Glossary of nuclear terms

ACCELEROGRAM (АКСЕЛЕРОГРАММА) – dependence of oscillation acceleration upon time. (NP-031-01)

Analogue accelerogram (акселерограмма аналоговая) – accelerogram recorded during a real earthquake and adopted for analysis of seismic resistance based on its conformance with seismic, tectonic and soil conditions of nuclear plant site. (NP-031-01)

Earthquake accelerogram (акселерограмма землетрясения) – accelerogram of the free ground surface during earthquake. (NP-031-01)

Floor response accelerogram (акселерограмма поэтажная) – response accelerogram for individual elevations of a structure, on which equipment is installed. (NP-031-01)1

Response accelerogram (акселерограмма ответная) – accelerogram of a structure defined from analysis of forced oscillations during seismic impact. (NP-031-01)

Synthesized accelerogram (акселерограмма синтезированная) – accelerogram obtained analytically based on statistic treatment and analysis of a number of accelerograms and (or) spectra of real earthquakes taking into account local seismic conditions. (NP-031-01)

ACCESS, UNAUTHORIZED (ДОСТУП НЕСАНКЦИОНИРОВАННЫЙ) – see UNAUTHORIZED ACCESS (НЕСАНКЦИОНИРОВАННЫЙ ДОСТУП).

ACCIDENT (АВАРИЯ)¹ – a deviation from normal operation of a nuclear power plant associated with release of radioactive materials and/or ionizing radiation beyond the limits specified by the design documentation (hereinafter – design) in the amount exceeding the established safe operation limits. An accident is characterized by an initiating event, progression sequence and consequences. (OPB-12)

• destruction or damage of machinery and (or) equipment, occurrence of uncontrolled explosions and (or) release of hazardous substances during operation of machinery and (or) equipment. (Technical Specifications on safety of machinery and equipment)

Comment

In the IAEA Glossary there are two terms corresponding to this one – “Accident” (Авария) and “Accident conditions” (Аварийные состояния)². However, they are defined rather qualitatively than quantitatively, whereas the Russian definition specifies clear quantitative boundaries for such events: release of radioactive materials and/or ionizing radiation beyond the limits specified by the design documentation in the amount exceeding the established safe operation limits. Such a definition for an accident at a nuclear power plant is assumed because radioactive materials and ionizing radiation generated during the plant operation are specific to the nuclear power plants and are the main hazards for personnel, public and environment to be protected against. In the IAEA Glossary, “Accident state” is defined as a more severe deviation from normal operation than “anticipated operational event", which is defined as deviations from normal operation not leading to damage of safety related equipment or to the state that is expected to occur at least once in the lifetime of the plant. The radiological consequences are not mentioned in the definition. However, in the definition of “Accident” radiological consequences are indirectly mentioned by using the expression “radiation protection”.

Beyond design basis accident (Запроектная авария) – an accident caused by an initiating event not considered for the design basis accidents or accompanied by additional failures of safety systems beyond a single failure or operator errors.(OPB-12)

Comment

The IAEA Glossary contains the same term. However, in the later IAEA standard SSR-2/1 it was replaced by the term “Design extension conditions” (Состояния расширенного проекта).

Design basis accident (Проектная авария) – an accident, for which initiating events and end states are defined by the design, and safety systems are in place ensuring that the consequences of the accident are within the limits established for such accident taking into account single failure principle for safety systems or single operator error independent of the initiating event. (OPB-12, NP-031-01)

Comment

A corresponding term in the IAEA Glossary is “Design basis accident” (Проектная авария).

Nuclear accident (ядерная авария) – an accident, accompanied by fuel element damage beyond the established safe operation limits, or an accident caused by:

• degradation of control and monitoring of chain fission reaction;

• occurrence of criticality during refueling, transportation and storage of nuclear fuel. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Nuclear accident” (Ядерная авария). However, it is defined through a more generic term "Accident" (авария), and does not contain such specific attributes, as in the Russian definition.

Radiation accident (радиационная авария) – loss of control of ionizing radiation source caused by equipment malfunction, inappropriate personnel actions, natural catastrophes or other causes that resulted or could have resulted in exposure of people above the established limits or to radioactive contamination of environment. (Federal Law No. 3-FZ “On radiation protection of public”, NRB 99/2009)

Severe beyond design basis accident (тяжёлая запроектная авария) – beyond design basis accident with damage of fuel elements above maximum design limit. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Severe accident” (Тяжелая авария). The Russian definition of this term is given on the quantitative level, whereas IAEA definition is qualitative.

ACCIDENT CONSEQUENCES (ПОСЛЕДСТВИЯ АВАРИИ) – radiological situation resulting from accident, causing harm and losses due to excess of established limits of radiation impact on personnel, public and environment. (OPB-12)

ACCIDENT MANAGEMENT (УПРАВЛЕНИЕ АВАРИЕЙ) – actions aimed at preventing development of design basis accidents into beyond design basis accidents and at mitigating consequences of beyond design basis accidents. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Accident management” (Управление аварией).

ACCIDENT SEQUENCE (Аварийная последовательность) – a sequence of events leading to a certain end state of a power unit of a nuclear power plant. This sequence includes an initiating event, events associated with successful or unsuccessful performance of safety functions by the plant systems and/or personnel, and successful or unsuccessful end state. (RB-032-04, RB-024-11)

ACCIDENT SEQUENCE (ПУТЬ ПРОТЕКАНИЯ АВАРИИ) – sequence of states of plant systems and components during accident progression. (OPB-12)

accounting batch (УЧЕТНАЯ ПАРТИЯ) – same as MATERIAL BATCH (ПАРТИЯ МАТЕРИАЛА).

ACCOUNTING DATA (Учетные данные)³ – information about present amounts, composition, location and state of RW and RS, predicable attributes of accounting units used for accounting purposes. (NP-067-11)

ACCOUNTING DATA (Учетные данные)⁴ – parameters of products, NM, predicable attributes of accounting units collected and stored in the framework of accounting. (NP-030-12)

ACCOUNTING UNIT (УЧЕТНАЯ ЕДИНИЦА)⁵ – object containing nuclear materials, having an individual predicable attribute or individual set of predicable attributes, parameters of which are recorded in the accounting documents, and integrity is confirmed by access control measures from the moment of recording of the accounting information. (NP-030-12, NP-025-2000)

Accounting unit of radioactive substances or radioactive wastes (Учетная единица радиоактивных веществ или радиоактивных отходов) – identifiable object containing RW or RS, characteristics of which are recorded in a document and /or an entry (line) in RW or RS accounting documents, and integrity of which remains unchanged over a certain period of time. (NP-067-11)

accounting, operative technical (учет Оперативно-технический) – see operative technical accounting (Оперативно-технический учет).

accumulated radioactive wastes (Накопленные радиоактивные отходы) – Radioactive wastes generated before adoption of Federal Law No. 190-FZ “On radioactive waste handling and amendments of certain legislative acts of the Russian Federation” and radioactive wastes registered in the radioactive waste registry according to the procedures prescribed by the federal legislation. (Refined definition of Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

ACT OF SABOTAGE (ДИВЕРСИЯ) – any intentional action with respect to nuclear materials, nuclear installations, storage facilities, radiation sources, radioactive substances or means of transportation for nuclear material, nuclear installation, radiation sources, radioactive substances or radioactive wastes, and such action can directly or indirectly cause an emergency situation and jeopardize health and life of people due to effects of radiation or can cause radioactive contamination of environment. (Refined definition of NP-034-01)

ACTIVE FAULT (РАЗЛОМ АКТИВНЫЙ ) – tectonic fault, in the vicinity of which relative displacement of adjacent blocks of earth crust by 0.5 meters and more occurred in the Quaternary period of geological development, or their relative displacement with velocity gradient of 5·10^-5 per year or more is presently observed (Refined definition of RB-019-01, NP-032-01)

ACTIVE SYSTEM (ELEMENT) (АКТИВНАЯ СИСТЕМА (ЭЛЕМЕНТ)) – a system (component), the functioning of which depends on normal operation of another system (component), e.g. control safety system, power source, etc. (OPB-12)

Comment

In the IAEA Glossary, there is a corresponding term “Active component”, the operation of which depends on such factors as actuation, mechanical movement or 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 a 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, of which the element is a part. Thirdly, unlike 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, as it works based on the passive principle of operation.

ACTIVITY (Активность) – measure of radioactivity. For a given quantity of radionuclide in a specific energy state at a given moment, activity A is expressed as:

where dN is the anticipated number of spontaneous nuclear transformations from a given energy level over time interval dt⁶. (NP-053-04, NRB-99/2009)

Comment

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

Equivalent equilibrium volumetric activity (of radon daughters) (эквивалентная равновесная объемная активность (эроа) (дочерних продуктов изотопов радона)) – weighed sum of volumetric activities of short-lived products of decay of radon isotopes ²¹⁸Po (Rae); ²¹⁴Pb (RaB); ²¹⁴Bi (RaC); ²¹²Pb (ThB); ²¹²Bi (ThC), respectively:

where Аi are volumetric activities of decay products of radon isotopes. (NRB-99/2009)

Comment

Corresponding term in the IAEA Glossary is “Equilibrium equivalent concentration” (Эквивалентная равновесная объемная активность).

Minimum significant activity (Минимально значимая активность (МЗА)) – activity of an open source of ionizing radiation in a room or at a workplace, exceedence of which requires obtaining a permit from the state sanitary and epidemiological regulatory authority for use of such a source, provided that minimum significant specific activity is also exceeded. (NRB-99/2009)

Comment

A corresponding term in the IAEA Glossary is “Minimum significant activity” (Минимальная значимая активность).

Minimum significant specific activity (Минимально значимая удельная активность (МЗА)) – activity of an open source of ionizing radiation in a room or at a workplace, exceedence of which requires obtaining a permit from the state sanitary and epidemiological regulatory authority for use of such a source, provided that minimum significant activity is also exceeded. (NRB-99/2009)

Seismic activity (активность сейсмическая) – number of earthquakes of certain intensity per unit of time per unit of area. (RB-019-01)

Specific activity (активность удельная) – ratio of activity A of radionuclide in substance to mass of the substance ⁷:

.

Comment

A corresponding term in the IAEA Glossary is “Specific activity” (Удельная активность).

Specific activity of material (Активность материала удельная) – activity per unit of mass or volume of material, in which radionuclides are generally homogeneously distributed. (NP-053-04)

Comment

A corresponding term in the IAEA Glossary is “Specific activity” (Удельная активность), which is defined both for materials and radionuclides.

Specific activity of isotope (удельная активность изотопа) – activity per unit of mass of the isotope. (NP-053-04)

Comment

A corresponding term in the IAEA Glossary is “Specific activity” (Удельная активность).

Volumetric activity (активность объёмная) – ration of activity A of radionuclide in a substance to volume V of the substance⁸:

.

actual presence of radioactive substances and radioactive materials (Фактическое наличие радиоактивных веществ и радиоактивных отходов) – amounts of RW and RS measured or analytically determined in accordance with formalized procedures existing in the organization and actually available in the organization at the present time. (NP-030-12)

actually present amount of nuclear material (Фактически наличное количество ядерного материала) – measured or otherwise determined in accordance with formalized inventory taking procedures mass of NM actually present in the MBA at a given time. (NP-030-12)

actuator, emergency protection (орган АВАРИЙНОЙ ЗАЩИТЫ Рабочий) – see EMERGENCY PROTECTION ACTUATOR (РАБОЧИЙ ОРГАН AЗ).

adverse FACTORS of explosion in the atmosphere (Поражающие факторы взрыва в атмосфере) – consequences of explosion processes hazardous for structures, equipment and human. Pressure waves in the air and seismic explosive waves, along with missiles (primary and secondary fragments, debris, components of equipment) have the largest damage potential. Secondary factor of explosion in the atmosphere is fire. (RB G-05-039-96)

airlock (Шлюз) – structure (room) or facility forming a part of containment system (leaktight enclosure) and designed for passage of people or transportation of cargo into (from) the accident localization zone without loss of leaktightness of the containment. (NP-010-11)

alarm, fire (СИГНАЛИЗАЦИЯ ПОЖАРНАЯ) – see FIRE ALARM (ПОЖАРНАЯ СИГНАЛИЗАЦИЯ).

ALLOWABLE EFFLUENT (Допустимый сброс) – see EFFLUENT (СБРОС).

ALLOWABLE EFFLUENT OF RADIOACTIVE SUBSTANCES (Допустимый сброс) – see EFFLUENT (СБРОС).

