27.120.10 反应堆工程 标准查询与下载

ASTM E185-21 轻水慢化核动力反应堆容器监督程序设计的标准实施规程

1.1?This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. New advanced light-water small modular reactor designs

Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

ASTM E900-21 反应堆容器材料中辐射诱导转变温度变化的预测标准指南

1.1?This guide presents a method for predicting values of reference transition temperature shift (TTS) for irradiated pressure vessel materials. The method is based on the TTS exhibited by Charpy V-notch data at 41-J (30-ft��lbf) obtained from surveillance programs conducted in

Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials

SN EN ISO 18229:2021 第四代核反应堆预期的机械部件和金属结构的基本技术要求（ISO 18229:2018）

Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors (ISO 18229:2018)

FprEN ISO 10270:2021 金属和合金的腐蚀 用于核动力反应堆的锆合金的水腐蚀试验（ISO/FDIS 10270:2021）

Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors (ISO/FDIS 10270:2021)

BS EN ISO 18229:2021 第四代核反应堆机械部件和金属结构的基本技术要求

1   Scope This document defines the essential technical requirements that are addressed in the process of design and construction of Generation IV (GEN IV) nuclear reactors. It does not address operation, maintenance and in-service inspection of reactors. Six reactor concepts are considered for GEN IV: the sodium fast reactor, the lead fast reactor, the gas fast reactor, the very high temperature reactor, the supercritical water reactor and the molten salt reactor. Annex A details the main characteristics for the different concepts. The scope of application of this document is limited to mechanical components related to nuclear safety and to the prevention of the release of radioactive materials — that are considered to be important in terms of nuclear safety and operability, — that play a role in ensuring leaktightness, partitioning, guiding, securing and supporting, and — that contain and/or are in contact with fluids (such as vessels, pumps, valves, pipes, bellows, box structures, heat exchangers, handling and driving mechanisms).

Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors

T/CPSS 1004-2021 聚变电源程序编码规范

本文件规定了核聚变电源程序中所涉及的C语言的编码规范，规定了相关的术语和编写C程序时应该遵循的规则。

Specification of Program Coding for Fusion Power Supply

BS ISO 23468:2021 反应堆技术 动力反应堆分析和测量 傅里叶变换红外光谱法测定重水同位素纯度

Reactor technology. Power reactor analyses and measurements. Determination of heavy water isotopic purity by Fourier transform infrared spectroscopy

DS/EN ISO 18229:2021 第四代核反应堆预期的机械部件和金属结构的基本技术要求（ISO 18229:2018）

Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors (ISO 18229:2018)

NF M64-002*NF EN ISO 18229:2021 第四代核反应堆机械部件和金属结构的基本技术要求

Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors

ISO 23468:2021 反应堆技术.动力反应堆分析和测量.用傅里叶变换红外光谱法测定重水同位素纯度

This document specifies an analytical method for determining heavy water isotopic purity by Fourier transform infrared spectroscopy (FTIR). It is applicable to the determination of the whole range of heavy water concentration. The method is devoted to process controls at the different steps of the process systems in heavy water reactor power plant or any other related areas. The method can be applied for heavy water isotopic purity measurements in a heavy water reactor power plant or research reactor, heavy water production factory and heavy water related areas.

Reactor technology - Power reactor analyses and measurements - Determination of heavy water isotopic purity by Fourier transform infrared spectroscopy

EN ISO 18229:2021 第四代核反应堆机械部件和金属结构的基本技术要求

Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors (ISO 18229:2018)

ASTM D8377-21a 熔盐浸渍石墨的高温强度测量标准指南

1.1 This guide covers the best practice for strength measurements at elevated temperature of graphite impregnated with molten salt. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 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. 1.4 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 High Temperature Strength Measurements of Graphite Impregnated with Molten Salt

DIN 25435-2:2021 轻水反应堆主要冷却剂回路组件在役检验指南. 第2部分: 磁性颗粒和渗透剂检测

This document is intended to be applied for in-service inspections of surfaces using the magnetic particle and penetrant method for primary coolant circuit components of light water reactors. It specifies inspection methods, requirements relating to the inspection personnel, the

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

DIN 25435-4:2021 轻水反应堆主要冷却剂回路组件在役检验指南. 第4部分: 外观检测

This document is intended to be applied for in-service inspections of primary coolant circuit components of light water reactors and their internals by visual inspection. It specifies inspection methods, requirements relating to the inspection personnel, the equipment, the prepar

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

DIN 25435-6:2021 轻水反应堆主要冷却剂回路组件在役检验指南. 第6部分: 蒸汽发生器加热管涡流检测

This document is intended to be applied for in-service eddy current inspections of not ferromagnetic steam generator heating tubes of pressurized water reactors. It specifies inspection methods, requirements relating to the inspection personnel, the equipment, the preparation and

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

DS/EN IEC/IEEE 60980-344:2021 核设施“安全重要设备”抗震鉴定

Nuclear facilities – Equipment important to safety – Seismic qualification

DS/ISO 18229:2021 第四代核反应堆预期机械部件和金属结构的基本技术要求

Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors

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

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