Document Center List of Standards on Reactor Engineering
ICS Code 27.120.10
Return to ICS Index.Up to Level 2:
The following documents are a part of this series:
ASTM:
- ASTM-B876 - Standard Specification for Borated Dispersion Strengthened Copper Plate, Sheet, Strip, and Rolled Bar for Nuclear Application (Withdrawn 2002)
- ASTM-C1051 - Standard Specification for Sodium (Na) as a Coolant for Liquid Metal-Cooled Reactors (Withdrawn 2000)
- ASTM-C1533 - Standard Guide for General Design Considerations for Hot Cell Equipment
- ASTM-C1615 - Standard Guide for Mechanical Drive Systems for Remote Operation in Hot Cell Facilities
- ASTM-C1725 - Standard Guide for Hot Cell Specialized Support Equipment and Tools
- ASTM-C781 - Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
- ASTM-C983 - Test Methods for Chemical and Instrumental Analysis of Metallic Core Components in Liquid Metal Fast-Breeder Reactors (LMFBR) (Withdrawn 1996)
- ASTM-D5144 - Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants
- ASTM-D7013 - Standard Guide for Calibration Facility Setup for Nuclear Surface Gauges
- ASTM-D7727 - Standard Practice for Calculation of Dose Equivalent Xenon (DEX) for Radioactive Xenon Fission Products in Reactor Coolant
- ASTM-E1167 - Standard Guide for Radiation Protection Program for Decommissioning Operations
- ASTM-E1278 - Standard Guide for Radioactive Pathway Methodology for Release of Sites Following Decommissioning (Withdrawn 2005)
- ASTM-E185 - Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
- ASTM-E2005 - Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
- ASTM-E2006 - Standard Guide for Benchmark Testing of Light Water Reactor Calculations
- ASTM-E2215 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
- ASTM-E2956 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
- ASTM-E509 - Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
- ASTM-E521 - Standard Practice for Investigating the Effects of Neutron Radiation Damage Using Charged-Particle Irradiation
- ASTM-E531 - Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials (Withdrawn 2022)
- ASTM-E560 - Standard Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E706(IC) (Withdrawn 2009)
- ASTM-E636 - Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
- ASTM-E706 - Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
- ASTM-E764 - Practice for Identifying Test Methods for Breeder Reactor Core Materials (Withdrawn 1998)
- ASTM-E798 - Standard Practice for Conducting Irradiations at Accelerator-Based Neutron Sources
- ASTM-E900 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
BSI:
- BS-4877 - Nuclear reactor instrumentation and control. Code of practice
- BS-4877-TC - Tracked Changes. Nuclear reactor instrumentation and control. Code of practice
- BS-6078 - Guide to the application of digital computers to nuclear reactor instrumentation and control
- BS-EN-IEC-61031 - Nuclear facilities. Instrumentation and control system. Design location and application criteria for installed area gamma radiation dose rate monitoring equipment for use during normal operation and anticipated operational occurrences
- BS-EN-IEC/IEEE-60980-344 - Nuclear facilities. Equipment important to safety. Seismic qualification
- BS-EN-ISO-10270 - Corrosion of metals and alloys. Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
- BS-EN-ISO-19226 - Nuclear energy. Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
- BS-IEC-61031 - Nuclear facilities. Instrumentation and control systems. Design, location and application criteria for installed area gamma radiation dose rate monitoring equipment for use during normal operation and anticipated operational occurrences
- BS-IEC-61501 - Nuclear reactor instrumentation. Wide range neutron fluence rate meter. Mean square voltage method
- BS-IEC-61505 - Nuclear reactor instrumentation. Boiling water reactors (BWR). Stability monitoring
- BS-IEC-62117 - Nuclear reactor instrumentation. Pressurized light water reactors (PWR). Monitoring adequate cooling within the core during cold shutdown.