ALLOWABLE RISK (допустимый риск) – level of risk associated with the use of a machine and (or) equipment based on technical and economic capabilities of the manufacturer, which are to provide for the required level of safety for all the stages of the lifecycle of products. (Technical Specifications on safety of machinery and equipment)

ANALYSIS (АНАЛИЗ)

Deterministic safety analysis (детерминистический анализ безопасности) – nuclear plant safety analysis for given operational states of the plant, postulated initiating events and given status of systems and components affecting the accident sequences, performed in order to confirm compliance of the plant with the established safety criteria or design limits. (OPB-12)

Comment

The IAEA Glossary provides definition of a similar term “Deterministic analysis” (Детерминистический анализ).

Importance analysis (анализ значимости) – analysis of influence of individual parameters of probabilistic model on the results of PSA. (RB-024-11)

Level 1 PSA (ВАБ АС уровня 1) – PSA of a nuclear plant consisting in development of probabilistic models of a nuclear power unit, identification of end states with damaged fuel, and evaluation of probabilities of occurrence of these states. (RB-032-04)

Level 2 PSA (ВАБ АС уровня 2) – PSA of a nuclear plant consisting in development of probabilistic models of a nuclear power unit for identification of probabilities of emergency releases from the plant into environment, including maximum emergency release. (RB-032-04)

Probabilistic safety analysis (вероятностный анализ безопасности) – qualitative and quantitative analysis of nuclear plant safety performed for defining the probabilities of occurrence of initiating events, accident sequences and end states, including probabilities of severe beyond design basis accidents and major releases. (OPB-12)

Comment

This term corresponds to the IAEA Glossary term “Probabilistic safety assessment” (Вероятностный анализ безопасности)

Sensitivity analysis (анализ чувствительности) – assessment of influence of changes of input data of a probabilistic model on the values of probabilistic parameters of nuclear plant safety. (RB-024-11)

Uncertainty analysis (анализ неопределенности) – analysis of influence of possible uncertainties in determination of IE frequencies, equipment reliability parameters and human error probabilities, assumptions and limitations of the analysis, incompleteness of knowledge about development of physical processes, on the results of PSA. (RB-024-11)

Comment

The IAEA Glossary contains the same term “Uncertainty analysis” (Анализ неопределенностей). However, it is defined more generically as analysis performed for the sake of evaluation of uncertainties and boundaries of errors of the parameters used for solving a problem and of the ultimate results.

analyzed situation (РАСЧЕТНАЯ СИТУАЦИЯ) – combination of possible conditions determining analytical requirements to structural elements, engineering and technical support systems and parts thereof, taken into account in the analysis. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

ANNUAL INTAKE LIMIT (Предел годового поступления (ПГП)) – level of intake of a particular radionuclide into human organism within a year, which, under multi-factor influence causes exposure of a reference person with anticipated dose equal to corresponding limit of annual dose. (NRB-99/2009, PRB AS-99)

Comment

This term corresponds to the IAEA Glossary term “Annual limit on intake (ALI)” (Предел годового поступления (ПГП)).

APPROVAL BY lead material science organization (Согласование головной материаловедческой организации) – see MATERIAL SCIENCE ORGANIZATION (МАТЕРИАЛОВЕДЧЕСКАЯ ОРГАНИЗАЦИЯ)

ARRAY SPACING (Шаг решетки) – distance between the axes of neighboring fuel assemblies, casks or packages located in the focal points of a regular lattice. (NP-061-05)

assigned life (Назначенный ресурс) – cumulative operative time, at reaching which operation of machinery and (or) equipment is to be discontinued regardless of their technical conditions. (Technical Specifications on safety of machinery and equipment)

Assigned life (of a valve) (Назначенный ресурс (арматуры)) – total operation time of a valve defined by design, after which its continued operation is possible only after special decision has been made based on performed operational safety analysis, e.g. after technical inspection (diagnostics). (NP-068-05)

assigned lifetime (Назначенный срок службы) – calendar duration of operation of a machine and (or) equipment, at reaching of which the operation of a machine and (or) equipment is to be terminated regardless of the technical conditions. (Technical Specifications on safety of machinery and equipment)

Assigned lifetime (of a valve) (Назначенный срок службы (арматуры)) – calendar duration of operation of a valve defined by design, after which its continued operation is possible only after a special decision has been made based on performed operational safety analysis, e.g. after technical inspection (diagnostics). (NP-068-05)

ASSIGNED OPERATION (SERVICE) LIFE (СРОК эксплуатации (службы) назначенный) – calendar duration of operation of a nuclear plant specified by the design, subsequent operation after completion of which is possible only based on a special decision made after safety and feasibility analysis. (NP-017-2000)

Comment

A corresponding term in the IAEA Glossary is “Design life” (Проектный (расчетный) срок службы).

assigned storage life (назначенный срок хранения) – calendar term of storage of a machine and (or) equipment, after reaching which its storage is to be terminated regardless of the technical conditions. (Technical Specifications on safety of machinery and equipment)

AUDIT (ПРОВЕРКА)⁹ – documented activities performed for assessment of effectiveness of quality assurance program. (RB-003-98)

Comment

A corresponding term in the IAEA Glossary is “Verification” (Верификация (проверка)).

AUTOMATED CONTROL (УПРАВЛЕНИЕ АВТОМАТИЗИРОВАННОЕ) – control with participation of personnel with the aid of automation aids. (NP-026-04)

AUTOMATED PROCESS CONTROL SYSTEM (АВТОМАТИЗИРОВАННАЯ СИСТЕМА УПРАВЛЕНИЯ ТЕХНОЛОГИЧЕСКИМ ПРОЦЕССОМ) – a system composed of personnel (staff) and a complex of process control automation means. (NP-003-97)

AUTOMATIC CONTROL (УПРАВЛЕНИЕ АВТОМАТИЧЕСКОЕ) – control by means of automation aids without participation of personnel. (NP-026-04)

AUXILIARY CONTROL ROOM (РЕЗЕРВНЫЙ ПУНКТ УПРАВЛЕНИЯ) – part of the power unit located in the room designed to enable safe transfer of power unit into subcritical cooled down state and maintaining this state for as long as necessary, actuation of safety systems and obtaining information about the reactor status. (OPB-12)

availability factor (Коэффициент готовности) – probability of a component (object) being operable in arbitrary moment of time, except for scheduled periods during which its intended use is not expected to be required. (NP-068-05)

AVALANCHES (ЛАВИНЫ)

Snow avalanches (Лавины снежные) – a process consisting in concerted movement of snow masses falling or sliding from mountain slopes in the form of continuous body (wet avalanches) or pulverized snow (dry avalanches). (NP-064-05)

Snow-rock and rubble-rock avalanches (Лавины снежно-каменные и щебенисто-глыбовые) – a process consisting in concerted sliding of snow and rock or rubble and rock masses from mountain slopes under gravity force and dynamic loads (seismic or explosive). (NP-064-05)

BACKGROUND (ФОН)

Natural radiation background (Естественный радиационный фон) – radiation dose caused by space radiation and radiation of natural isotopes naturally distributed in the ground, water, air, other elements of biosphere, food products and human organism. (Federal Law No. 3-FZ “On radiation protection of public”, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Natural background” (Естественный фон).

Technogenically altered radiation background (Техногенно измененный радиационный фон) – natural radiation background altered by human activities. (Federal Law No. 3-FZ “On radiation protection of public”. (PRB AS-99)

BARRIER (Барьер) – an obstacle on the way of propagation of ionizing radiation, radioactive substances (radionuclides) into the environment. Leaktight enclosures of rooms and storage facilities, containers, equipment and pipelines containing radioactive equipment, or physical and chemical form of conditioned RW can serve as barriers. (NP-002-04)

Comment

This term is fully equivalent to the same term in the IAEA Glossary. However, it is formulated broader – not only as a physical obstacle on the way of propagation of ionizing radiation, radioactive substances (radionuclides) into the environment, but also an obstacle preventing or precluding penetration of people or propagation of some other phenomena (e.g. fire).

Barrier (барьер) – a component of natural geological formation or engineering structure, preventing radionuclides and (or) ionizing radiation from propagating into the environment. (RB-014-2000)

Barrier ensuring protection of public and environment (барьер для обеспечения безопасности населения и окружающей среды) – packaging of radioactive waste, engineering structure of radioactive waste storage facility or their parts, or an element of natural geological formation preventing ionizing radiation from propagating into the environment (Federal Law No.190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

Physical barrier (Физический барьер) – an obstacle on the way of propagation of ionizing radiation and radionuclides into the environment. (NP-058-04)

Physical barrier during decommissioning of a nuclear power plant (Физический барьер при выводе из эксплуатации блока АС) – engineering structure, hardware or system, limiting release of radioactive substances or ionizing radiation into the rooms of nuclear power plant or to environment. (NP-012-99)

Protective barriers (Защитные барьеры) – barriers consisting of a complex of hardware designed for confining radioactive substances and ionizing radiation within the boundaries prescribed by the nuclear facility design. (NP-064-05)

bases of buildings or structures (ОСНОВАНИЯ ЗДАНИЯ ИЛИ СООРУЖЕНИЯ) – base of a building or structure (hereafter – base) is the mass of soil receiving loads and impacts from the building or structure and transferring to the building or structure the impacts caused by natural or technogenic processes occurring in the soil bulk. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

basic event (Базисное событие) – an elementary event included into probabilistic model of a nuclear plant and characterized by a set of quantitative probabilistic parameters. (RB-024-11)

batch of radioactive substances (radioactive wastes (Партия радиоактивных веществ (радиоактивных отходов)) – totality of RS (RW) contained in the accounting units, quantitative and (or) qualitative composition of which, for the purposes of RW and RS accounting and control is determined based on single set of data and measurement results recorded in the accounting documents. (NP-030-12)

bedrock (Порода коренная) – primary rock or other formation characterized by the velocity of propagation of transversal (shear) waves of at least 700 m/s. (RB-006-98)

BELLOWS (Сильфон) – thin-walled (single- or multi-layer) tube or chamber. (NP-068-05)

bellows module (Сильфонный узел) – bellows together with welded end pieces. (NP-068-05)

beyond design BASIS accident (запроектная авария) – see ACCIDENT (АВАРИЯ).

Bistable valve (Клапан двухпозиционный) – see VALVES (АРМАТУРА).

blowhole (СВИЩ) – a defect in the form of conical or tube-shape indentation in a weld. (PNAE G-7-010-89)

BREACH IN ACCOUNTING AND control of racioactive substances and radioactive wastes (Нарушение в учете и контроле радиоактивных веществ и радиоактивных отходов) – lack or excess, unauthorized use and/or illegal translocation of RS and RW, errors in the accounting or reporting documents, damage of access control equipment and systems, inconsistency of predicable attributes of accounting units with records, violation of the procedures for use and transfer of RW and RS. (Refined definition of NP-064-067-11)

building (ЗДАНИЕ) – result of construction represented by a major construction system with above-ground and (or) underground parts including rooms, engineering networks and utilities, and support systems; it is designed for accommodation and (or) activities of people, industrial activities, storage of products, or livestock housing. (Federal Law No. 384-FZ “Technical Specifications on safety of buildings and structures”)

burn-through (Прожог) – defect in the form of reach-through hole in the weld formed due to efflux of part of liquid metal of the weld pool during welding process. (PNAE G-7-010-89)

cadastral registry of radioactive waste storage facilities (Кадастр пунктов хранения радиоактивных отходов) – systemized documentary information about radioactive waste storage facilities, owners of the facilities and about the wastes stored therein. (Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

CALCULATION UNCERTAINTY, SYSTEMATIC COMPONENT (компонента погрешности расчета Методическая) – see SYSTEMATIC COMPONENT OF CALCULATION UNCERTAINTY (Методическая компонента погрешности расчета).

calibration of instruments (Калибровка средств измерений) – set of operations performed for determining actual metrological properties of an instrument. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

Comment

A corresponding term in the IAEA Glossary is “Calibration” (Калибровка).

capital construction object (Объект капитального строительства) – building, structure, facilities, construction of which is not complete (hereafter – incomplete construction objects), except for temporary buildings, kiosks, tents and similar structures. (“Town Building Code of the Russian Federation” No. 190-FZ)

category (of packaging or overpack) (Категория (упаковки или транспортного пакета)) – designation of radiation hazard level determined based on the radiation levels on the surface and transport index. (Refined definition of NP-053-04)

Comment

A corresponding term in the IAEA Glossary is “Transport Index (TI)” (Транспортный индекс (ТИ)).

