Standards

NB/T 20007.14-2021 Pressurized water reactor nuclear power plant stainless steel - Part 14: forged and rolled bars of austenitic stainless steels grades 1, 2, and 3

This document specifies the requirements for the manufacture, chemical composition, mechanical properties, and acceptance of austenitic stainless steel forgings and rolled bars for Class 1, Class 2, and Class 3 pressurized water reactors. This document is applicable to austenitic stainless steel forgings and rolled bars for Class 1, Class 2, and Class 3 pressurized water reactors.

Publish Date: 2021-01-07

NB/T 20513.1-2018 Nuclear Power Plant Periodic Safety Review Guidelines - Part 1: General Requirements

Publish Date: 2018-12-10

NB/T 10077-2018 Guidelines for Concrete Dam Construction Using Rock Fill Materials

Publish Date: 2018-10-29

NB/T 42150-2018 Low-voltage surge protector dedicated protection equipment

Publish Date: 2018-04-03

NB/T 20007.49-2018 Pressurized water reactor nuclear power plant - Stainless steel for safety-grade equipment - Part 49: Cold work hardened stainless steel bars for use in safety-grade equipment

This part specifies the requirements for the manufacture, inspection, and acceptance of cold-work hardened stainless steel rods used in fasteners for safety-class equipment in pressurized water reactor nuclear power plants. This part applies to cold-work hardened 06Cr17Ni12Mo2 stainless steel rods used in fasteners for reactor internals and quick disassembly/core measurement sealing assemblies in reactor pressure vessels of pressurized water reactor nuclear power plants.

Publish Date: 2018-03-22

NB/T 20442.12-2017 NB/T 20442.12-2017 Guide for Periodic Safety Review of Nuclear Power Plants Part 12: Design

This section describes the purpose, scope, content, methods, and process of the regular safety review of design elements in nuclear power plants. This section applies to the review of design elements in regular safety reviews of nuclear power plants. The content specified in this section takes pressurized water reactors as an example, and other types of nuclear power plants can refer to and use it accordingly.

Publish Date: 2017-04-01

NB/T 20442.7-2017 Guidelines for Periodic Safety Review of Nuclear Power Plants - Part 7: Feedback on Experience

This section stipulates the review objectives, scope, content, methods, and process of the review of experience feedback elements in regular safety reviews of nuclear power plants. This section applies to the review of experience feedback elements (including the experience feedback management system and the application of other nuclear power plant experiences and research results) in regular safety reviews of nuclear power plants. The content stipulated in this section takes pressurized water reactor nuclear power plants as an example, and other reactor types of nuclear power plants can refer to and use it accordingly.

Publish Date: 2017-04-01

NB/T 20442.6-2017 Guidelines for Periodic Safety Review of Nuclear Power Plants - Part 6: Actual Condition of Buildings, Systems, and Components

This section stipulates the purpose, scope, content, methods, and process of regular safety reviews of the actual condition of nuclear power plant structures, systems, and components. This section applies to the review of the actual condition of structures, systems, and components in regular safety reviews of nuclear power plants. The content stipulated in this section takes pressurized water reactors as an example, and other reactor types can refer to it for use.

Publish Date: 2017-04-01

NB/T 20007.8-2017 Pressurized water reactor nuclear power plant stainless steel - Part 8: Seamless steel pipes for austenitic stainless steels grades 1, 2, and 3

This section specifies the requirements for the manufacture, inspection, and acceptance of Class 1, 2, and 3 austenitic stainless steel seamless steel pipes in pressurized water reactor nuclear power plants. This section applies to Class 1, 2, and 3 equipment and auxiliary pipelines in pressurized water reactor nuclear power plants using austenitic stainless steel seamless steel pipes with a wall thickness of 1 mm to 50 mm. Other nuclear engineering projects can refer to and use it for reference. This section does not apply to heat exchange tubes used in pressurized water reactor nuclear power plants.

Publish Date: 2017-04-01

NB/T 20005.12-2017 Pressurized water nuclear power plant - Carbon steel and low alloy steel for steam systems, main feedwater flow control systems, auxiliary feedwater systems, and steam-turbine bypass systems - Seamless steel pipes and tubing for pressure vessel components used in the main steam system, main feedwater flow control systems, auxiliary feedwater systems, and steam-turbine bypass system of a pressurized water nuclear power plant - Part 12: Seamless steel pipes and tubes for the turbine bypass system. (Note: The text in parentheses is provided for reference only.)

This part specifies the requirements for the manufacture, inspection, and acceptance of P280GH seamless steel pipes used in the main steam system, the main feedwater flow control system, the auxiliary feedwater system, and the turbine bypass system of pressurized water reactor nuclear power plants. This part applies to P280GH hot-worked or cold-worked seamless steel pipes used in the main steam system, the main feedwater flow control system, the auxiliary feedwater system, and the turbine bypass system of pressurized water reactor nuclear power plants. This part does not apply to heat exchange tubes.

Publish Date: 2017-04-01

NB/T 20005.9-2017 Pressurized water nuclear power plant carbon steel and low alloy steel - Part 9: Seamless steel pipes for Classes 2 and 3

This part specifies the requirements for the manufacture, inspection, and acceptance of Class 2 and Class 3 20 carbon steel seamless steel pipes used in pressurized water reactor nuclear power plants. This part applies to Class 2 and Class 3 carbon steel seamless steel pipes with a nominal outer diameter not exceeding 711 mm and a nominal wall thickness not exceeding 60 mm used in pressurized water reactor nuclear power plants. This part does not apply to seamless steel pipes used in the main feedwater flow control system, auxiliary feedwater system, turbine bypass system, and main steam system of pressurized water reactor nuclear power plants. This part does not apply to heat exchanger heat transfer tubes.

Publish Date: 2017-04-01

NB/T 20469-2017 NB/T 20469-2017 Nuclear Power Plant Test Technical Guidelines for Loss of External Power Supply in Pressurized Water Reactors

This standard specifies the test items, test conditions, test content, and acceptance criteria for the loss of off-site power supply tests during the commissioning and start-up phase of pressurized water reactor nuclear power plants. This standard is applicable to the loss of off-site power supply tests in pressurized water reactor nuclear power plants. Nuclear power plants of other reactor types may refer to and use it according to actual circumstances.

Publish Date: 2017-04-01