reactor target system

reactor target system, Total:264 items.

The international standard classification for "reactor target system" includes: Reactor engineering , Nuclear power plants. Safety , Nuclear energy engineering .

The Chinese standard classification for "reactor target system" includes: Nuclear reactor and nuclear island equipment of nuclear power plant , Nuclear instrument for reactor , Medical nuclear instrument , Nuclear island of nuclear power plant , Power reactor , General nuclear instrument .

Group Standards of the People's Republic of China

T/TLRIA 0005-2018 Rubber gaskets for ventilation systems in nuclear reactor pits
T/CNS 39-2020 Design criteria for the reactor protection system of high temperature gas-cooled reactor nuclear power plant
T/CNS 30-2020 Design criteria for the reactor coolant systems of high temperature gas cooled reactor nuclear power plant

Professional Standard - Energy

NB/T 20285-2014 General requirements of reactor system design for pressurized water reactor nuclear power plants
NB/T 20057.3-2023 Pressurized Water Reactor Nuclear Power Plant Reactor System Design Reactor Core Part 3: Fuel Assemblies
NB/T 20304-2014 Technical guideline for installation of reactor protection system of pressured water reactor nuclear power plants
NB/T 20254-2013 Code for the Leakage Detection of Reactor Coolant System in Nuclear Power Plants
NB/T 20102-2012 Determination of Steady State Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
NB/Z 20254-2013 Guidelines for Leak Detection of Reactor Coolant Systems in Nuclear Power Plants
NB/T 20057.1-2012 Pressurized Water Reactor Nuclear Power Plants Reactor System Design - Core - Part 1: Nuclear Design
NB/T 20343-2021 Design and fabrication specification for the thermal insulation of reactor vessel and reactor cool an tpipings and equipments of PWR nuclear power plants
NB/T 20057.3-2012 PWR Nuclear Power Plants Reactor System Design - Core - Part 3: Fuel Assembly
NB/T 20100-2012 Principles for Main Primary System and Main Steam System Overpressure Analysis of Pressurized Water Reactor Nuclear Power Plants
NB/T 20057.2-2012 Pressurized Water Reactor Nuclear Power Plants Reactor System Design - Core- Part 2: Thermal Hydraulic Design Criteria
NB/T 20467-2017 Commissioning technical guideline for reactor protection system of PWR nuclear power plant
NB/T 20688-2023 Transient analysis requirements for reactor coolant system design in pressurized water reactor nuclear power plants
NB/T 20556-2019 Calculation method of reactor core excess reactivity for heavy water reactor
NB/T 20064-2012 Installation and Test Requirement of In-core Instrumentation System in Pressured Water Reactor Nuclear Power Plant
NB/T 20434-2017RK PWR Nuclear Power Plant Reactor's First Fuel Loading Test
NB/T 20100-2016 Requirements of overpressure analysis for reactor coolant system and main steam system for pressurized water reactor unclear power plants
NB/T 20100-2016RK Requirements of overpressure analysis for reactor coolant system and main steam system for pressurized water reactor nuclear power plants
NB/T 20660-2023 Technical Guidelines for Commissioning of Reactor Coolant Systems in Pressurized Water Reactor Nuclear Power Plants
NB/T 20435-2017 Physics tests for pressurized water reactor of nuclear power plants commissioning startup
NB/T 20435-2017RK PWR Nuclear Power Plant Reactor Commissioning Start-up Core Physical Test
NB/T 20343-2015 Design and fabrication specification for the thermal insulation of reactor vessel and reactor coolant pipings and equipments of PWR nuclear power plants
NB/T 20187-2012 Design Criteria for Reactor Coolant System in Pressurized Water Reactor Nuclear Power Plants
NB/T 20057.4-2012 PWR Nuclear Power Plants Reactor System Design - Core - Part 4: Core Components
NB/T 20434-2017 Initial loading test for pressurized water reactor of nuclear power plant
NB/T 20582-2021 Commissioning technical guideline for reactor boron and water makeup system of PWR nuclear power plants
NB/T 20144-2012 Initial Criticality Tests for Pressurized Water Reactor of Nuclear Power Plants

General Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of China

GB/T 12789.2-1991 Criteria for nuclear reactor instrumentation Part 2:pressurized water reactors
GB/T 4083-1983 General safety principles of nuclear reactor protection system
GB/T 8995-1988 In-core instrumentation for neutron fluence rate measurements in nuclear reactors
GB/T 13628-1992 Nuclear reactor use of the protection system for non-safety purpose
GB/T 45569-2025 Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
GB/T 5963-1995 Separation criteria for reactor protection system
GB/T 4083-2005 General safety principles of unclear reactor protection system
GB 12789.2-1991 Nuclear Reactor Instrumentation Guidelines Part II: Pressurized Water Reactors
GB/T 8995-2008 In-core instrumentation for neutron fluence rate measurements in nuclear reactors
GB/T 12789.3-1992 Criteria for nuclear reactor reactor instrumentation Part three. High temperature gas-cooled reactor(HTGR)
GB 12789.3-1992 Nuclear Reactor Instrumentation Guidelines Part III: High Temperature Gas Cooled Reactors
GB/T 12789.3-2025 Criteria for nuclear reactor instrumentation—Part 3：High temperature gas-cooled reactor
GB/T 12789.2-2025 Criteria for nuclear reactor instrumentation—Part 2: Pressurized water reactors
GB/T 41591-2022 Initial criticality tests for pressurized water reactor of nuclear power plants

Professional Standard - Nuclear Industry

EJ/T 1114-2000 Initial loading test for PWR nuclear power plant
EJ/T 449-1989 300MW PWR Nuclear Power Plant Reactor Main System Equipment and Installation Guidelines for Its Supports
EJ/T 675-1992 Fission ionization chamber for reactor
EJ/T 20130-2016 Design criteria for ship reactor containment and systems
EJ/T 325-1988 Design criteria for reactor coolant system in pressurized water reactor nuclear power plant
EJ/T 720-2008 Design criterion for the thermal insulation of reactor vessel and reactor coolant pipings and equipments of PWR nuclear power plants
EJ/T 720-1992 Design criteria for the insulation layer of reactor pressure vessels and reactor coolant system piping and equipment in pressurized water reactor nuclear power plants
EJ/T 20206-2018 Sodium Cooled Fast Breeder Reactor Design Criteria Reactor Overpressure Protection System
EJ 326-1988 Design criteria for reactor coolant auxiliary systems in pressurized water reactor nuclear power plants
EJ/T 383-1989 Transient regulations for design of reactor coolant system in 300 MW pressurized water reactor nuclear power plant
EJ/T 1115-2000 Physics tests at low power for PWR nuclear power plant
EJ/T 320-1998 General design criteria of reactor for pressurized water reactor nuclear power plants
EJ/T 1113-2000 Initial critical test in PWR nuclear power plant
EJ/T 1014-2005 Determination of steady state neutron reaction rate distributions and reactivity of nuclear reactors
EJ/T 836-1994 Pulse Reactor Commissioning Program
EJ/T 318-1992 Reactor Design Criteria for Pressurized Water Reactor Nuclear Power Plants
EJ/T 853-1994 Design and application of microreactor beryllium reflector
EJ/T 567-1991 Nuclear Reactor Instrumentation Terminology
EJ 622-1992 Reactor Fuel Element Terminology
EJ/T 493-1989 300MW PWR Nuclear Power Plant Reactor Core Neutron Flux Measurement System Piping Design Regulations
EJ/T 400-1989 Technical conditions for piping installation of the secondary circuit system of the reactor building of the 300,000-kilowatt pressurized water reactor nuclear power plant
EJ/T 668-1992 Design criteria for reactor coolant pressure boundary leak detection system for pressurized water reactor nuclear power plants
EJ 334-1988 Design criteria for main equipment supports of reactor coolant system in pressurized water reactor nuclear power plant
EJ/T 20050-2014 Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors

Professional Standard - Navy

HJB 220-2000 Test target for antiship missile weapon system

Military Standard of the People's Republic of China-General Armament Department

GJB 3550-1999 Specification for submarine reactor coolant systems and equipment insulation
GJB 6269-2008 Specification for the target of anti-ship missile weapon system
GJB 820A-2018 Specification for coatings for submarine reactor compartments
GJB 2984-1997 Specification for vertical target acoustic target system for gun use

Professional Standard - Energy and Power Planning

DL/T 1142-2009 Suftwarae test for reactur cuntrul systemof nuelear popear power plants

Professional Standard - Machinery

JB/T 14283-2022 Vertical in-vessel composter

American Nuclear Society (ANS)

15.15-1978 Criteria for the Reactor Safety Systems of Research Reactors
ANS 15.15-1978(R1986) Criteria for the Reactor Safety Systems of Research Reactors
ANS 56.6-1978 Pressurized Water Reactor Containment Ventilation Systems
51.10-1979 AUXILIARY FEEDWATER SYSTEM FOR PRESSURIZED WATER REACTORS
56.6-1986 Pressurized Water Reactor Containment Ventilation Systems
56.6-1978 PRESSURIZED WATER REACTOR CONTAINMENT VENTILATION SYSTEMS
ANS 56.6-1986 Pressurized Water Reactor Containment Ventilation Systems
ANS 56.7-1978(R1987) Boiling Water Reactor Containment Ventilation Systems
56.7-1978 Boiling Water Reactor Containment Ventilation Systems
ANS 51.10-1991 Auxiliary feedwater system for pressurized water reactors
ANS 59.1-1986 Cooling Water Systems for Light Water Reactors, Nuclear Safety Related
ANS 59.1-1979 Nuclear Safety Related Cooling Water Systems for Light Water Reactors
ANS 55.6-1979 Liquid Radioactive Waste Processing System for Light Water Reactor Plants
57.1-1980 DESIGN REQUIREMENTS FOR LIGHT WATER REACTOR FUEL HANDLING SYSTEMS
ANS 57.1-1992(R2024) Design Requirements for Light Water Reactor Fuel Handling Systems
57.1-1992 Design Requirements for Light Water Reactor Fuel Handling Systems
ANS 57.1-1992 Design Requirements for Light Water Reactor Fuel Handling Systems
ANS 55.1-2021 Solid Radioactive Waste Processing System for Light-Water-Cooled Reactor Plants
58.6-1996 Criteria for Remote Shutdown for Light Water Reactors
19.3-1983 DETERMINATION OF NEUTRON REACTION RATE DISTRIBUTIONS AND REACTIVITY OF NUCLEAR REACTORS
ANS 55.1-1979 Solid Radioactive Waste Processing System for Light-Water-Cooled Reactor Plants
ANS 15.16-2015(R2024) Emergency Planning for Research Reactors
ANS 55.4-1993 Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants
ANS 19.3-2005 Determination of Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
58.6-1983 CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTORS
19.3-1995 Determination of Steady State Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
ANS 19.3-1995 Determination of Steady State Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
ANS 55.4-1979 Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants
ANS 55.6-1993 Liquid Radioactive Waste Processing System for Light Water Reactor Plants
14.1-1975 Operation of Fast Pulse Reactors
ANS 15.16-2008 Emergency planning for research reactors
19.3-2005 Determination of Steady-State Neutron Reaction-Rate Distributions and Reactivity of Nuclear Power Reactors
ANS 58.9-1981(R2020) Single Failure Criteria for Light Water Reactor Safety-Related Fluid Systems
55.4-1993 Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants
55.6-1993 Liquid Radioactive Waste Processing System for Light Water Reactor Plants
58.9-2002 Single failure criteria for light water reactor safety-related fluid systems
14.1-2004 Operation of Fast Pulse Reactors
ANS 14.1-2004(R2019) Operation of Fast Pulse Reactors
ANS 14.1-2004(R2024) Operation of Fast Pulse Reactors
ANS 55.6-1993(R2007) Liquid Radioactive Waste Processing System for Light Water Reactor Plants
ANS 55.1-1992(R2017) Solid Radioactive Waste Processing System for Light-Water-Cooled Reactor Plants
ANS 58.11-1983(W1995) Cooldown Criteria for Light Water Reactors
ANS 55.4-1993(R1999) Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants
ANS 19.3-1983 Determination of Steady-State Neutron Reaction-Rate Distributions and Reactivity of Nuclear Power Reactors
55.4-1979 GASEOUS RADIOACTIVE WASTE PROCESSING SYSTEMS FOR LIGHT WATER REACTOR PLANTS
ANS 56.3-1977(R1987) Overpressure Protection of Low Pressure Systems Connected to the Reactor Coolant Pressure
55.6-1979 LIQUID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT WATER REACTOR PLANTS
ANS 14.1-1975 Operation of Fast Pulse Reactors R(2000)
ANS 14.1-1975(R2000) Operation of Fast Pulse Reactors
ANS 14.1-2004 Operation of Fast Pulse Reactors
58.11-1983 COOLDOWN CRITERIA FOR LIGHT WATER REACTORS
ANS 19.11-1997 Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Water Moderated Power Reactors