CATEGORY OF EMERGENCY RELEASE (Категория аварийного выброса) – combination of end states with emergency release grouped based on the attributes affecting the quantity and composition of radioactive material (ionizing radiation) released into environment. (RB-044-09)

CATEGORY OF RADIONUCLIDE SOURCE IN TERMS OF POTENTIAL RADIATION HAZARD (Категория радионуклидного источника (РНИ) по их потенциальной радиационной опасности) – parameter of a radionuclide source determined by radiation hazard for personnel and public in case of a potential radiation accident. (NP-073-11)

caving and sinking (Оседания и провалы) – terrain relief forms occurring due to collapse of roof of karst, thermokarst or mining cavities, or due to water, oil or gas extraction. (NP-064-05)

CERTIFICATION OF MEASUREMENT METHODS (TECHNIQUES) (Аттестация методик (методов) измерений) – investigation and confirmation of compliance of measurement methods (techniques) with the established metrological requirements. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

certification of type of standard specimenS or instruments (Утверждение типа стандартных образцов или типа средств измерений) – properly documented decision about recognition of compliance of standard specimen type or instrument type to metrological and technical requirements (characteristics) based on results of tests of standard specimens or instrument for the purpose of type certification. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

check valve (Клапан обратный) – see VALVES (АРМАТУРА).

CLOSING BODY (Запорный ОРГАН) – a part of valve shutter, normally movable and connected to the valve actuator, enabling in interaction with the valve seat to control (cut off, isolate, distribute, mix, etc.) the flow(s) of fluids by means of changing the flow cross section. (NP-068-05)

CLOSURE OF RADIOACTIVE WASTE DISPOSAL SITE (Закрытие пункта захоронения радиоактивных отходов) – activities aimed at bringing the radioactive waste disposal site to the state ensuring safety of public and environment for the period of potential hazard caused by the radioactive wastes located therein after completion of placement of the radioactive wastes. (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 “Closure” (Закрытие).

COLLECTION OF RADIOACTIVE WASTES (Сбор радиоактивных отходов) – accumulation of RW in the specially allocated and equipped locations. (NP-058-04, NP-002-04)

COMMISSIONING (ВВОД В ЭКСПЛУАТАЦИЮ) – a process, during which systems and components of a nuclear power unit or nuclear power plant as a whole start functioning and undergo tests for consistency with design, including pre-startup adjustments, initial criticality, connection to the grid, trial operation, and finalized by acceptance into commercial operation. (OPB-12)

Comment

This term is fully equivalent to the same term in the IAEA Glossary. The latter, however, does not define stages of commissioning.

Commissioning of instrumentation (Ввод в эксплуатацию средства измерений) – properly documented readiness of instrumentation for intended use. (Federal Law No.102-FZ “On ensuring unification of measurements”)

common use territories (Территории общего пользования) – territories, used by unlimited number of individuals without restrictions (including squares, streets, drives, embankments, shores of common use water bodies, parks, boulevards). (“Town Building Code of the Russian Federation” No. 190-FZ)

comparison OF REFERENCE STANDARDS of units (Сличение эталонов единиц величин) – set of operations establishing relation between the units represented by reference standards of the same accuracy class in identical conditions. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

COMPENSATORY MEASURES (МЕРЫ компенсирующие) – technical and organizational measures aimed at partial or complete exclusion and (or) limitation of influence of safety deficit. (NP-017-2000, NP-024-2000)

complicated environmental conditions (СЛОЖНЫЕ ПРИРОДНЫЕ УСЛОВИЯ) – presence of grounds of specific state or composition and (or) risk of hazardous natural processes and phenomena and (or) technogenic impacts on the territory where construction, maintenance, and operation of building or structure is to be performed. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

COMPONENTS OF A NUCLEAR PLANT (ЭЛЕМЕНТЫ АС) – equipment, instrumentation, pipelines, cables, structural elements and other products enabling performance of intended functions on their own or within systems and viewed in the design as structural units of reliability and safety analysis. (OPB-12)

Comment

Also see the terms “Active system (component)”, “Passive system (component)”, “Independent systems (components)", “Safety systems (components)”, “Systems (components), important for safety”.

COMPOUND (КОМПАУНД) – matrix material with RW included into it. (NP-019-2000)

CONCAVITY (Вогнутость)

Angular weld concavity (Вогнутость углового шва) – maximum distance from the weld surface to the line connecting the edges of its surface in one cross-section (assessed by the maximum depth of location of the weld surface under the aforementioned line). (PNAE G-7-010-89).

Weld root concavity (Вогнутость корня шва) – a depression on the surface of a welded joint with single-sided weld at the location of its root (assessed by the maximum depth of location of the root surface counted from the surface level of the welded components). (PNAE G-7-010-89)

CONFIRMATORY measurements (Подтверждающие измерения)¹⁰ – measurements, results of which are used for confirming all or part of accounting data for accounting unit or nm batch. (NP-030-12)

confirmatory measurements (Подтверждающие измерения)¹¹ – measurements, results of which are used for confirming all or part of accounting data for radioactive substance or RW. (NP-067-11)

CONNECTION OF POWER UNIT TO THE GRID (ЭНЕРГЕТИЧЕСКИЙ ПУСК БЛОКА АС) – see POWER UNIT STARTUP (ПУСК БЛОКА АС).

connector (Разъем) – component for connecting or disconnecting electric cables. (NP-086-12)

connector (соединительное устройство) – see COUPLING BAR (Соединительное звено).

CONSERVATIVE APPROACH (КОНСЕРВАТИВНЫЙ ПОДХОД) – approach to design and engineering, under which values of the parameters of the unit are assumed so as to intentionally provide more unfavorable results. (OPB-12, RB-022-01)

conserved radioactive waste storage facility (хранилище радиоактивных отходов Законсервированное) – storage facility, placement of RW in which is over, and a complex of measures to bring it to the state ensuring safe long-term storage of RW and storage facility monitoring for the entire period of conservation is implemented. (NP-067-11)

construction (Строительство) – creation of buildings, structures and installation (inclusively in the place of demolished capital construction objects). (“Town Building Code of the Russian Federation” No. 190-FZ)

Comment

A corresponding term in the IAEA Glossary is “Construction” (Строительство).

CONSTRUCTION SITE (ПЛОЩАДКА СТРОИТЕЛЬСТВА) – territory within the selected limits, on which main and auxiliary buildings and structures of the plant are located. The site includes the territory within the fence perimeter (industrial site) and territory beyond the perimeter, where the switchgear, outer waterworks, cooling ponds, cooling towers, inlet and outlet flumes, processing systems, waste disposal sites, construction base, transshipment base, residential area, etc. (SP PNAE-87)

CONTAMINATION (ЗАГРЯЗНЕНИЕ)

Non-removable surface contamination of (Неснимаемое загрязнение поверхности) – radioactive substances that are not transferred to other objects during contact and cannot be removed during decontamination. (Refined definition of NRB-99/2009, PRB AS-99, NP-053-04)

Removable contamination of a surface (Снимаемое загрязнение поверхности) – radioactive substances that are transferred to other objects during contact and can be removed during decontamination. (Refined definition of NRB-99/2009, PRB AS-99, NP-053-04)

CONTROL (КОНТРОЛЬ) – a part of control function aimed at assessing the value of parameter (identifying) or determining the state of controlled process or equipment. (NP-026-04)

Comment

A corresponding term in the IAEA Glossary is “Control” (Контроль). However, in English the meaning of this term is broader and often means the equivalent of the Russian term “Управление” (Control).

control and protection system (Система управления и защиты) – combination of hardware, software and information support intended to ensure safety of nuclear fusion chain reaction. (NP-082-07)

Comment

A corresponding term in the IAEA Glossary is “Protection system” (Система защиты).

control and protection system actuator (Рабочий орган СУЗ) – means of reactivity control used in the control and protection system. (NP-082-07)

control overlay (наплавка Контрольная) – welding overlay performed with the use of control welding (surfacing) materials in order to test the properties of weld deposited material in the process of testing of welding (surfacing) materials. (PNAE G-7-010-89)

control rod group (Группа рабочих органов СУЗ) – one or several control rods with common controls, moved simultaneously in order to change reactivity. (NP-082-07)

CONTROL SAFETY SYSTEMS (COMPONENTS) (УПРАВЛЯЮЩИЕ СИСТЕМЫ (ЭЛЕМЕНТЫ) БЕЗОПАСНОСТИ) – see SAFETY SYSTEMS (COMPONENTS) (СИСТЕМЫ (ЭЛЕМЕНТЫ) БЕЗОПАСНОСТИ).

CONTROL SYSTEM (СИСТЕМА УПРАВЛЕНИЯ) – system consisting of a combination of object of control and controlling system. (NP-026-04)

control weld (сварной шов Контрольный) – a weld of a joint welded with the tested welding materials in order to check the properties of the metal of the joint in the process of testing of the welding materials. (PNAE G-7-010-89)

control welded joint (сварное соединение Контрольное) – a welded joint made during manufacturing process qualification in order to make sure that the welding technology undergoing certification provides the required characteristics of the weld metal. (PNAE G-7-010-89)

Manufacturing control welded joint (сварное соединение производственное контрольное) – a welded joint made for the purpose of verification of compliance of the metal properties of the manufacturing welded joint with the established requirements. (PNAE G-7-010-89)

CONTROLLING SYSTEM (УПРАВЛЯЮЩАЯ СИСТЕМА) – part of control system, controlling the object based on preset targets, criteria and limitations. (NP-026-04)

convexity (Выпуклость)

Angular weld convexity (выпуклость углового шва) – a part of an angular weld protruding over the line connecting the edges of its surface in one cross-section (assessed by the maximum height of location of the weld surface under the aforementioned line). (PNAE G-7-010-89)

Convexity (excessive penetration) of weld root (выпуклость (превышение проплавления) корня шва) – a part of single-sided weld on the side of its root protruding over the level of the welded components (assessed as maximum height of the root surface over the component’s surface). (PNAE G-7-010-89)

Convexity (excessive penetration) of abutting weld (выпуклость стыкового шва) – a part of a butt-end weld protruding over the level of the welded components (assessed as maximum height of the weld surface over the surface specified above). (PNAE G-7-010-89)

core (Активная зона) – part of the nuclear reactor, in which nuclear fuel, moderator, absorber, coolant, means of reactivity control and structural elements designed for realizing controlled chain nuclear fission reaction and transferring the energy to coolant are located. (NP-082-07, NP-080-07)

CORRECTIVE MEASURES (МЕРЫ корректирующие) – measures to eliminate identified non-compliances and prevent their recurrence. (NP-011-99)

COUPLING BAR (Соединительное звено) – components of actuator (executive mechanism), connecting movable parts with the reactivity control rod. (Refined definition of NP-086-12)

cps drive (Привод СУЗ) – a component designed for changing location of the control and protection system actuator and for maintaining its fixed position. (NP-082-07)

CPS ROD POSITION INDICATOR (Указатель положения рабочего органа СУЗ) – device for determining the position of control and protection system actuator (control rod) in the reactor core. (NP-082-07)

cracks (Трещины) – defects in the form of rupture of metal of welded joint or overlaid component (item). (PNAE G-7-010-89)

crash of aircraft or other missiles (Падение летательного аппарата и других летящих предметов) – technogenic factor characterized by a combination of load parameters (mechanical, fire, heat) on the territory of a nuclear facility, buildings, structures, systems, components, occurring due to crash of an aircraft or its fragments in case of flight accidents, or caused by missiles (fragments of structures, buildings or transportation vehicles) moved by excess pressure or shockwave occurring during explosions, high winds, hurricanes or tornadoes. (NP-064-05)

CRITERIA OF ACCEPTANCE OF RADIOACTIVE WASTES FOR DISPOSAL (Критерии приемлемости радиоактивных отходов для захоронения) – characteristics of RW that the wastes have to meet after collection, reprocessing, storage and conditioning. (NP-058-04, NP-072-06, Federal Law No. 190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

critical group (Группа критическая) – group of representatives of general public (at least 10 individuals) homogeneous in terms of one or several attributes – sex, age, social or professional conditions, location of residence, or diet – which is exposed to largest radiation exposure for a given exposure route from a given radiation source. (NRB-99/2009, PRB AS-99)

cryosolic (CRYOGENIC) geological processes (Мерзлотно-геологические (криогенные) процессы) – processes characterized by frost crack formation and frost buckling occurring under periodic freezing and thawing of soils. (NP-064-05)

cumulative operation (Наработка) – duration or scope of operation of a machine and (or) equipment. (Technical Specifications on safety of machinery and equipment)

CURRENT STATE OF FULL SCOPE SIMULATOR (ТЕКУЩЕЕ СОСТОЯНИЕ ПМТ) – values of parameters and states of modeling systems and components of the plant, determining the state of full scope simulator at present time. (NP-003-97)

cutset, minimum (сечение Минимальное) – see MINIMUM CUTSET (МИНИМАЛЬНОЕ СЕЧЕНИЕ).

