – see INDEX (ИНДЕКС).

transportation and process operations (Транспортно-технологические операции) – manipulations associated with translocation of cargo and equipment anticipated by the nuclear facility technological process. (NP-043-03)

transportation package set, on-site (комплект Внутриобъектовый транспортный упаковочный) – see ON-SITE TRANSPORTATION PACKAGE SET (ВНУТРИОБЪЕКТОВЫЙ ТРАНСПОРТНЫЙ УПАКОВОЧНЫЙ КОМПЛЕКТ).

TREND (Тренд) – a consistent pattern characterizing generic long-term tendency in change of a parameter with time (RB-046-08)

tropical CYCLONE (Циклон тропический) – a giant atmospheric vortex characterized by decrease of pressure towards the vortex center and air circulation in the vortex around the center in the counterclockwise direction in the northern hemisphere, and in the clockwise direction in the southern. (NP-064-05)

tsunami (Цунами) – process of oscillation of water surface in the form of sequential waves caused by pulse wise disturbance of the water body caused by movements caused by underwater earthquake, volcano eruptions, underwater landslides, or collapse of coastal line. (NP-064-05)

tungsten inclusion (Вольфрамовое включение) – non-melted particle (fragment) of tungsten electrode incorporated into a weld or weld overlay metal. (PNAE G-7-008-89)

type line (Типовой ряд) – group of products of similar design differing only in main dimensions. (NP-068-05)

TYPE OF INSTRUMENTS (Тип средств измерений) – group of instruments designed for measuring same parameters expressed in the same measurement units, based on the same action principle, having identical design and produced per the same technical documentation. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

TYPE OF NUCLEAR MATERIALS (Вид ядерных материалов) – array of nuclear materials, the parameters of which are within the limits established by Rosatom State Corporation and (or) operating utility. (NP-030-12)

typhoon (Тайфун) – tropical cyclone with the wind velocity above 32 m/s. (NP-064-05)

ULTIMATE HEAT SINK (КОНЕЧНЫЙ ПОГЛОТИТЕЛЬ (ТЕПЛА)) – external media (water body and (or) atmosphere), to which residual heat generated by nuclear fuel is transferred. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Ultimate heat sink” (Конечный поглотитель тепла).

unallowable operation (недопустимая эксплуатация) – non-designed operation of a machine and (or) equipment. (Technical Specifications on safety of machinery and equipment)

UNAUTHORIZED ACCESS (НЕСАНКЦИОНИРОВАННЫЙ ДОСТУП) – access to instrumentation, controls or equipment without proper authorization. (NP-026-04)

UNAUTHORIZED ACTION (НЕСАНКЦИОНИРОВАННОЕ ДЕЙСТВИЕ) – accomplished or attempted act of sabotage, theft of nuclear materials, radioactive source, radioactive substance, radioactive wastes, unauthorized access, transportation (entry) of unallowable objects, disabling of security systems or their components. (NP-034-01)

UNCERTAINTY (Неопределенность) – ambiguity (vagueness) of determination of probabilistic safety parameters associated with probabilistic nature of modeled phenomena and incomplete knowledge of development of physical processes. (RB-024-11)

undercut (Подрез) – sharp indentation at the boundary between welded joint surface and main metal or on the boundary of surfaces of two neighboring weld beds. (PNAE G-7-010-89)

UNIDENTIFIABLE FAILURE (НЕОБНАРУЖИВАЕМЫЙ ОТКАЗ) – see FAILURES (ОТКАЗЫ).

UNIFICATION OF MEASUREMENTS (Единство измерений) – state of measurements, at which their results are expressed in the units adopted in the Russian Federation, and the accuracy of measurements lies within the prescribed boundaries. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

UNIT (Единица величины) – fixed value of a parameter assumed as a unit of this parameter and used for quantification of congeneric values. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

unit, accounting (единица Учетная) – see ACCOUNTING UNIT (УЧЕТНАЯ ЕДИНИЦА).

upper seal (Уплотнение верхнее) – a seal duplicating a packing gland or bellows sealing formed by surfaces made on the spindle (stem) and in the cover to provide leaktightness of the inner cavity of the valve with respect to inner fluid in the uppermost position of the valve plug. (NP-068-05)

URANIUM (УРАН)

Depleted uranium (Обедненный уран) – uranium, containing smaller mass percentage of uranium-235 than natural uranium. Small amount of uranium-234 is present. (NP-053-04)

Comment

This term is fully equivalent to the same term in the IAEA Glossary –“Depleted uranium” (Обедненный уран).

Enriched uranium (Обогащенный уран) – uranium, containing larger mass percentage of uranium-235 than natural uranium. Small amount of uranium-234 is present. (NP-053-04)

Comment

A corresponding term in the IAEA Glossary is “Enriched uranium” (Обогащенный уран).

High enriched uranium (Высокообогащенный уран) – uranium with the enrichment of at least 20% by uranium-235 isotope. (NP-030-12)

Low enriched uranium (Низкообогащенный уран) – uranium with the enrichment of at least 0.73%, but no more than 20% by uranium-235 isotope. (NP-030-12)

Natural uranium (Природный уран) – uranium containing natural mixture of uranium isotopes (approximately 99.28% uranium-238 and 0.72% uranium-235 by mass). Small amount of uranium-234 is present. (NP-053-04)

Comment

A corresponding term in the IAEA Glossary is “Natural uranium” (Природный уран).

Non-irradiated uranium (Необлученный уран) – uranium, containing no more than 2·10³ Bq plutonium per 1 g of uranium-235 and no more than 9 MBq fission products per 1 g of uranium-235 and no more than 5·10^-3 g uranium-236 per 1 g of uranium-235. (NP-053-04)

urban development regulations (регламент Градостроительный) – forms of allowable use of land plots within the boundaries of appropriate territory along with everything over and under the surface of the land plots, which is used during construction and subsequent operation of capital construction objects, limiting (minimum and maximum) sizes of land plots and limiting parameters of allowable construction or renovation of capital construction objects, as well as limitations imposed on the use of land plots and capital construction objects. (“Town Building Code of the Russian Federation” No. 190-FZ)

VALVE TRIM (Исполнение арматуры) – design of a specific type of a valve with the following defined parameters: purpose, nominal diameter, operating pressure, material of main components, method of control and of connection to the pipeline, etc. (NP-068-05)

valve type (Тип арматуры) – classifier characterizing functional properties and design specific of a valve, e.g. wedge valve, regulating valve. (NP-068-05)