Canadian General Standards Board （CGSB)

CAN3-N290.1-1980(C2011) Requirements Related to CANDU Nuclear Power Plant Shutdown Systems
CAN3-N290.4-M82-1982(R2011) Requirements for the Reactor Regulating Systems of CANDU Nuclear Power Plants
CAN3 N290.4-M82-1982(R2006) Requirements for the Reactor Regulating Systems of CANDU Nuclear Power Plants
CAN3-N290.4-M82-1982(C2011) Requirements for nuclear power plant reactor control systems (CANDU)

Canadian Standards Association (CSA)

CSA N290.4-2019 Reactor control system requirements
CSA N290.4-11:2011 Requirements for reactor control systems of nuclear power plants
CSA N290.4-2011(R2016) Requirements for Reactor Control of Systems of Nuclear Power Plants
CSA N290.4-2011 Requirements for reactor control systems of nuclear power plants (Second Edition)
CSA N290.11-13:2014 Requirements for reactor heat removal capacity during shutdown of nuclear power plants
CSA N290.4-M82-CAN3-1982 Requirements for the Reactor Regulating Systems of CANDU Nuclear Power Plants General Instruction No 1

American National Standards Institute （ANSI)

ANSI/ANS 56.5-1979 American National Standard for PWR and BWR Containment Spray System Design Criteria
ANSI/ANS 51.10-1991 Auxiliary Feedwater System for Pressurized Water Reactors
ANSI/ANS 56.8-2002 Nuclear Reactors – Containment System Leakage Testing Requirements
ANSI/ANS 55.4-1993 Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants
ANSI/ANS 57.1-1992 Design Requirements for Light Water Reactor Fuel Handling Systems
ANSI/ANS 55.1-1992 Solid Radioactive Waste Processing System for Light Water Cooled Reactor Plants
ANSI/ANS 55.4-1993(2007) Gaseous radioactive waste treatment system for light water reactor power plants
ANSI/ANS 15.16-2008 Emergency Planning for Research Reactors
ANSI/ANS 58.11-1995(2002) Cooldown Criteria for Light Water Reactors
ANSI/ANS 58.11-1995 Cooldown Criteria for Light Water Reactors
ANSI/ANS 56.2-1984(2000) Containment Isolation Provisions for Fluid Systems After a LOCA
ANSI/ANS 55.6-1993(2007) Liquid Radioactive Waste Processing Systems for Light Water Reactor Plants
ANSI/ANS 55.6-1993 Liquid Radioactive Waste Processing Systems for Light Water Reactor Plants
ANSI/ANS 55.1-2021 Solid Radioactive Waste Processing System for Light- Water-Cooled Reactor Plants
ANSI/ANS 58.9-2002(2015) Single Failure Criteria for Light Water Reactor Safety-Related Fluid Systems
ANSI/ANS 14.1-2004 Operation of Fast Pulse Reactors
ANSI/ANS 14.1-2004(2014) operation of fast pulse reactors
ANSI/ANS 58.9-2002 Single Failure Criteria for Light Water Reactor Safety-Related Fluid Systems
ANSI/ANS 8.17-2004 Criticality Safety Criteria for the Handling, Storage and Transportation of LWR Fuel Outside Reactors
ANSI/ANS 5.1-2005 Light Water Reactors, Decay Heat Power in
ANSI/ANS 58.6-1996 Reactor Design and Safety Specifications