DATA (ДАННЫЕ)

Generic data (обобщенные данные) – information on the IE frequencies and equipment reliability parameters obtained from the sources not directly related to the analyzed unit (plant). (RB-024-11)

Specific data (специфические данные) – information on the IE frequencies and equipment reliability parameters obtained from the sources directly related to the analyzed unit (plant). (RB-024-11)

DATA BASE (БАЗА ДАННЫХ) – combination of design, experimental and analytical data on the prototype reactor unit used for creation and operation of nuclear plant full scope simulator. (NP-003-97)

Nuclear plant decommissioning database (база данных по выводу из эксплуатации блока АС) – a set of documentally confirmed and ordered information about plant operation, engineering and radiological surveys, results of analysis, design information required for planning and performing nuclear plant decommissioning, as well as about results of activities performed at each stage of decommissioning.(NP-012-99)

DECOMMISSIONING OF A NUCLEAR POWER UNIT (ВЫВОД БЛОКА АС ИЗ ЭКСПЛУАТАЦИИ) – implementation of a set of measures after removal of nuclear fuel precluding the use of the nuclear power unit as a source of energy and ensuring safety of personnel, public and environment. (OPB-12, NP-012-99)

Comment

A corresponding term in the IAEA Glossary is “Decommissioning” (Вывод из эксплуатации). However, the latter is defined with respect to a nuclear facility, and contains an objective of providing possibility for cancellation of some or all the regulatory controls.

DECLARATION (ДЕКЛАРАЦИЯ)

Declaration of safety of a hydraulic engineering facility (декларация безопасности гидротехнического сооружения) – a document justifying safety of a hydraulic engineering facility and defining measures to ensure its safety taking into account the facility class. (Federal Law No. 117-FZ “On safety of hydraulic engineering facilities")

Fire safety declaration (декларация пожарной безопасности) – compliance assessment form, containing information about fire safety measures intended to maintain the fire risk at the protected facility within the prescribed limits. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

decommissioning of radioactive waste storage facility (Вывод из эксплуатации пункта хранения радиоактивных отходов) – activities performed after removal of radioactive wastes from the storage facility aimed at bringing it to the state precluding its further use as a radioactive waste storage facility and ensuring safety of public and environment. (Federal Law No.190-FZ “On radioactive waste handling and amendments to some legislative acts of the Russian Federation”)

Comment

In the IAEA standards, the term “Decommissioning” (Вывод из эксплуатации) is not used with respect to storage and disposal facilities. The IAEA standards use the term “Closure” (Закрытие).

decontamination (Дезактивация) – removal of radioactive contamination from a surface or media, or decrease of such contamination. (NRB-99/2009, PRB AS-99)

Comment

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

deflagration (Дефлаграция ) – explosion of hydrogen-containing mixture within a limited volume when the reaction edge propagates at subsonic velocity creating moderate pressure and thermal loads (explosive combustion). (NP-040-02)

degree of fire resistance of buildings, structures and fire compartments (Степень огнестойкости зданий, сооружений, строений и пожарных отсеков) – classifier of buildings, structures or fire compartments determined by fire resistance limits of structural elements of these buildings, structures or compartments. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”, “Code of rules. Nuclear power stations. Fire safety requirements”. SP 13.13130.2009)

delamination (отслоение) – defect in the form of violation of continuity of fusion of welded overlay metal with the main metal on components (products) with anti-corrosion welding surfacing or with pre-welded edges, or on other surfaced or overlaid components. (PNAE G-7-010-89)

DEPENDENT FAILURE (ЗАВИСИМЫЙ ОТКАЗ) – see FAILURES (ОТКАЗЫ).

depleted uranium (Обедненный уран) – see URANIUM (УРАН).

DESIGN BASES (Проектные основы) – set of input data about the required parameters and characteristics of a nuclear facility, its systems, components, buildings, structures, including information about operation conditions, operating modes and their parameters, postulated external events required for designing the facility, manufacturing its equipment, systems and components, installation and adjustment, construction of the facility, and for ensuring its normal operation for the assigned lifetime and decommissioning. (NP-064-05, RB-006-98)

Comment

A corresponding term in the IAEA Glossary is “Design basis ” (Проектные основы).

design BASIS accidenT (проектная авария) – see ACCIDENT.

DESIGN BASIS EARTHQUAKE (ПРОЕКТНОЕ ЗЕМЛЕТРЯСЕНИЕ) – see EARTHQUAKE (ЗЕМЛЕТРЯСЕНИЕ).

DESIGN LIMITS (ПРОЕКТНЫЕ ПРЕДЕЛЫ) – values of parameters and characteristics of the state of plant systems (components) and plant as a whole, established in the design for normal operation, and abnormal operation including pre-accident states and accidents. (OPB-12, NP-003-97)

Comment

There is no such a term in the IAEA Glossary. However, the IAEA standard SSR-2/1 dedicated to nuclear plant design there is a requirement with the same title, fully consistent with the Russian definition.

Maximum design limit of fuel element damage (Максимальный проектный предел повреждения твэлов) – allowable values of parameters and characteristics of fuel elements under design basis accident conditions, exceeding which can result in critical damage (destruction) of fuel elements. (NP-082-07)

Operating limits (Эксплуатационные пределы) – values of parameters and characteristics of the state of systems (components) and of the plant as a whole, established by the design for normal operation. (OPB-12)

Plant safe operation limits (Пределы безопасной эксплуатации АС) – the values of process parameters established by the design, deviation from which can result in an accident. (OPB-12, NP-003-97, PRB AS-99)

designer (проектировщик) – legal entity or individual entrepreneur developing design documentation for machinery and (or) equipment. (Technical Specifications on safety of machinery and equipment)

System designer (Проектировщик системы) – a company or an individual entrepreneur developing design documents for systems of machinery and (or) equipment (process lines interconnected through production cycle). (Technical Specifications on safety of machinery and equipment)

designer organization (Организация-разработчик) – organization, developing design and/or architecture of nuclear facility systems, equipment, or individual assembly units and components of pipelines. (PNAE G-7-008)

DESIGNER’S SUPERVISION (АВТОРСКИЙ НАДЗОР) – supervision by the author of design documentation over compliance with the requirements of design documentation during construction. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

DETECTOR RESPONSE (ОТКЛИК ДЕТЕКТОРА) – characteristic of irradiated detector (e.g. number of reactions over the irradiation time, or average rate of neutron-induced reaction over the irradiation time), functionally dependent on the characteristics of neutron field. (RB-018-01)

DETERMINISTIC APPROACH (Детерминистический подход ) – approach to design or engineering based on fully determined data on the parameters of impact and properties of the object with safety margins and non-exceedence of pre-determined standards with margin coefficients of the limiting values of the controlled parameters. (NP-064-05)

DETERMINISTIC EFFECTS OF IRRADIATION (детерминированные Эффекты облучения) – see RADIATION EXPOSURE EFFECTS (ЭФФЕКТЫ ОБЛУЧЕНИЯ)

DETERMINISTIC SAFETY ANALYSIS (ДЕТЕРМИНИСТИЧЕСКИЙ АНАЛИЗ безопасности) – see ANALYSIS (АНАЛИЗ)

DETONATION (Детонация) – explosion of hydrogen-containing mixture within a limited volume when the reaction edge propagates at ultrasonic velocity creating high pressure and high velocity head. (NP-040-02)

developer (Застройщик) – an individual or a legal entity performing on the land he/she/it owns construction, renovation, overhaul of capital structures, as well as performing engineering surveys, preparation of design documentation for construction, renovation or overhaul. (“Town Building Code of the Russian Federation” No. 190-FZ)

DEVIATION FROM NORMAL OPERATION OF A NUCLEAR PLANT (НАРУШЕНИЕ НОРМАЛЬНОЙ ЭКСПЛУАТАЦИИ АС) – a violation in operation of the plant associated with deviation from established operating limits and conditions. Other design limits and conditions can also be violated, including safe operation limits and conditions. (OPB-12, NP-031-01, NP-003-97)

Comment

In the IAEA Glossary there is a similar term ‘Abnormal operation’ (не нормальная эксплуатация), but such a state does not exist on the chart of the plant operating states. In the text defining the term ‘Anticipated operational occurrence’ (ожидаемое при эксплуатации событие), which defines a state existing on the operational chart it is mentioned that some countries identify “abnormal operation” with this state. In the Russian regulatory practice, the term “Deviation from normal operation" is associated with any state of the plant differing from normal operation.

DEVICE (SOURCE) GENERATING IONIZING RADIATION (Устройство (источник), генерирующее ионизирующее излучение) – electrophysical device (X-ray unit, accelerator, generator, etc.), in which ionizing radiation occurs due to change of velocity of charged particles, their annihilation or nuclear reactions. (NRB-99/2009)

DIAGNOSTIC SYSTEMS (СИСТЕМЫ ДИАГНОСТИКИ) – systems designed for obtaining, as a rule, continuously, information about the status of metal of equipment and pipelines, usually operating based on different physical principles of monitoring and testing (neutron, acoustic, vibration diagnostics, tensothermometry, etc.). (PNAE G-7-008)

DIAGNOSTICS (Диагностика) – a monitoring function, the purpose of which is to determine the state of operability (inoperability) or faultlessness (failure) of the subject of diagnostics. (NP-082-07, NP-026-04)

direct measurement (Прямое измерение) – see MEASUREMENT (MEASUREMENTS) (ИЗМЕРЕНИЕ (ИЗМЕРЕНИЯ)).

discontinuity (Несплошность) – generic term for cracks, weld-throughs, scaling, leaks, pores, incomplete welds and inclusions. (PNAE G-7-010-89)

DISPOSAL (ЗАХОРОНЕНИЕ)

Liquid radioactive waste disposal (захоронение жидких радиоактивных отходов) – placement of LRW in deep reservoir beds at the depth of several hundred meters within the mining license boundaries by means of injection through boreholes without intention of their subsequent retrieval. (NP-058-04)

Near surface disposal of radioactive wastes (захоронение радиоактивных отходов приповерхностное) – RW disposal in the structures located on the ground surface or at the depth of several tens of meters. (NP-058-04)

Comment

A corresponding term in the IAEA Glossary is “Near surface disposal” (Приповерхностное захоронение).

Nuclear power unit disposal (захоронение блока АС) – a nuclear power unit decommissioning option with localization of highly radioactive components of equipment, systems and structures by means of creating additional physical barriers precluding unauthorized access to them. (NP-012-99)

Radioactive waste disposal (захоронение радиоактивных отходов) – safe placement of RW without intention of their subsequent retrieval. (NP-058-04, NRB-99/2009, 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 “Disposal” (Захоронение).

Radioactive waste disposal in deep geological formations (deep disposal) (захоронение радиоактивных отходов в глубокие геологические формации (захоронение глубокого заложения)) – RW disposal in the structures located at the depth of several hundred meters without intention of their subsequent retrieval. (NP-058-04)

Comment

A corresponding term in the IAEA Glossary is “Geological disposal” (Геологическое захоронение).

DIVERSITY PRINCIPLE (ПРИНЦИП РАЗНООБРАЗИЯ) – principle of reliability enhancement by means of using two or more systems or components of different design or action principles for performing the same safety function in order to decrease common cause failure probability. (OPB-12)

Comment

A corresponding term in the IAEA Glossary is “Diversity” (Разнообразие).

DOCUmented amount of nuclear material (Документально зарегистрированное количество ядерного материала) – the amount of nuclear material currently present in the MBA in the responsibility zone of an organization; this amount is determined based on the existing accounting data. (NP-030-120)

door (дверь) – a component of leaktight enclosure enabling entry of people and (or) transportation of the equipment across the structures enclosing the accident localization zone. (NP-010-11)

DOSE (Доза)

Absorbed dose (доза поглощенная) (D) – amount of energy of ionizing radiation transferred to substance

,

where ‘de’ is the average energy of ionizing radiation transferred to substance in an elementary volume, and ‘dm’ is the mass of substance in that volume.

