27.120.10 反应堆工程 标准查询与下载

NB/T 20307-2014 核电厂冷却塔环境影响评价技术规范

本标准规定了核电厂冷却塔环境影响评价应遵循的评价原则、方法和要求。本标准适用于各类新建、扩建内陆及滨海核电厂选址阶段、建造阶段、运行阶段的循环冷却水系统冷却塔环境影响评价相关工作。

Technical code for environmental impact assessment of cooling tower in nuclear power plants

NB/T 20311-2014 压水堆核电厂安全壳喷淋系统设计准则

本标准规定了二代改进型压水堆核电厂安全壳喷淋系统设计的基本要求,包括与该系统设计直接有关的运行、维修和试验要求,但不包括该系统与设备的具体设计要求。本标准适用于二代改进型压水堆核电厂安全壳喷淋系统的设计,其它同类型核电厂可参照执行。

Design criteria for containment spray system of pressurized water reactor nuclear power plants

ASTM E636-14e1 核电反应堆船舶补充监测试验标准指南

1.1 This guide discusses test procedures that can be used in conjunction with, but not as alternatives to, those required by Practices E185 and E2215 for the surveillance of nuclear reactor vessels. The supplemental mechanical property tests outlined permit the acquisition of additional information on radiation-induced changes in mechanical properties of the reactor vessel steels. 1.2 This guide provides recommendations for the preparation of test specimens for irradiation, and identifies special precautions and requirements for reactor surveillance operations and post-irradiation test planning. Guidance on data reduction and computational procedures is also given. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition. 1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels

DIN 25435-1:2014 轻水反应堆初级冷却剂回路元件运行中检查.第1部分:自动超声检查

In-service inspections for primary coolant circuit components of light water reactors - Part 1: Automated ultrasonic testing

DIN 25435-6:2014 轻水反应堆初级冷却剂回路元件运行中检查.第6部分:蒸汽发生器加热管涡流检测

In-service inspections for primary coolant circuit components of light water reactors - Part 6: Eddy current testing of steam generator heating tubes

DIN 25435-2:2014 轻水反应堆初级冷却剂回路元件运行中检查.第2部分:磁粉检验和渗透检验

In-service inspections for primary coolant circuit components of light water reactors - Part 2: Magnetic particle and penetrant testing

DIN 25435-7:2014 轻水反应堆初级冷却剂回路元件运行中检查.第7部分:放射性检测

In-service inspections for primary coolant circuit components of light water reactors - Part 7: Radiographic testing

DIN 25435-4:2014 轻水反应堆初级冷却剂回路元件运行中检查.第4部分:目视检查

In-service inspections for primary collant circuit components of light water reactors - Part 4: Visual testing

NB/T 20225-2013 核电厂安全级电气连接件鉴定

本标准规定了核电厂安全级连接件鉴定的基本要求、指导和方法。本标准适用于和相关电缆或电线相结合,共同形成组件的连接器、终端和密封的鉴定。本标准不适用于安全壳电气贯穿件、在线接头或用于反应堆容器内的电气连接件。本标准不提供环境应力水平和性能要求。

Qualification of class 1E connection assemblies for nuclear power plants

NB/T 20220-2013 轻水冷却反应堆压力容器辐照监督

本标准规定了轻水冷却反应堆压力容器在中子辐照环境下的中子注量计算和测量,以及温度环境监测和铁素体材料力学性能变化监督试验的要求及方法,用以确定反应堆压力容器安全运行的条件,使其在设计寿期内始终保持完整性。本标准适用于设计寿期末反应堆压力容器筒体内表面最大中子注量大于1× 10 n/cm (E>1 MeV)的轻水冷却反应堆压力容器的辐照监督。

Irradiation surveillance of reactor pressure vessels (RPVs) for light-water cooled reactors

NB/T 20227-2013 核电厂安全级成套开关设备鉴定

本标准规定了安装在核电厂反应堆安全壳外的户内安全级成套开关设备鉴定的基本要求和方法。本标准适用于低压金属封闭开关设备、高压金属封闭开关设备。

Qualification of switchgear assemblies for class 1E applications in nuclear power plants

NB/T 20230-2013 压水堆冷却剂压力边界材料断裂韧性要求

本标准规定了压水堆冷却剂压力边界材料的断裂韧性试验要求以及最低断裂韧性要求。本标准适用于压水堆冷却剂压力边界用铁素体钢。本标准不适用于压力边界中的焊接接头及其所用的焊接材料。

Fracture toughness requirements for materials uesd for coolant pressure boundary of pressurized water reactor

GSO ISO 10645:2013 核能 轻水反应堆 核燃料热能衰变的计算

This International Standard provides the basis for calculating the decay heat power of non-recycled nuclear fuel of light water reactors. For this purpose the following components are considered: — the contribution of the fission products from nuclear fission; — the contribution of the actinides; — the contribution of isotopes resulting from neutron capture in fission products. This International Standard applies to light water reactors (pressurized water and boiling water reactors) loaded with a nuclear fuel mixture consisting of 235U and 238U. Its application to recycled nuclear fuel is not permissible. The calculation procedures apply to decay heat periods of 0 and 109 s.

Nuclear energy -- Light water reactors -- Calculation of the decay heat power in nuclear fuels

GSO ISO 10979:2013 核反应堆燃料组件的定义

Specifies requirements for the unique identification. Was developed primarily for commercial light-water reactor fuel, but may be used for any reactor fuel contained in discrete fuel assemblies that can be identified with an identification code. Defines the characters and proposed sequence to be used in assigning identification to the fuel assemblies. The identification is intended to be borne by the fuel assembly throughout its lifetime. Aims at providing an organizing principle for fuel assembly identification systems in order to guarantee unequivocal identification at any time and any place in the world.

Identification of fuel assemblies for nuclear power reactors

ANSI/ANS 6.1.2-2013 核电站核辐射防护和屏蔽计算用的中子和γ射线截面

Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection and Shielding Calculations for Nuclear Power Plants

ANSI/ASME BPVCSection 11-2013 核电站部件的在职检验规则

Rules for Inservice Inspection of Nuclear Power Plant Components

ANSI/ASME BPVCSection 3-2013 核设施元件的建设规则

Rules for Construction of Nuclear Facility Components

ASME STP-PT-064-2013 氢作业用断裂性能试验方法评价

This report evaluates testing methods on the measurement of fracture properties for design of ASME Boiler and Pressure Vessel Code, Section VIII, Division 3 (ASME BPVC VIII-3) pressure vessels for hydrogen service.

EVALUATION OF FRACTURE PROPERTIES TEST METHODS FOR HYDROGEN SERVICE

ASME BPVC Section 3 Appendices-2013 ASME锅炉和压力容器规范.第3节:核设施组件的制造规则.附录

ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Appendices

ASME BPVC Section 3 Division 1 Subsection ND-2013 ASME锅炉和压力容器规范.第3节:核设备组件的制造规则.第1分册:第ND子节.3级:组件

ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection ND - Class 3 Components