Türk Standardları Enstitüsü

TS 1819-1975 SERIES REACTORS
TS 2596-1977 General Characteristics of Nuclear Reactor Instn?mentation

Swedish Institute for Standards

SIS SS IEC 639:1981 Nuclear instrumentation - Nuclear reactors - Use of the protection system for non-safety purposes
SIS SS IEC 671:1983 Nuclear instrumentation - Protection system of nuclear reactors - Period/c tests and monitoring

Czech Standards Institute (UNMZ)

CSN IEC 709:1993 Separation within the reactor protection system
CSN IEC 639:1994 Nuclear reactors.Use of the protection system for non-safety purposes
CSN IEC 231:1994 General principles of nuclear reactor instrumentation

Bureau of Indian Standards

IS 5553-5-1989 Reactors: Part 5 Tuning reactors
IS 5553-8-1990 Reactors: Part 8 Smoothing reactors
IS 5553-1-1989 Reactors - Part 1 : General

International Electrotechnical Commission (IEC)

IEC 60709:1981 Separation within the reactor protection systems
IEC 60289:1968 Reactors
IEC 61343:1996 Nuclear reactor instrumentation - Boiling light water reactors (BWR) - Measurements in the reactor vessel for monitoring adequate cooling within the core
IEC 61505:1998 Nuclear reactor instrumentation - Boiling water reactors (BWR) - Stability monitoring
IEC 60639:1979 Nuclear reactors. Use of the protection system for non-safety purposes
IEC 60671:1980 Periodic tests and monitoring of the protection system of nuclear reactors
IEC 60911:2025 PRV Nuclear power plants - Instrumentation systems - Measurements for monitoring adequate cooling within the core of pressurized light water reactors
IEC 62117:1999 Nuclear Reactor Instrumentation - Pressurized Light Water Reactors (PWR) - Monitoring Adequate Cooling within the Core During Cold Shutdown (Edition 1.0)
IEC 60231D:1975 General principles of nuclear reactor instrumentation
IEC 63374:2025 PRV Nuclear power plants – Instrumentation systems important to safety – Characteristics and test methods of nuclear reactor reactivity meters
IEC 62118:2000 Nuclear reactor instrumentation - Pressurized water reactor (PWR) of VVER design - Monitoring adequate cooling within the core during shutdown
IEC 60231G:1977 General principles of nuclear reactor instrumentation. Seventh supplement: Liquid-metal cooled fast reactor
IEC 61250:1994 Nuclear reactors; instrumentation and control systems important for safety; detection of leakage in coolant systems
IEC 60231C:1974 General principles of nuclear reactor instrumentation
IEC 60231B:1972 General principles of nuclear reactor instrumentation
IEC 60231:1967 General principles of nuclear reactor instrumentation
IEC 60231F:1977 General principles of nuclear reactor instrumentation. Sixth supplement: Heavy-water-moderated reactor with steam generating direct-cycle turbine
IEC 60557:1982 I E C terminology in the nuclear reactor field

Korean Agency for Technology and Standards (KATS)