The energy can be averaged over any definite volume, in this case the average dose will be equal to total energy received by the volume, divided by the mass of this volume¹². (NRB-99/2009, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Absorbed dose, D” (Поглощенная доза, D).

Dose per body organ or tissue (доза в органе или ткани) (d_t) – average absorbed dose in a certain body organ or tissue:

,

where ‘m_т’ is the mass of body organ or tissue, ‘D’ – absorbed dose in the mass element ‘dm’. (NRB-99/2009)

Comment

A corresponding term in the IAEA Glossary is “Organ dose” (Доза на орган)

Effective dose (доза эффективная) – magnitude of the effect of ionizing radiation used as a measure of risk of delayed consequences of radioactive exposure of human organism or its individual organs taking into account their sensitivity to radiation. It represents the integral sum of equivalent dose in organs and tissues multiplied by corresponding weighing factors:

where ‘H_T’is the equivalent dose per tissue or organ ‘Т’; ‘W_T’ – weighing factor for the tissue or organ Т.¹³ (NRB-99/2009, Federal Law No. 3-FZ “On nuclear safety of general population”, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Effective dose, E” (Эффективная доза, E).

Effective yearly dose (доза эффективная годовая) – the sum of the effective external exposure dose over a calendar year and committed effective dose of internal exposure due to intake of radionuclides over the same year¹⁴. (NRB-99/2009, PRB AS-99)

Effective collective dose (доза эффективная коллективная) – a measure of collective risk of occurrence of stochastic effects of radiation exposure equal to the sum of individual effective doses¹⁵. (NRB-99/2009)

Comment

A corresponding term in the IAEA Glossary is “Collective effective dose, S” (Коллективная эффективная доза, S).

Equivalent dose (доза эквивалентная) (h_t,r) – a dose absorbed by a body organ or tissue multiplied by an appropriate weighing factor for this type of radiation ¹⁶, W_R:

,

where ‘D_T,R’ is the average absorbed dose in the organ or tissue ‘Т’; ‘W_R’ – weighing factor for radiation ‘R’. In case of combined action of several types of radiation with different weighing factors the equivalent dose is defined as a sum of equivalent doses for these types of radiation:

(NRB-99/2009, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Equivalent dose, HT” (Эквивалентная доза, HT).

Equivalent dose (h_t (tau)) or effective dose (e (tau)) committed for internal exposure (доза эквивалентная (h_t (тau)) или эффективная (e (тau)), ожидаемая при внутреннем облучении) – dose over a period ‘tau’ after intake of radioactive substances by the organism:

where ‘t₀’ is the time of intake; ‘H_T (t)’ is the equivalent dose rate by the time moment ‘t’ in the organ or tissue ‘Т’. When ‘tau’ is not defined, it should be assumed equal to 50 years for adults and (70 - t₀) for children. (NRB-99/2009)

Comment

There are two corresponding terms in the IAEA Glossary:” Committed equivalent dose, HT(τ)” (Ожидаемая эквивалентная доза, HT(τ)), and “Committed effective dose, E(τ)” (Ожидаемая эффективная доза, E(τ)).

Equivalent yearly dose (доза эквивалентная годовая) – the sum of equivalent doses of external radiation received over a calendar year and anticipated equivalent absorbed dose associated with intake of radionuclides for the same year¹⁷. (NRB-99/2009, PRB AS-99)

Preventable dose (доза предотвращаемая) – predicted dose due to a radiation accident that could be prevented by protective measures. (NRB-99/2009)

DOSE LIMIT (Предел дозы (ПД)) – value of effective or equivalent dose of technogenic exposure of public and personnel due to normal operation of a radiation facility, which is not to be exceeded. Compliance with the annual dose limits precludes deterministic effects and probability of stochastic effects is maintained at acceptable level. (NRB-99/2009, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Dose limit” (Предел дозы).

dose rate (Мощность дозы) – radiation dose per unit of time (second, minute, hour). (NRB-99/2009, PRB AS-99)

Comment

A corresponding term in the IAEA Glossary is “Dose rate” (Мощность дозы).

DOSE REGULATION PRINCIPLE (ПРИНЦИП нормирования) – non-exceedance of allowable limits of individual exposure dose for public from all sources of ionizing radiation. (Federal Law No. 3-FZ “On radiation safety of public”)

Comment

A corresponding term in the IAEA Glossary is “Dose constraint” (Ограничение доз).

DRAINAGE WATER (ДРЕНАЖНЫЕ ВОДЫ) – water removed by drainage facilities designed for diverting drainage water into water bodies. (“The Water Code of the Russian Federation” No. 74-FZ)

drive (Привод) – a component designed for moving the locking or regulating element, or for creating force to ensure proper leaktightness of the lock. Depending on the type of consumed energy, a drive can be electrical (with electric motor or electric magnet), hydraulic, or pneumatic; depending on its location with respect to the valve it can be in-built or remote. (NP-068-05)

DRY SNF STORAGE FACILITY (ПУНКТ сухого хранения ОЯТ) – stationary object (structure) designed for SNF storage, in which heat is removed from SNF by air. (NP-035-02)

dry storage of spent nuclear fuel (Сухое хранилище отработавшего ядерного топлива) – storage facility intended for storing SNF in gaseous environment (air or noble gas). (NP-061-05)

Comment

A corresponding term in the IAEA Glossary is “Dry storage facility” (Сухое хранилище)

duration of seismic oscillations (Продолжительность сейсмических колебаний) – time, during which the amplitude of oscillations exceeds background oscillations by more than 10%. (RB-006-98)

dynamic characteristics (характеристики Динамические) – free oscillation frequencies, shapes and decay parameters. (RB-045-08)

DYNAMIC METHOD OF ANALYSIS (МЕТОД анализа динамический) – method of analysis of impacts in the form of accelerograms of ground oscillations at the base of a building by means of numeric integration of mechanical equations. (NP-031-01)

EARTHQUAKE (ЗЕМЛЕТРЯСЕНИЕ) – subsurface shocks and oscillations of the earth surface caused by pulse-wise displacements and ruptures in the earth crust. (NP-064-05)

Design basis earthquake (DBE, SL1) (Проектное землетрясение) – an earthquake of maximum intensity on the plant site with the recurrence rate of once in 1000 years. (NP-031-01, RB-019-01, RB-006-98)

Comment

This term corresponds to the IAEA Glossary term “Design Basis Earthquake” (проектное землетрясение) of SL-2 level. (However, the IAEA Glossary does not explicitly refer to the recurrence level of SL-1 earthquakes; it does specify that in some countries SL-1 corresponds to the probability of 10-2 1/year. At the same time, the recurrence rate of once in 1000 years as per the Russian regulatory documents is equivalent to probability of 10-3 1/year.

Local earthquake (землетрясение локальное) – an earthquake, the focus of which is located in the vicinity of the nuclear facility site (within a radius of less than 30 km). (RB-019-01)

Proximal earthquake (землетрясение местное) – an earthquake, the focus of which is located in the radius of 30 to 300 kilometers from the nuclear facility site. (RB-019-01)

Remote earthquake (землетрясение удаленное) – an earthquake, the focus of which is located more than 300 kilometers away from the nuclear facility site. (RB-019-01)

Safe shutdown earthquake (Maximum rated earthquake, SL2) (Максимальное расчетное землетрясение) – an earthquake of maximum intensity on the plant site with the recurrence rate of once in 10 000 years. (NP-031-01, RB-019-01, RB-006-98)

Comment

This term corresponds to the IAEA Glossary term “Design Basis Earthquake” (проектное землетрясение) of SL-2 level. (However, the IAEA Glossary does not explicitly refer to the recurrence of SL-2 earthquakes; it does specify that in some countries SL-2 corresponds to the probability of 10-4 1/year. This probability is equivalent to the recurrence rate of once in 10000 years that is specified in the Russian regulatory documents).

EARTHQUAKE RECURRENCE LAW (ЗАКОН ПОВТОРЯЕМОСТИ ЗЕМЛЕТРЯСЕНИЙ) – linear dependence of logarithm of the number of earthquakes in a given region over a given period of time upon the earthquake magnitude. (RB-019-01)

EFFLUENT (сброс)

Allowable effluent (Допустимый сброс) – a prescribed limit for yearly release of radionuclides with waste water into environment allowable for a nuclear facility taking into account optimization principle. (NP-058-04)

Comment

IAEA Glossary contains a broader term “Authorized discharge” (Разрешенный сброс (выброс)) referring to both liquid effluents and gaseous releases.

Allowable effluent of radioactive substances (допустимый сброс радиоактивных веществ) – prescribed maximum activity of nuclides released from the plant to the environment with waste water over a year. (PRB AS-99)

Corrosive effluents into surface and ground water (Коррозионные жидкие сбросы в поверхностные и грунтовые воды) – effluents of pollutants into water bodies in the amounts degrading composition and properties of water, causing corrosive impact on underground networks and structures. (NP-064-05)

Maximum allowable effluent (Предельно допустимый сброс) – the prescribed limit for release of radionuclides into environment with waste water over a year, calculated based on the quota for liquid radioactive discharges of the nuclear facility. (NP-058-04)

electromagnetic pulses (Импульсы электромагнитные) – pulses consisting of powerful short-term radiation from the electromagnetic field source. (NP-064-05)

electromagnetic radiation (излучение электромагнитное) – process of formation of free electromagnetic field. (NP-064-05)

EMERGENCY EXIT (АВАРИЙНЫЙ ВЫХОД) – a door, hatchway or other exit towards evacuation route, leading immediately outside or to a safe area. It is used as an additional rescue exit, but is not accounted for in assessment of the required number and dimensions of evacuation routes and evacuation exits, and it is to be compliant with the requirements of safe evacuation in case of fire. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements)

EMERGENCY LIGHTING (АВАРИЙНОЕ ОСВЕЩЕНИЕ) – lighting on the evacuation routes with autonomous power supply operable in case of fire, accident and other emergencies, actuated automatically by appropriate alarms or manually if there is no alarm or the alarm signal failed. (Federal Law No. 384-FZ “Technical Specifications on safety of buildings and structures”)

EMERGENCY POWER SUPPLY BUSBAR OF HIGHEST NOMINAL VOLTAGE (Секции системы аварийного электроснабжения наибольшего номинального напряжения) – busbars with the largest design value of nominal voltage among AC emergency power supply busbars designed to supply power to the components of the second group in the given train of the emergency power supply system. (NP-087-11)

EMERGENCY POWER SUPPLY SYSTEM (Система аварийного электроснабжения) – support safety system consisting of a set of autonomous sources, transforming, switching and distributing components providing electric power supply in all states of the unit (including accidents and loss of off-site power). (NP-087-11)

emergency power supply system consumers (Потребители системы аварийного электроснабжения)

Emergency power supply system consumers of the first category (Потребители системы аварийного электроснабжения первой группы) – AC and DC consumers of emergency power supply system not admitting (from the nuclear plant safety consideration) power interrupts longer than the time of operation of automatic switches during normal operation of the plant or deviations from normal operation, including accidents and station blackout events. (NP-087-11)

Emergency power supply system consumers of the second category (Потребители системы аварийного электроснабжения второй группы) – AC consumers of emergency power supply system admitting power interrupts during transition to autonomous power supply sources for the duration of startup of the source, which is justified based on the nuclear plant safety considerations. (NP-087-11)

EMERGENCY PREPAREDNESS LEVEL (УРОВЕНЬ АВАРИЙНОЙ ГОТОВНОСТИ) – established degree of preparedness of plant personnel, operating utility, organizations of the national system for prevention and mitigation of emergency situations, other participants of emergency response and equipment and hardware used for protection of personnel and public in case of an accident at a nuclear plant. (OPB-12)

emergency protection (scram) signal (Сигнал AЗ) – signal generated by the emergency protection instrumentation and controls in order to induce operation of the reactor control rods; this signal goes into the recording systems, as well as to the main control room and auxiliary control room for personnel notification. (NP-082-07)

emergency protection of technical and engineering support systems (ПРОТИВОАВАРИЙНАЯ ЗАЩИТА СИСТЕМ ИНЖЕНЕРНО-ТЕХНИЧЕСКОГО ОБЕСПЕЧЕНИЯ) – set of components providing protection, prevention and (or) mitigation of harmful consequences of accidents during operation of technical support systems and increasing the lifetime (life) of such systems.

emergency protection system actuator (Рабочий орган AЗ) – means of reactivity control used in the emergency protection system. (NP-082-07)

EMERGENCY RELEASE DISTRIBUTION (Распределение аварийных выбросов) – dependence, presented in the following form: probability vs release source term. (RB-044-09)

EMERGENCY SITUATION (ЧРЕЗВЫЧАЙНАЯ СИТУАЦИЯ) – situation on certain territory caused by an accident, hazardous natural phenomenon, catastrophe or disaster, which can cause or have caused casualties, damage to health of people and to environment, significant material losses and degradation of living conditions of people. (Refined definition of the Federal law “On protection of public and territories against natural or technogenic emergency situations” No. 68-FZ)

EMISSION (ВЫБРОС) – release of a substance (mixture of substances in gaseous and (or) aerosol form into environment (atmosphere) from the emission source. (NP-021-2000)

Comment

The IAEA Glossary contains the term "Discharge” combining the two Russian terms – “Emission” (выброс) and “Effluent” (сброс).

