27.120.10 反应堆工程 标准查询与下载

ASTM E2005-21 标准和参考中子场中反应堆剂量法的基准测试标准指南

1.1?This guide covers facilities and procedures for benchmarking neutron measurements and calculations. Particular sections of the guide discuss: the use of well-characterized benchmark neutron fields to calibrate integral neutron sensors; the use of certified-neutron-fluence st

Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields

ASTM D5144-08(2021) 核电厂保护涂层标准使用标准指南

1.1 This guide provides a common basis on which protective coatings for the surfaces of nuclear power generating facilities may be qualified and selected by reproducible evaluation tests. This guide also provides guidance for application and maintenance of protective coatings. Under the environmental operating and accident conditions of nuclear power generation facilities, encompassing pressurized water reactors (PWRs) and boiling water reactors (BWRs), coating performance may be affected by exposure to any one, all, or a combination of the following conditions: ionizing radiation; contamination by radioactive nuclides and subsequent decontamination processes; chemical and water sprays; hightemperature high-pressure steam; and abrasion or wear. 1.2 The content of this guide includes: Section Referenced Documents 2 Terminology 3 Significance and Use 4 Coating Material Testing 5 Thermal Conductivity 5 Surface Preparation, Coating Application, and Inspection for Shop and Field Work 6 Quality Assurance 7 Keywords 8 1.2.1 In addition, this guide addresses technical topics within ANSI N5.12 and ANSI N101.2 that are covered by separate ASTM standards, for example, surface preparation, (shop and field) and coating application, (shop and field). 1.2.2 Applicable sections of this guide and specific acceptance criteria may be incorporated into specifications and other documents where appropriate.2 1.3 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this standard. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.5 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 Use of Protective Coating Standards in Nuclear Power Plants

ASTM E509/E509M-21 轻水中等核反应堆船舶在役退火标准指南

1.1?This guide covers the general procedures for conducting an in-service thermal anneal of a light-water moderated nuclear reactor vessel and demonstrating the effectiveness of the procedure. The purpose of this in-service annealing (heat treatment) is to improve the mechanical

Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels

T/CNS 31-2020 高温气冷堆核动力厂燃料装卸系统设计准则

本文件规定了球床模块式高温气冷堆（简称高温气冷堆）核动力厂燃料装卸系统设计基本要求。

Design criteria for fuel handling system of high temperature gas cooled reactor nuclear power plant

T/CNS 25-2020 高温气冷堆核动力厂控制棒驱动机构设计准则

本文件规定了球床模式高温气冷堆（简称高温气冷）核动力厂控制棒驱动机构的设计要求。

Design criteria for control rod drive mechanism of high temperature gas cooled reactor nuclear power plant

T/CNS 29-2020 高温气冷堆核动力厂堆芯热工流体设计准则

本文件规定了球床模块式高温气冷堆核动力厂（以下简称高温气冷堆）堆芯热工流体总设计原则、设计基准和设计参数的确定。

Core thermal hydraulic design criteria for high temperature gas cooled reactor nuclear power plant

T/CNS 28-2020 高温气冷堆核动力厂核设计准则

本文件规定了球床模块式高温气冷堆（简称高温气冷堆）核动力厂核设计准则。

Nuclear design criteria for high temperature gas cooled reactor nuclear power plant

T/CNS 33-2020 高温气冷堆核动力厂主蒸汽与主给水系统设计准则

本文件给出了球床模块式高温气冷堆（简称高温气冷堆）核动力厂主蒸汽与主给水系统的系统功能、系统范围、安全等级和抗震类别、性能准则等设计要求。

Design criteria for main steam and feed water system of high temperature gas cooled reactor nuclear power plant

T/CNS 41-2020 高温气冷堆核动力厂仪表系统设计准则

本文件规定了球床模块式高温气冷堆（简称“高温气冷堆”）核动力厂主要物理量仪表系统的设计准则的基本要求。

Design criteria for the instrumentation system of high temperature gas cooled reactor nuclear power plant