KS C IEC 60289-2013 Reactors
KS C IEC 60709:2012 Nuclear power plants-Instrumentation and control systems important to safety-Separation
KS C IEC 60289-2003(2008) Reactors
KS C IEC 60671:2012 Nuclear power plants-Instrumentation and control systems important to safety-Surveillance testing
KS C IEC 62117-2009(2019) Nuclear reactor instrumentation－ Pressurized light water reactors(PWR)－ Monitoring adequate cooling within the core during cold shutdown
KS C IEC 62117-2024 Nuclear reactor instrumentation－ Pressurized light water reactors(PWR)－ Monitoring adequate cooling within the core during cold shutdown
KS C IEC 62117-2009(2024) Nuclear reactor instrumentation－ Pressurized light water reactors(PWR)－ Monitoring adequate cooling within the core during cold shutdown
KS C IEC 62117:2009 Nuclear reactor instrumentation- Pressurized light water reactors(PWR)- Monitoring adequate cooling within the core during cold shutdown
KS C IEC 60231D:2012 Fourth supplement:Principles of instrumentation for pressurized water reactors
KS C IEC 61250-2006(2016) Nuclear reactors－Instrumentation and control systems important for safety－Detection of leakage in coolant systems
KS C IEC 60557-2004(2014) IEC terminology in the nuclear reactor field
KS C IEC 61250:2006 Nuclear reactors－Instrumentation and control systems important for safety－Detection of leakage in coolant systems
KS C IEC 60557:2004 IEC terminology in the nuclear reactor field
KS C IEC 60557-2016 IEC terminology in the nuclear reactor field
KS D 3748-2008(2018) Steel for steam evaporator of nuclear reactor
KS C IEC 60231:2012 General principles of nuclear reactor instrumentation

British Standards Institution (BSI)

BS EN 60289:1995 Reactors
BS EN 60289:1994 Reactors
BS IEC 61505:1998 Nuclear reactor instrumentation. Boiling water reactors (BWR). Stability monitoring
BS ISO 4233:2023 Reactor technology. Nuclear fusion reactors. Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors
25/30475278 DC BS ISO 18075 Reactor technology - Power reactor analysis - Steady-state neutronics methods
BS IEC 62117:2000 Nuclear reactor instrumentation - Pressurized light water reactors (PWR) - Monitoring adequate cooling within the core during cold shutdown
BS IEC 62117:1999 Nuclear reactor instrumentation. Pressurized light water reactors (PWR). Monitoring adequate cooling within the core during cold shutdown.
BS ISO 23466:2020 Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
23/30469793 DC BS IEC 60911. Nuclear Power Plants. Instrumentation systems. Measurements for monitoring adequate cooling within the core of pressurized light water reactors

Spanish Association for Standardization (UNE)

UNE-EN 60289:1995 REACTORS

European Committee for Electrotechnical Standardization（CENELEC）

EN 60289:1994 Reactors

International Atomic Energy Agency

NS-G-1.10-2004 Design of Reactor Containment Systems for Nuclear Power Plants
NS-G-1.9-2004 Design of the Reactor Coolant System and Associated Systems in Nuclear Power Plants
NS-G-1.12-2005 Design of the Reactor Core for Nuclear Power Plants

German Institute for Standardization

DIN 25434:1986 Reactor protection system and monitoring equipment of the safety system
DIN 25434:1986-11 Reactor protection system and monitoring equipment of the safety system
DIN 25473 E:1992-04 Drainage systems in nuclear power plants with light water reactors
DIN 25476:2023 Primary-coolant clean-up system in nuclear power plants with light water reactors
DIN 25442:1980 Evaluation of shutdown reactivity
DIN 25476 E:2022-10 Primary-coolant clean-up system in nuclear power plants with light water reactors
DIN 25476:1987 Primary-coolant clean-up system in nuclear power plants with light water reactors
DIN 25476:2012 Primary-coolant clean-up system in nuclear power plants with light water reactors
DIN 25476 E:2011 Draft Document - Primary-coolant clean-up system in nuclear power plants with light water reactors
DIN 25476:2022-10 Draft Document - Primary-coolant clean-up system in nuclear power plants with light water reactors
DIN 25433:1988-03 Fuel assembly identification for nuclear power reactors
DIN IEC 62117:2001-10*VDE 0491-4:2001-10 Nuclear power plants - Pressurized light water reactors

Ente Nazionale Italiano di Unificazione

UNI 7459:1975 Nuclear power plants. Power reactors. Criteria for protection systems.
UNI ISO 4233:2023 Reactor technology - Nuclear fusion reactors - Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors
UNI 9785:1990 Protective coatings (paints) for light water nuclear reactor containment facilities. Determination of fire reaction.
UNI 7459-1975 Nuclear power plants. Power reactors. Criteria for protection systems.
UNI 7797:1977 Nuclear installations. Isolating, control and check valves of water reactors.