Allowable emission (Допустимый выброс) – a limit of allowed yearly release of radionuclides into atmosphere established for the nuclear facility taking into account optimization principle. (NP-058-04)

Allowable emission of radioactive substances (Допустимый выброс радиоактивных веществ) – prescribed maximum activity of the nuclides released from the plant into atmosphere over a year. (PRB AS-99)

Emergency emission (Аварийный выброс) – release of radioactive materials and/or ionizing radiation into environment in the amounts exceeding the established safe operation limits. (RB-044-09)

Large emergency release (Большой аварийный выброс) – emergency emission of radioactive substances into environment during a severe beyond design accident requiring implementation of protective measures on the boundary of the zone of planning of protective measures established according to the siting requirements and standards and beyond these boundaries. (OPB-12)

Maximum allowable emission (Предельно допустимый выброс) – the standard value of the amount of radionuclides realeased from the nuclear facility into atmosphere over a year; this value is calculated based on the established emission quota for the nuclear facility. (NP-058-04)

Release of explosive, flammable, toxic vapors, gases and aerosols into atmosphere (Выброс взрывоопасных, воспламеняющихся, токсичных паров, газов и аэрозолей в атмосферу) – release into atmosphere of harmful substances (pollutants) in the amount and concentrations that change composition and properties of significant volumes of air masses and negatively affect people and environmental objects. (NP-064-05)

EMPLOYEE (РАБОТНИК) – an individual, temporarily or permanently working directly with sources of ionizing radiation. (Federal Law No. 3-FZ “On radiation safety of public”)

END STATE (СОСТОЯНИЕ КОНЕЧНОЕ) – stationary controlled state of plant systems and components after accident. (OPB-12)

Safe end state (состояние конечное безопасное) – stable state of the unit, in which the design limits for accidents are not exceeded. (RB-024-11)

Successful end state (состояние конечное успешное) – same as SAFE END STATE (СОСТОЯНИЕ КОНЕЧНОЕ БЕЗОПАСНОЕ). (RB-032-04)

Unsafe end state (состояние конечное небезопасное)) – state of the unit, characterized by design limits for accidents being exceeded. (RB-024-11)

Unsuccessful end state (состояние конечное неуспешное) – same as UNSAFE END STATE (СОСТОЯНИЕ КОНЕЧНОЕ НЕБЕЗОПАСНОЕ). (RB-032-04)

END STATE OF POWER UNIT AFTER DECOMMISSIONING (СОСТОЯНИЕ КОНЕЧНОЕ БЛОКА АС ПОСЛЕ ВЫВОДА ИЗ ЭКСПЛУАТАЦИИ) – state of nuclear power unit specified by decommissioning program to be achieved after completion of all decommissioning activities (NP-012-99)

endogenous phenomena, gravity-slope (эндогенные явления гравитационно-склоновые) – phenomena consisting in sloughs, subsidence, rubble and rock avalanches, and mudflows, occurring in highly seismic areas (above 8) and active neotectonics on high mountain slopes, contributing to formation of unstable slopes. (NP-064-05)

engineered protection (ИНЖЕНЕРНАЯ ЗАЩИТА) – see PROTECTION (ЗАЩИТА).

ENGINEERED PROTECTION OF NUCLEAR FACILITY AGAINST EXTERNAL IMPACTS (ИНЖЕНЕРНАЯ ЗАЩИТА ОБЪЕКТА ИСПОЛЬЗОВАНИЯ АТОМНОЙ ЭНЕРГИИ ОТ ВНЕШНИХ ВОЗДЕЙСТВИЙ) – see PROTECTION (ЗАЩИТА).

ENGINEERED PROTECTION OF NUCLEAR FACILITY TERRITORY (ИНЖЕНЕРНАЯ ЗАЩИТА ТЕРРИТОРИИ ОБЪЕКТА ИСПОЛЬЗОВАНИЯ АТОМНОЙ ЭНЕРГИИ) – see PROTECTION (ЗАЩИТА).

Engineering survey (Инженерные изыскания) – investigation of natural conditions and factors of technogenic impacts in order to ensure rational and safe use of territories and land allotments, preparation of data for justification materials required for territorial planning, development, design and civil engineering activities. (“Town Building Code of the Russian Federation” No. 190-FZ)

engineering and technical support network (СЕТЬ ИНЖЕНЕРНО-ТЕХНИЧЕСКОГО ОБЕСПЕЧЕНИЯ) – set of pipelines, ducts and other structures designed for engineering and technical support of buildings and structures. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

engineering and technical support system (СИСТЕМА ИНЖЕНЕРНО-ТЕХНИЧЕСКОГО ОБЕСПЕЧЕНИЯ) – one of the systems of a building or structure, designed for performing functions of water supply, sewerage, heating, ventilation, air conditioning, gas supply, power supply, communication, information, dispatching, waste removal, vertical transportation (elevators, escalators), or a support safety function. Federal Law No. 384-FZ “Technical Specifications on safety of buildings and structures”)

enriched uranium (Обогащенный уран) – see URANIUM (УРАН).

ensuring nuclear facility safety under external impacts (Обеспечение безопасности объекта использования атомной энергии при внешних воздействиях) – a set of engineered and organizational measures at a nuclear facility designed for preventing violations of allowable limits and conditions of safe operation under external impacts. (NP-064-05)

ENVIRONMENTAL REVIEW (ЭКСПЕРТИЗА ЭКОЛОГИЧЕСКАЯ) – verification of consistency of the intended commercial or industrial activities with the environmental requirements defining allowability of realization of the subject of environmental review in order to preclude potential harmful effects of these activities upon environment, as well as social, economic and other consequences of realization of the subject of review associated with these effects. (Federal Law No. 174-FZ “On environmental review”)

environmental surveillance (Наблюдения за окружающей средой) – system of measures for determination of parameters characterizing the state of environment, its individual components, types of technogenic impact, and observation of natural physical, chemical and biological processes occurring in the environment. (RB-046-08)

epicenter (Эпицентр) – projection of hypocenter of earthquake up the earth surface, characterized by geographic coordinates. (RB-006-98)

epicentral distance (Расстояние ЭПИцентральное) – distance between epicenter and observation point. (RB-006-98)

EQUIPMENT (Оборудование) – vessels, operated under increased or volumetric pressure (hereafter – pressure), (including reactor vessels and their outer shells), steam generators, heat exchangers, tanks, bodies of valves, pumps and filters of a nuclear facility. (PNAE G-7-008)

Equipment (Оборудование) – hardware used separately or installed in a machine to perform its main and (or) auxiliary functions, or to integrate several machines into a unified complex. (Technical Specifications on safety of machinery and equipment)

equivalent depth of oxidation of cladding (степень окисления оболочки Эквивалентная) – total thickness of equivalent layer that would have reacted with steam assuming that all the locally absorbed oxygen was used up for formation of stoichiometric zirconium dioxide ZrO2 divided by the initial thickness of cladding. In case of loss of cladding integrity, oxidation of both outer and inner surfaces is to be taken into account. (NP-082-07)

EQUIVALENT EQUILIBRIUM VOLUMETRIC ACTIVITY (of radon isotope daughters) (эквивалентная равновесная объемная Активность (ЭРОА) (дочерних продуктов изотопов радона)) – see ACTIVITY (АКТИВНОСТЬ).

equivalent voltage (напряжение Эквивалентное) – power supply voltage in electric winding, providing at the temperature of 20°С the same current through the winding as can occur at higher (lower) temperature and minimum (maximum) allowable power supply voltage at this temperature. (NP-068-05)

erosion of banks, slopes, riverbeds (Размывы берегов, склонов, русел) – processes of deformations caused by of banks of rivers, ponds, sea or water reservoir shore lines in the surf zones with formation of terrace and littoral shelf, ablation, transfer and resedimentatoin of soil on the slopes and beds of rivers and ravines caused by surface water streams. (NP-064-05)

ERRONEOUS DECISION (ОШИБОЧНОЕ РЕШЕНИЕ) – incorrect performance or failure to perform a number of sequential correct actions due to incorrect assessment of the occurring processes. (OPB-12)

especially radiation-hazardous activities (Особо радиационно-опасные работы) – radiation-hazardous activities, during which the anticipated collective exposure doses exceed 0.5 man-Sv or 10 mSv of effective individual dose. (PRB AS-99)

EXPLOSION (Взрыв) – fast exothermal chemical transformation of explosive media accompanied by release of energy and generation of compressed gases capable of performing mechanical work. (NP-040-02)

Explosion at a facility (Взрыв на объекте) – explosion that occurred outside of a nuclear facility due to different reasons and sources, and that can result in external technogenic impact on the nuclear facility site or nuclear facility. (NP-064-05)

Explosion in the air (взрыв в воздушной среде) – a spatially localized process of rapid transition of the source energy (chemical, thermal, electrical, mechanical) into kinetic energy of the media in the form of pressure wave, oscillation of soil, missiles, and radiant heat. (RB G-05-039-96)

Explosion of clouds of gaseous and fuel-air mixtures, deflagrative (взрыв облаков газо- и топливновоздушных смесей дефлаграционный) – release of energy into the bulk of the cloud in the process of propagation of exothermal chemical reaction with subsonic velocity (deflagration). (RB G-05-039-96)

Explosion of clouds of gaseous and fuel-air mixtures, detonative (взрыв облаков газо- и топливновоздушных смесей детонационный) – release of energy into the bulk of the cloud in the process of propagation of exothermal chemical reaction with ultrasonic velocity. (RB G-05-039-96)

Explosion of drifting clouds (Взрыв облаков дрейфующих) – explosion caused by ignition of flammable gases leaking into atmospheric air in the form of clouds that, moving over substantial differences, can maintain flammable concentrations for long periods of time. (NP-064-05)

EVACUATION (ЭВАКУАЦИЯ)¹⁸ – process of organized self-maintained movement of people immediately outside or to a safe area from the rooms, in which hazardous factors of fire can affect people. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

Comment

A corresponding term in the IAEA Glossary is “Evacuation” (Эвакуация).

EVACUATION CONTROL AND NOTIFICATION HARDWARE (ТЕХНИЧЕСКИЕ СРЕДСТВА ОПОВЕЩЕНИЯ И УПРАВЛЕНИЯ ЭВАКУАЦИЕЙ) – set of hardware (annunciator controls, fire annunciators) designed for notifying people of fire. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

EVACUATION EXIT (ЭВАКУАЦИОННЫЙ ВЫХОД) – exit leading to the evacuation route immediately outside or to a safe area. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

EVACUATION ROUTE (ЭВАКУАЦИОННЫЙ ПУТЬ) – route for movement and (or) transportation of people leading immediately outside or to a safe area, consistent with the requirements to evacuation of people during fire. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

EVENT FREQUENCY (Частота события) – number of events per unit of time. (RB-024-11)

event tree (Дерево событий) – a graph representing the logics of accident development used for accident sequence modeling in PSA. (Refined definition from RB-024-11)

EVOLUTION OF RADIOACTIVE WASTE STORAGE FACILITY (ЭВОЛЮЦИЯ ХРАНИЛИЩА РАО) – logically justified and ordered in time, sequence of interrelated states of the storage facility assumed by it over the life cycle due to external events of natural and technogenic origin, including the initiators of accidents in the storage facility; personnel actions, including personnel errors; physical and chemical processes occurring in the storage facility. (RB-011-2000)

exclusive use (Исключительное использование) – use of a transportation vehicle or large cargo container by a single cargo shipper, when all the initial, intermediate and final cargo loading and unloading operations are performed by the cargo shipper or receiver, or under their directions. (NP-053-04)

executive mechanism of protection and control system (Исполнительный механизм СУЗ) – a mechanism consisting of a drive, effectors and structural elements, intended for changing reactivity of the reactor. (NP-082-07)

EXPLOSION AND FIRE HAZARD OF THE SUBJECT OF PROTECTION (ВЗРЫВОПОЖАРООПАСНОСТЬ ОБЪЕКТА ЗАЩИТЫ) – state of the subject of protection characterized by possibility of explosion and development of fire, or occurrence of fire with subsequent explosion. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

EXPLOSION HAZARD AREA (ВЗРЫВООПАСНАЯ ЗОНА) – same as FIRE HAZARD AREA (ПОЖАРООПАСНАЯ ЗОНА).