T/CNS 26-2020 高温气冷堆核动力厂吸收球系统落球装置设计准则

本文件规定了球床模块式高温气冷堆（简称高温气冷堆）核动力厂吸收球系统落球装置设计、功能、材料及设计验证等方面的基本要求。

Design criteria for sphere discharge equipment of small absorber sphere system of high temperature gas cooled reactor nuclear power plant

T/CNS 24-2020 高温气冷堆核动力厂假想管道破损事故防护设计准则

本文件给出了球床模块式高温气冷堆核动力厂对假想管道破损的潜在不利效应的防护设计要求。

Design criteria for protection against the effects of postulated pipe rupture of high temperature gas cooled reactor nuclear power plant

T/CNS 27-2020 高温气冷堆核动力厂一回路压力泄放系统设计准则

本文件规定了球床模块式高温气冷堆核动力厂一回路压力泄放系统的设计。

Design criteria for primary circuit pressure relief system of high temperature gas cooled reactor nuclear power plant

DIN 25435-1:2020 轻水反应堆主要冷却剂回路组件在役检验指南. 第1部分: 自动超声检测

This document is intended to be applied to in-service inspections using automated ultrasonic testing devices for primary coolant circuit components of light water reactors. It specifies inspection methods, requirements relating to the inspection personnel, the equipment, the prep

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

T/CECPA 001-2020 核电厂配置风险管理技术要求

为保障核电厂的运行安全，防止或减轻可能危及安全的事故后果，核电厂设置了大量的安全系统，以将事故后果限制在可接受的范围内。为保证安全系统的可用性，核电厂营运单位编制了技术规格书，对核电厂配置（即核电厂各安全系统、设备及其必要的支持系统所处的状态）进行管理。技术规格书通常针对各具体系统或设备给出允许的维修时间等限制，但并不能对多重系统或设备失效进行有效管理，从而控制多重系统或设备失效可能导致的核电厂风险增量，尽管有些技术规格书对多重系统或设备失效做了一些规定，但由于核电厂配置组合的复杂性和多样性，这种对风险的控制方式并不完全合理。国际实践表明，对多重设备失效进行控制的有效方法是核电厂的配置风险管理。配置风险管理通常使用风险监测工具来开展，为了使风险评估的结果便于理解，使可接受的和不可接受的风险水平有清楚明确的定义，在建立配置风险管理流程的同时，还需建立一套风险阈值和相应的风险管理矩阵来对不同的风险水平分类并进行分级管理。

Technical Requirement for Configuration Risk Management at Nuclear Power Plants

BS EN IEC/IEEE 60980-344:2021 核设施 对安全至关重要的设备 抗震鉴定

Nuclear facilities. Equipment important to safety. Seismic qualification

UNI ISO 20890-1:2020 轻水反应堆一次冷却剂回路部件在役检查指南 第1部分：机械化超声波检测

Guidelines for in-service inspections for primary coolant circuit components of light water reactors - Part 1: Mechanized ultrasonic testing

UNI ISO 20890-2:2020 轻水反应堆一次冷却剂回路部件在役检查指南 第2部分：磁粉和渗透检测

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

UNI ISO 20890-3:2020 轻水反应堆一次冷却剂回路部件在役检查指南 第3部分：水压试验

Guidelines for in-service inspections for primary coolant circuit components of light water reactors - Part 3: Hydrostatic testing

UNI ISO 20890-4:2020 轻水反应堆一次冷却剂回路部件在役检查导则 第4部分：外观测试

Guidelines for in-service inspections for primary coolant circuit components of light water reactors - Part 4: Visual testing

UNI ISO 20890-5:2020 轻水反应堆一次冷却剂回路部件在役检查导则第5部分：蒸汽发生器加热管的涡流检测

Guidelines for in-service inspections for primary coolant circuit components of light water reactors - Part 5: Eddy current testing of steam generator heating tubes