Magyar Szabványügyi Testület

MNOSZ 2960-1951 Technology Thermal Reactor Plan Thermal Reactor Equipment Logo
MSZ 14345/2-1976 Nuclear energy, nuclear reactor concept
MSZ 9200/30-1980 Electronic signals. Reactors and base stations
MSZ 24030/2-1980 Nuclear reactor equipment storage classification

The Directorate General of Specifications and Metrology (DGSM)

OS GSO IEC 62117:2015 Nuclear reactor instrumentation - Pressurized light water reactors (PWR) - Monitoring adequate cooling within the core during cold shutdown

GCC Standardization Organization

GSO IEC 62117:2015 Nuclear reactor instrumentation - Pressurized light water reactors (PWR) - Monitoring adequate cooling within the core during cold shutdown
GSO IEC/TR 61510:2014 RBMK nuclear reactors - Proposals for instrumentation and control improvements

Asociación Española de Normalización (AENOR)

INTA 15 03 34 berlin blue reactor

American Society for Testing and Materials (ASTM)

ASTM STP 1228-1994 Nuclear Reactor Dosimetry
ASTM STP 1490-2007 Nuclear Reactor Dosimetry
ASTM STP 314-1962 Reactor structural materials and the impact of nuclear reactor service on their engineering performance
ASTM DS52-1974 NUCLEAR REACTOR NEUTRON ENERGY SPECTRA

Instrument Society of America (ISA)

ISA ADV REACT MEAS CNTRL-2015 Advances in Reactor Measurement and Control

American Society of Mechanical Engineers (ASME)

ASME N-7-2010 Nuclear Containments
ASME N-7-2002 Nuclear Containments Data Report (07/01)

Gosstandart of Russia

GOST 26843-1986 Nuclear power reactors. General requirements for control and testify systems
GOST 18624-1973 Reactors. Terms and definitions
GOST 17137-1987 Monitoring, control and protection systems of nuclear reactors. Terms and definitions
GOST 23082-1978 Nuclear reactors. Terms and definitions

Defense Logistics Agency

DLA MS16476 REV A VALID NOTICE 2-2003 INDUCTOR, (REACTOR) TYPE TF4SX04EB214
DLA MS16476 REV A-1966 INDUCTOR, (REACTOR) TYPE TF4SX04EB214
DLA MS16476 REV A VALID NOTICE 1-1988 INDUCTOR, (REACTOR) TYPE TF4SX04EB214

US Federal Contractor Registration (USFCR)

FCR DOE 5480.6-1986 SAFETY OF DEPARTMENT OF ENERGY-OWNED NUCLEAR REACTORS
FCR DOE 5480.30-1993 NUCLEAR REACTOR SAFETY DESIGN CRITERIA

International Organization for Standardization (ISO)

ISO 23466:2020 Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
ISO 4233:2023 Reactor technology — Nuclear fusion reactors — Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors

Indonesia Standards

SNI 2034:2024 Panduan evaluasi tapak reaktor nuklir
SNI IEC 60557:2009 IEC Terminology in nuclear reactor field

Polski Komitet Normalizacyjny (PKN)

PN J01101-1989 Nuclear technics Inspection, control and protection systems of nuclear reactor Terms and definitions

American Water Works Association (AWWA)

AWWA JAW6685 Journal AWWA — Nuclear Power Reactor Accidents and the Role of Water System Managers

National Standardisation Body (ASRO)

STAS 6729/1-1982 Nuclear energy PHYSICS OF NUCLEAR REACTORS Glosaary

Others: Criteria for design and operation of ventilation systems for non-reactor nuclear facilities,Target system,reactor target system,Liquid Target System,Liquid Radioactive Waste Treatment System in Light Water Cooled Reactors,Image target system