EXPLOSION RESISTANCE OF OBJECT (Взрывоустойчивость объекта) – ability of the object to perform its functions under mechanical impact of emergency explosion without breach of safety. (RB G-05-039-96)

EXPLOSIVE MIXTURE (ВЗРЫВООПАСНАЯ СМЕСЬ) – mixture of air or oxidizer with flammable gases, vapors of flammable liquids, flammable dust or fibers, capable of exploding at certain concentrations conditionally to occurrence of explosion initiation source. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

EXTENDED OPERATION PERIOD (СРОК дополнительный эксплуатации) – calendar duration (period) of operation of a unit on power above the assigned lifetime. (NP-017-2000)

EXTERNAL FACILITIES (НАРУЖНАЯ УСТАНОВКА) – complex of systems and process equipment located outside buildings or structures. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

external impact accounting (Учет внешних воздействий) – activities aimed to ensure stability and safety of a nuclear facility under external impacts at all stages of its life cycle associated with siting, design, operation and decommissioning taking into account external impacts at the nuclear facility site, the results of which are reflected in the design solutions, organizational and engineered measures. (NP-064-05)

EXTERNAL RESPONSE FORCES (Внешние силы реагирования) – forces deployed for rendering assistance in neutralizing the perpetrators during transportation of radioactive substances or radioactivity sources. (NP-073-11)

Comment

The IAEA Glossary contains a broader term – “Emergency response arrangements” (Мероприятия по аварийному реагированию).

Externally originated fire (Пожар по внешним причинам) – fire originated beyond nuclear facility site for different reasons, which can result in external technogenic impact on site or upon the facility itself. (NP-064-05)

facility (Объект) – building, structure or complex, operating as a whole. (RB G-05-039-96)

FAILURES (ОТКАЗЫ)

Common cause failures (Отказы по общей причине) – failures of systems (components) caused by a single failure or operator error, external or internal impact (event), or other cause. (OPB-12)

Note: Internal impacts (events) or causes are impacts occurring during initiating events of accidents, including pressure waves, jets, missiles, changes of parameters of media or fluids (pressure, temperature, chemical activity, etc.), fires, etc., design, process, or other internal causes.

Comment

This term corresponds to IAEA Glossary term “Common cause failure” (Отказ по общей причине).

Common mode failures (Отказы общего вида) – type of common cause failure resulting from human errors during design, construction and operation of facilities, or from adverse environmental effects. (RB-024-11)

Comment

This term corresponds to IAEA Glossary term “Common mode failure” (Общий отказ).

Critical failure (Критический отказ) – failure of a machine and (or) equipment, which could lead to infliction of harm to life and health people, to personal, corporate, municipal or state property, environment, life and health of animals and plants. (Technical Specifications on safety of machinery and equipment)

Dependent failure (specific case of common cause failure) (Зависимый отказ (частный случай отказа по общей причине)) – failure of a system (component, consequential to other failure or event. (OPB-12)

Failures (of machinery or equipment) (Отказы (машины или оборудования)) – event, consisting in degradation of operability of a machine and (or) equipment due to design errors, deviations from specified manufacturing or maintenance processes, violation of operational procedures or manuals. (Technical Specifications on safety of machinery and equipment)

Safe failure (Безопасный отказ) – system or component failure, in case of which the plant transfers to safe state without any need of actuation of actions through control safety systems. (OPB-12)

Undetectable failure (Необнаруживаемый отказ) – failure of system (component) that does not reveal itself when occurring in normal operation and is not detected by existing diagnostic and control tools systems according to the inspection and testing specifications. (OPB-12)

fast response pressure reducing station (установка Быстродействующая редукционная (БРУ)) – a system composed of a valve and orifice plate intended for reduction of steam parameters before discharging it to atmosphere, condenser, deairator, etc. (NP-068-05)

federal state metrological regulation (Федеральный государственный метрологический надзор) – controlling activities in the area of federal regulation of consistency of measurements performed by authorized federal executive bodies and consisting in systematic checks of compliance with the mandatory requirements established by the legislation of the Russian Federation and in taking actions prescribed by the legislation of the Russian Federation for violations identified during regulatory activities. (Federal Law No. 102-FZ “On ensuring unification of measurements”)

FINAL TEMPERATURE (ТЕМПЕРАТУРА КОНЕЧНАЯ) – temperature of the walls of equipment or pipelines equal to maximum arithmetic average of the temperatures on the outer and inner surface in one cross section under normal operation conditions, at which the value of allowable stress is selected during analysis of main dimensions of valves. (NP-068-05)

FIRE (ПОЖАР) – uncontrolled combustion causing material damage, harm to health and life of citizens, and to the interests of state and society. (Federal Law No. 69-FZ “On fire safety”)

FIRE ALARM (ПОЖАРНАЯ СИГНАЛИЗАЦИЯ) – combination of hardware designed for identification of fire, processing, transfer of fire notification in the prescribed form, transfer of special information and (or) initiation of signals to actuate automated fire fighting systems and smoke removal systems, process and engineered equipment, and other fire safety systems and facilities. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

fire alarm actuator (ПОЖАРНЫЙ ИЗВЕЩАТЕЛЬ) – technical component designed for generating fire signal. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

fire alarm system (СИСТЕМА ПОЖАРНОЙ СИГНАЛИЗАЦИИ) – a combination of fire alarm components installed at one facility and controlled from a common fire control point. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

FIRE AND EXPLOSION HAZARD OF SUBSTANCES AND MATERIALS (ПОЖАРОВЗРЫВОООПАСНОСТь ВЕЩЕСТВ и МАТЕРИАЛОВ) – ability of substances and materials to form flammable (fire and explosion hazardous) media characterized by their physical and chemical properties and (or) behavior in the conditions of fire. Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

fire annunciator (ПОЖАРНЫЙ ОПОВЕЩАТЕЛЬ) – technical component designed for notifying people about fire. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

fire barrier (ПРОТИВОПОЖАРНАЯ ПРЕГРАДА) – a structure with established fire resistance limit and assigned structural fire hazard class, volumetric part of a building or other engineering feature designed for preventing spreading of fire from one part of building or structure to another building or structure, or wooded area. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”, “Code of practice. Nuclear power plants. Fire safety requirements”. SP 13.13130.2009)

fire compartment (Пожарный отсек) – part of building or structure isolated by fire resistant walls and fire resistant flooring or surfaces, with the fire resistance limits of the structures ensuring non-propagation of fire beyond the limits of the compartments for the entire duration of fire. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”, “Code of practice. Nuclear power plants. Fire safety requirements”. SP 13.13130.2009)

fire control device (ПРИБОР УПРАВЛЕНИЯ ПОЖАРНЫЙ) – technical component designed for transferring control signals to automated fire fighting facilities and (or) startup of smoke protection system actuators, and (or) notification of people about fire, as well as for communication of signals to other fire protection components. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

fire DEPARTment (ПОЖАРНОЕ ДЕПО) – fire protection object, in which rooms for storage and maintenance of firefighting equipment and hardware are located, along with personnel rooms, room for receiving notifications of fire, auxiliary rooms and compartments required to achieve the tasks of the fire fighting service. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

fire fighting means, primary (СРЕДСТВА ПОЖАРОТУШЕНИЯ ПЕРВИЧНЫЕ) – see PRIMARY FIRE FIGHTING MEANS (ПЕРВИЧНЫЕ СРЕДСТВА ПОЖАРОТУШЕНИЯ).

FIRE HAZARD (ПОЖАРНАЯ ОПАСНОСТЬ)

Fire hazard of substances and materials (Пожарная опасность веществ и материалов) – state of substances and materials characterized by possibility of combustion or explosion of substances and materials. (Federal Law No 123-FZ “Technical Specifications on fire safety requirements”)

Fire hazard of the protection object (Пожарная опасность объекта защиты) – state of the protection object characterized by 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”)

fire hazard zone (ПОЖАРООПАСНАЯ ЗОНА) – see ZONE (ЗОНА).

fire notification system (СИСТЕМА ПЕРЕДАЧИ ИЗВЕЩЕНИЙ О ПОЖАРЕ) – a combination of jointly acting technical systems designed for transferring through communication channels and receiving in the centralized control and monitoring room notifications about fire at the protected facility, service and diagnostic notifications, and, in case of availability of reverse communication channel, transfer and acquisition of remote control signals. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

fire origin (ОЧАГ ПОЖАРА) – location of initial occurrence of fire. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

fire prevention system (Система предотвращения пожара) – a set of organizational and engineered measures precluding possibility of fire at the protected facility. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”, “Code of practice. Nuclear power stations. Fire safety requirements”. SP 13.13130.2009)

FIRE PROTECTION DISTANCE (ПРОТИВОПОЖАРНЫЙ РАЗРЫВ) – regulated distance between buildings and structures established for prevention of fire propagation. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

fire protection spacinG (ПРОТИВОПОЖАРНОЕ РАССТОЯНИЕ) – same as FIRE PROTECTION DISTANCE (ПРОТИВОПОЖАРНЫЙ РАЗРЫВ)

fire protection system (Система противопожарной защиты) – complex of organizational measures, engineered systems and hardware designed to protect people and property against the influence of hazardous factors of fire and (or) limit the influence of hazardous factors of fire upon the protected object (products). (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”, “Code of practice. Nuclear power stations. Fire safety requirements”. SP 13.13130.2009)

fire receiver anD control device (ПРИБОР ПРИЕМНО-КОНТРОЛЬНЫЙ ПОЖАРНЫЙ) – technical component, intended for receiving signals from fire alarm initiating systems, checking integrity of the fire alarm cable sleeves, visual indication and audio alarm, generation of startup signal for fire control device. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

fire resistance limit of structure (fire barrier filling) (ПРЕДЕЛ ОГНЕСТОЙКОСТИ КОНСТРУКЦИИ (ЗАПОЛНЕНИЯ ПРОЁМОВ ПРОТИВОПОЖАРНЫХ ПРЕГРАД)) – period of time from beginning of fire impact in the conditions of a standard test to occurrence of one of the limiting states postulated for the structure (fire barrier filling). (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

fire risk (ПОЖАРНЫЙ РИСК) – see RISK (РИСК).

fire safety of the protectION object (Пожарная безопасность объекта защиты) – see PROTECTION OBJECT FIRE SAFETY (БЕЗОПАСНОСТЬ ОБЪЕКТА ЗАЩИТЫ ПОЖАРНАЯ).

fire SUPRESSION (Ликвидация пожара) – actions to stop combustion and preclude its recurrence. (“Code of practice. Nuclear plants. Fire safety requirements”. SP 13.13130.2009)

FIRE ZONE (Пожарная зона) – see ZONE (ЗОНА).

fissile materials (Делящиеся материалы) – nuclear materials, containing Uranium-233, Uranium-235, Plutonium-239, Plutonium-241 or any combination of these nuclides. The following does not fall under this definition:

• non-irradiated natural uranium or depleted uranium;

• natural uranium or depleted uranium irradiated only in the thermal neutron reactors. (NP-053-04)

FIXED CONTAMINATION OF SURFACE (фиксированное загрязнение поверхности) – see CONTAMINATION (ЗАГРЯЗНЕНИЕ).

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

flame propagation, LOWER CONCENTRATION limit (предел распространения пламени Нижний концентрационный) – see LOWER CONCENTRATION LIMIT OF FLAME PROPAGATION (Нижний концентрационный предел распространения пламеНИ).