- BS-IEC-62118 - Nuclear reactor instrumentation. Pressurized water reactor (PWR) of VVER design. Monitoring adequate cooling within the core during cold shutdown
- BS-IEC/IEEE-60980-344 - Nuclear facilities. Equipment important to safety. Seismic qualification
- BS-ISO-10645 - Nuclear energy. Light water reactors. Decay heat power in non-recycled nuclear fuels
- BS-ISO-18075 - Steady-state neutronics methods for power-reactor analysis
- BS-ISO-18077 - Reload startup physics tests for pressurized water reactors
- BS-ISO-18077-TC - Tracked Changes. Reload startup physics tests for pressurized water reactors
- BS-ISO-18229 - Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors
- BS-ISO-19226 - Nuclear energy. Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
- BS-ISO-20890-1 - Guidelines for in-service inspections for primary coolant circuit components of light water reactors
- BS-ISO-20890-2 - Guidelines for in-service inspections for primary coolant circuit components of light water reactors
- BS-ISO-20890-3 - Guidelines for in-service inspections for primary coolant circuit components of light water reactors
- BS-ISO-20890-4 - Guidelines for in-service inspections for primary coolant circuit components of light water reactors
- BS-ISO-20890-5 - Guidelines for in-service inspections for primary coolant circuit components of light water reactors
- BS-ISO-23468 - Reactor technology. Power reactor analyses and measurements. Determination of heavy water isotopic purity by Fourier transform infrared spectroscopy
- BS-ISO-26802 - Nuclear facilities. Criteria for the design and the operation of containment and ventilation systems for nuclear reactors
IEC:
- IEC-1224 - Nuclear reactors - Response time in resistance temperature detectors (RTD) - In situ measurements
- IEC-231 - General principles of nuclear reactor instrumentation
- IEC-231A - First supplement
- IEC-231B - Second supplement: Principles of instrumentation of direct cycle boiling water power reactors
- IEC-231C - Third supplement: Instrumentation of gas-cooled graphite-moderated reactors
- IEC-231D - Fourth supplement: Principles of instrumentation for pressurized water reactors
- IEC-231E - Fifth supplement: Principles of instrumentation of high temperature indirect cycle gas-cooled power reactors (HTGR)
- IEC-231F - Sixth supplement: Steam generating, direct cycle, heavy-water moderated reactors
- IEC-231G - Seventh supplement: Liquid-metal cooled fast reactors
- IEC-60568 - Nuclear power plants - Instrumentation important to safety - In-core instrumentation for neutron fluence rate (flux) measurements in power reactors
- IEC-60768 - Nuclear power plants - Instrumentation important to safety - Equipment for continuous in-line or on-line monitoring of radioactivity in process streams for normal and incident conditions
- IEC-60964 - Nuclear power plants - Control rooms - Design
- IEC-60964-RL - Nuclear power plants - Control rooms - Design
- IEC-61031 - Nuclear facilities - Instrumentation and control systems - Design, location and application criteria for installed area gamma radiation dose rate monitoring equipment for use during normal operation and anticipated operational occurrences
- IEC-980 - Recommended practices for seismic qualification of electrical equipment of the safety system for nuclear generating stations
- IEC/IEEE-60980-344 - Nuclear facilities - Equipment important to safety - Seismic qualification
ISO:
- ISO-10270 - Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
- ISO-10645 - Nuclear energy - Light water reactors - Decay heat power in non-recycled nuclear fuels
- ISO-10979 - Identification of fuel assemblies for nuclear power reactors
- ISO-18075 - Steady-state neutronics methods for power-reactor analysis
- ISO-18077 - Reload startup physics tests for pressurized water reactors
- ISO-18229 - Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors
- ISO-19226 - Nuclear energy - Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
- ISO-20890-1 - Guidelines for in-service inspections for primary coolant circuit components of light water reactors - Part 1: Mechanized ultrasonic testing
- ISO-20890-2 - Guidelines for in-service inspections for primary coolant circuit components of light water reactors - Part 2: Magnetic particle and penetrant testing
- ISO-20890-3 - Guidelines for in-service inspections for primary coolant circuit components of light water reactors - Part 3: Hydrostatic testing
- ISO-20890-4 - Guidelines for in-service inspections for primary coolant circuit components of light water reactors - Part 4: Visual testing
- ISO-20890-5 - Guidelines for in-service inspections for primary coolant circuit components of light water reactors - Part 5: Eddy current testing of steam generator heating tubes
- ISO-23018 - Group-averaged neutron and gamma-ray cross sections for radiation protection and shielding calculations for nuclear reactors
- ISO-23468 - Reactor technology - Power reactor analyses and measurements - Determination of heavy water isotopic purity by Fourier transform infrared spectroscopy
- ISO-26802 - Nuclear facilities - Criteria for the design and the operation of containment and ventilation systems for nuclear reactors
- ISO-7753 - Nuclear criticality safety - Use of criticality accident alarm systems for operations
Other SDOs:
- EN-ISO-10270 - Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
- SS-EN-ISO-10270 - Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors (ISO 10270:2022)
- SS-EN-ISO-18229 - Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors (ISO 18229:2018)
- SS-EN-ISO-19111-2 - Geographic information - Spatial referencing by coordinates - Part 2: Extension for parametric values (ISO 19111-2:2009)
- SS-EN-ISO-19226 - Nuclear energy - Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals (ISO 19226:2017)
- SS-ISO-10979 - Identification of fuel assemblies for nuclear power reactors (ISO 10979:2019, IDT)
- SS-ISO-18075 - Steady-state neutronics methods for power-reactor analysis (ISO 18075:2018, IDT)
- SS-ISO-18077 - Reload startup physics tests for pressurized water reactors (ISO 18077:2022, IDT)
- SS-ISO-18195 - Method for the justification of fire partitioning in water cooled nuclear power plants (NPP) (ISO 18195:2019, IDT)
- SS-ISO-18229 - Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors (ISO 18229:2018, IDT)
- SS-ISO-19226 - Nuclear energy - Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals (ISO 19226:2017, IDT)
- SS-ISO-20956 - Radiological protection - Low dose rate calibration of instruments for environmental and area monitoring (ISO 20956:2023, IDT)
- SS-ISO-23468 - Reactor technology Power reactor analyses and measurements Determination of heavy water isotopic purity by Fourier transform infrared spectroscopy (ISO 23468:2021, IDT)
- SS-ISO-26802 - Nuclear facilities - Criteria for the design and the operation of containment and ventilation systems for nuclear reactors (ISO 26802:2010, IDT)
- SS-ISO-6258 - Nuclear power plants - Design against seismic hazards
- SS-ISO-6527 - Nuclear power plants - Reliability data exchange - General guidelines