FLAMMABLE MEDIA (ГОРЮЧАЯ СРЕДА) – media capable of ignition under the influence of ignition source. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

flash flood (Паводок) – rapid short-term increase of water level in the river, followed by rapid decrease and occurring irregularly. (NP-064-05)

flooding (Наводнение) – inundation of territory within a river valley and townships located above the regular flood plain caused by precipitation in combination with other meteorological phenomena, e.g. repeated rainstorms and snow melting. (NP-064-05)

FLOW PATH cross-section (Сечение проходное) – the smallest of the areas formed by the gating (or regulating) element and the valve seat. (NP-068-05)

focus (Очаг) – area in the earth crust, where process of non-elastic failure of rock occurs as a result of “instantaneous” relief of tectonic stresses. (RB-006-98)

fragments (ОСКОЛКИ)

Primary fragments (Первичные осколки) – products of destruction of vessels or containers during explosions inside objects (buildings, structures or complexes). (RB G-05-039-96)

Secondary fragments (Вторичные осколки) – non-fixed objects located on the territory of facility or structures, set in motion by the explosion pressure wave from emergency explosion. (RB G-05-039-96)

fresh nuclear fuel (Свежее ядерное топливо) – new NF or non-irradiated NF made through reprocessing of irradiated nuclear fuel. (NP-061-05)

Comment

A corresponding term in the IAEA Glossary is “Fresh fuel” (Свежее топливо).

fuel assembly (сборка Тепловыделяющая) – a product of mechanical engineering containing nuclear materials and designed for obtaining thermal energy in a nuclear reactor at the expense of controlled nuclear reaction. (NP-082-07, NP-080-07, Federal Law No. 170-FZ “On the use of nuclear energy”)

Comment

A corresponding term in the IAEA Glossary is “Fuel assembly” (Топливная сборка).

fuel assembly of nuclear reactor (Тепловыделяющая сборка ядерного реактора) – see FUEL ASSEMBLY (сборка Тепловыделяющая).

fuel channel (Технологический канал) – a tube in the reactor designed for installation of fuel assembly. (PNAE G-7-008)

fuel element (Тепловыделяющий элемент (твэл)) – individual assembly unit containing nuclear materials and designed for generating thermal energy in nuclear reactor at the expense of controlled nuclear fusion reaction and (or) for accumulation of nuclides. (NP-082-07, NP-080-07)

Comment

A corresponding term in the IAEA Glossary is “Fuel element” (Топливный элемент).

FUEL ELEMENT DAMAGE (ПОВРЕЖДЕНИЕ ТВЭЛ) – violation of at least one of the damage limits established for fuel elements. (OPB-12, NP-082-07, NP-080-07)

fuel element destruction (Разрушение твэла) – loss of integrity of a fuel element resulting in loss of geometry enabling its designed cooling. (NP-082-07, NP-080-07)

FULL SCOPE SIMULATOR INSTRUCTOR (ИНСТРУКТОР ПМТ) – a person who has undergone appropriate full course of training and having the right to train operators of a nuclear plant. (NP-003-97)

FULL SCOPE SIMULATOR INTEGRATED TESTING REPORT (ОТЧЕТ О КОМПЛЕКСНЫХ ИСПЫТАНИЯХ ПМТ – report containing analysis of the results of integrated testing of full scope simulator (verification of compliance of the simulator with the technical specifications and requirements of the existing regulatory documents, determination of completeness realization of functions and training capabilities of the simulator, verification of consistency of the processes modeled by the simulator with experimental and analytical data for the prototype unit) containing testing program, results, and simulator mathematical model verification report. (NP-003-97)

FULL SCOPE SIMULATOR MODEL VERIFICATION REPORT (ОТЧЕТ О ВЕРИФИКАЦИИ МАТЕМАТИЧЕСКОЙ МОДЕЛИ ПМТ) – report, containing the results of testing and comparison of the processes in the simulator with experimental, design, and analytical data. (NP-003-97)

FULL SCOPE SIMULATOR OF A NUCLEAR POWER UNIT (ПОЛНОМАСШТАБНЫЙ ТРЕНАЖЕР ЭНЕРГОБЛОКА АС) – modeling software-hardware complex designed for group professional training of operating personnel of the main control room with the use of full scale model of a real MCR and integrated multi-mode mathematical model of the unit operating in real time. (NP-003-97)

FULL SCOPE SIMULATOR TESTS (ТЕСТИРОВАНИЕ ПМТ) – test of full scope simulator by means of solving problems with known answers with the aid of the simulator. (NP-003-97)

FUNCTIONAL 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 specifics of operation of the buildings, structures or fire compartment, including the specifics of technological processes performed in them. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”)

FUNCTIONAL GROUP (ФУНКЦИОНАЛЬНАЯ ГРУППА) – part of control system assumed in the design, representing a set of automation means performing a given function of control systems. (NP-026-04)

FUNCTIONAL GROUP QUALITY CATEGORY (КАТЕГОРИЯ КАЧЕСТВА ФУНКЦИОНАЛЬНОЙ ГРУППЫ) – combination of qualitative characteristics and quantitative measures of properties of a functional group, defined in the design documentation. (NP-026-04)

GATE valve (ЗАДВИЖКА) – see VALVES (АРМАТУРА).

generic data (Обобщенные данные) – see DATA (ДАННЫЕ).

geodynamic conditions (Условия геодинамические) – location of nuclear plant with respect to geodynamic zones. (NP-031-01)

geological and engineering-geological processes and phenomena (Геологические и инженерно-геологические процессы и явления) – processes and phenomena of natural origin, occurring in the upper horizons of the earth crust and caused by influence of energy sources located within the earth crust (endogenous sources) or outside it (exogenous sources), or by a combination thereof. Exogenous and endogenous energy sources are classified into natural and technogenic ones. (NP-064-05)

Geotechnogenic processes, gravity slope (геотехногенные процессы гравитационно-склоновые) – processes occurring or are enhanced on slopes in case of deforestation, ditching of the slopes and filtration of water from canals, powerful explosion and other technogenic processes decreasing mechanical strength of the ground and increasing tension in the slopes. (NP-064-05)

GRADIENT OF TECTONIC MOVEMENT VELOCITY (ГРАДИЕНТ СКОРОСТИ ТЕКТОНИЧЕСКИХ ДВИЖЕНИЙ) – change of amplitude of tectonic movements of marking surface per unit of distance and time. (Refined definition of RB-019-01)

ground acceleration (velocity, displacement) for design basis (Ускорение (скорость, перемещение) грунта для проектных основ) – peak free surface acceleration (velocity, displacement) with specified exceedence probability. (RB-006-98)

harmful natural processes and phenomena (ОПАСНЫЕ ПРИРОДНЫЕ ПРОЦЕССЫ и ЯВЛЕНИЯ) – earthquakes, mudslides, landslides, avalanches, flooding, hurricanes, tornadoes, soil erosion and other similar processes and phenomena causing negative influence on buildings or structures. (Federal Law No. 384-FZ “Technical specifications on safety of buildings and structures”)

HATCH (Люк) – a component of leaktight enclosure enabling entry of people and (or) transportation of the equipment across the structures enclosing the accident localization zone. (NP-010-11)

hazardous factor of fire (Опасный фактор пожара) – a factor of fire that can cause injury, poisoning or death of human and (or) material loss. (Federal Law No. 123-FZ “Technical Specifications on fire safety requirements”), “Code of practice. Nuclear power plants. Fire safety requirements”. SP 13.13130.2009)

HEAT SINK, ULTIMATE (ПОГЛОТИТЕЛЬ КОНЕЧНЫЙ) – see КОНЕЧНЫЙ ПОГЛОТИТЕЛЬ (ТЕПЛА) (ULTIMATE HEAT SINK).

hurricane (Ураган) – destructive wind (level 12 or above on the Beaufort wind scale), characterized by extensive duration and velocity of 35 m/s or more. (NP-064-05)

HYDRAULIC ENGINEERING FACILITIES (ГИДРОТЕХНИЧЕСКИЕ СООРУЖЕНИЯ) – dams, buildings of hydro power plants, water discharge, release or draining structures, tunnels, canals, pumping stations, ship locks, ship lifts; structures designed for protection against flood, degradation of banks and bottom of water reservoirs or rivers, structures (dams) surrounding liquid waste storage facilities of industrial or agricultural enterprises (except for centralized hot and cold water supply systems and (or) water disposal systems), specified in the Federal Law “On water supply and water disposal”; structures, preventing.erosion of canals and other structures designed for use of water resources and prevention or negative impacts of waters or liquid wastes. (Federal Law No. 117-FZ “On safety of hydraulic engineering facilities”)

HYDROGEN EXPLOSION PROTECTION (ВЗРЫВОЗАЩИТА ВОДОРОДНАЯ) – properties of the nuclear power plant and engineered measures preventing detonation of hydrogen-containing mixtures accumulated in the containment during normal operation and abnormal operation, including accidents, and mitigating the effects of combustion of the hydrogen-containing mixtures upon the containment walls and other safety related systems and components of the plant. (OPB-12, NP-010-11)

hydrometeorological processes and phenomena (Гидрометеорологические процессы и явления) – processes and phenomena occurring in atmosphere and hydrosphere and characterized by the parameters of air mass movement, moisture circulation, atmosphere thermal properties, hydrological properties of rivers, seas, oceans, and other parameters. (NP-064-05)

hypocenter (Гипоцентр) – a point at the earthquake source where the process of movement along the fault initiates during earthquake; it is characterized by geographic coordinates and depth. (RB-006-98)

Instrumental hypocenter (гипоцентр инструментальный) – a point at the earthquake source where the process of movement along the fault initiates during earthquake as determined by the data from seismic stations. (RB-006-98)

Macroseismic hypocenter (гипоцентр макросейсмический) – a point at the earthquake source corresponding to maximum density of released seismic energy as determined by macroseismic observations. (RB-006-98)

hypocentral distance (Расстояние гипоцентральное) – distance between hypocenter and observation point. (RB-006-98)

ice gorge (Зажор льда) – accumulation of unconsolidated ice material in a river bed. (NP-064-05)

ice jam (Затор льда) – mass of ice in the river bed that congests water flow in the river and causes an increase of water level at the location of the ice jam and upstream of it. (NP-064-05)

immobilization of products (Иммобилизация продуктов) – transfer of products classified as radioactive wastes into a form preventing, at the present technical level, extraction and further use of nuclear materials contained in the RW. (NP-072-06)

Comment

A corresponding term in the IAEA Glossary is “Immobilization” (Иммобилизация).

IMPACT (Воздействие) – a physical action (mechanical or influence) upon buildings, structures, systems, components or personnel of a nuclear facility, public and environmental objects. (NP-064-05)

External impact (воздействие внешнее) – impact caused by natural or technogenic phenomena, processes or factors that are external to the nuclear facility. (Refined definition of NP-064-05)

Comment

A corresponding term in the IAEA Glossary is “External event” (Внешнее событие).

Natural (external) impact (воздействие (внешнее) природное) –impact caused by natural phenomena, processes or factors that are external to the nuclear facility. (NP-064-05)

Technogenic (external) impact (воздействие (внешнее) техногенное) – impact caused by human actions directly or as a result of use of engineered facilities or technologies. (NP-064-05)

Technogenic impacts (техногенные воздействия) – hazardous impacts resulting from accidents in buildings, structures, or transportation systems, fires, explosions, release of various types of energy, or impacts resulting from construction activities in the adjacent territory. (Federal Law No. 384-FZ “Technical Specifications on safety of buildings and structures”)

incident (инцидент) – failure of a machine and (or) equipment, deviation from normal operation or violation of operating procedures. (Technical Specifications on safety of machinery and equipment)

incipient stage of fire (Начальная стадия пожара) – a stage of fire characterized by linear development of fire according to the fire load, up to the point of flashing of all flammable materials in the room. (“Code of practice. Nuclear power plants. Fire safety requirements”. SP 13.13130.2009)

INCLUSION (Включение) – cavity in the weld metal or weld overlay metal filled with gas, slug, or other foreign matter (pore, slug or tungsten inclusion). (PNAE G-7-010-89)

Slug inclusion (Шлаковое включение) – a cavity in the weld metal or weld overlay metal filled with slug. (PNAE G-7-008-89)

INCOMPLETE FUSION (Непровар) – incomplete welding in a welded joint or built-up (overlaid) component between the main metal and the metal of the weld (overlay) or between individual beads. (PNAE G-7-010-89)

increased planned exposure (повышенное планируемое Облучение) – see EXPOSURE (Облучение).

INDEPENDENCE PRINCIPLE (ПРИНЦИП НЕЗАВИСИМОСТИ) – principle of enhancement of reliability by means of functional and/or physical separation of trains (components), so that failure of one train (component) cannot cause failure of another train (component). (OPB-12)

INDEPENDENT SYSTEMS (COMPONENTS) (НЕЗАВИСИМЫЕ СИСТЕМЫ (ЭЛЕМЕНТЫ)) – systems (components), for which a failure of one system (component) does not cause a failure of another system (component). (OPB-12)