27.120.01 核能综合 标准查询与下载

T/CNS 32-2020 高温气冷堆核动力厂乏燃料贮存系统设计准则

本文件规定了球床模块式高温气冷堆核动力厂乏燃料贮存系统设备、构筑物及辅助系统的设计准则。

Design criteria for the spent fuel storage system of high temperature gas cooled reactor nuclear power plant

T/CNS 46-2020 高温气冷堆核动力厂主氦风机设计准则

本文件规定了球床模块式高温气冷堆（简称“高温气冷堆”）核动力厂主氦风机的设计要求。

Design criteria for the helium circulator of high temperature gascooled reactor nuclear power plant

T/CNS 34-2020 高温气冷堆核动力厂氦净化与氦辅助系统设计准则

本文件规定了球床模块式高温气冷堆（以下简称高温气冷堆）核动力厂氦净化与氦辅助系统的设计准则，包括系统范围、系统功能、系统分级、系统组成、主要设备、系统设计要求、机械设计要求、电气设计要求、布置要求、试验和在役检查要求等内容。

Design criteria for the helium purification and helium auxiliary system of high temperature gas cooled reactor nuclear power plant

T/CNS 35-2020 高温气冷堆核动力厂一回路气体采样和分析系统设计准则

本文件规定了球床模块式高温气冷堆（以下简称高温气冷堆）核动力厂一回路气体采样和分析系统的基本设计要求。

Design criteria for the primary circuit gas sampling and analyzing system of high temperature gas-cooled reactor nuclear power plant

DB13/T 5288-2020 核与辐射环境航空监测要求

Nuclear and Radiation Environment Aviation Monitoring Requirements

IEC 63048:2020 核和辐射应用的移动遥控系统.一般要求

Mobile remotely controlled systems for nuclear and radiological applications - General requirements

OVE EN IEC 63047:2020 核仪器仪表用于辐射检测和测量的列表模式数字数据采集的数据格式（英文版）

Nuclear instrumentation - Data format for list mode digital data acquisition used in radiation detection and measurement (english version)

BS EN IEC 63046:2021 核电厂 电力系统 一般要求

Nuclear power plants. Electrical power system. General requirements

T/CSTM 00033-2020 核辐射探测用无机光学单晶术语

本标准规定了核辐射探测用无机光学单晶的术语和定义。 本标准主要适用于核辐射探测用无机光学单晶。

Terms of optical inorganic single crystals for nuclear radiation detection

T/CSTM 00034-2020 硫酸钡基反射层

本标准规定了硫酸钡基反射层的术语和定义、技术要求、检测方法、检验规则、包装、标志、运输和贮存等。 本标准主要适用于闪烁晶体阵列拼装用硫酸钡基反射层。

Barium sulfate based reflection layer

T/CSTM 00032-2020 铈掺杂硅酸钇镥闪烁晶体阵列

本标准规定了铈掺杂硅酸钇镥闪烁晶体阵列的术语和定义、产品标记、技术要求、检测方法、检验规则、包装、标志、运输和贮存等。 本标准适用于X射线、γ射线及带电粒子探测用铈掺杂硅酸钇镥闪烁晶体阵列。

Array of LYSO:Ce scintillation crystal

T/CSTM 00035-2020 铈掺杂硅酸钇闪烁晶体

本标准规定了铈掺杂硅酸钇闪烁晶体的术语和定义、技术要求、检验方法、检验规则、包装、标志、运输和贮存等。 本标准主要适用于在高能物理量能器、核医学成像、安全稽查、工业无损探测领域作为探测材料使用的铈掺杂硅酸钇闪烁晶体产品，其它核辐射探测领域使用的铈掺杂硅酸钇闪烁晶体产品也可参照使用。

Cerium-doped yttrium oxyorthosilicate scintillation crystal

T/CSTM 00036-2020 铈掺杂铝镓酸钆闪烁晶体

本标准规定了铈掺杂铝镓酸钆闪烁晶体的术语定义、产品标记和分类、技术要求、检测方法、检验规则、包装、标志、运输和贮存等。 本标准主要适用于在核医学成像、安全稽查、工业无损探测、中子探测及无中微子双β衰变探测领域作为探测材料使用的铈掺杂铝镓酸钆晶体产品，其它核辐射探测领域使用的铈掺杂铝镓酸钆晶体产品也可参照使用。

Cerium-doped gadolinium aluminum gallium garnet scintillation crystal

T/CEPPEA 5004-2020 《核电厂常规岛施工图设计文件内容深度规定》

本标准为系列标准将由12部分组成：总的部分、热机、电厂化学、电气、仪表与控制、建筑、土建结构、采暖通风与空气调节、水工工艺、水工结构、系统保护与调度自动化、通信部分。 本标准主要对常规岛各专业施工图设计的图纸、说明、计算书等内容、深度和编制方式作出规定。

Regulations on the Depth of Contents in Design Documents of Construction Drawings for Conventional Islands of Nuclear Power Plants

ASTM E2216-02(2020) 核设施退役评估混凝土处置选择标准指南

1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists. 1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1)2 from which the analysis methodology and supporting data are taken. 1.3 Guide E1760 provides a general process for release of materials containing residual amounts of radioactivity. In 1 This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.03 on Radiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components. Current edition approved July 1, 2020. Published July 2020. Originally approved in 2002. Last previous edition approved in 2013 as E2216–02(2013). DOI: 10.1520/E2216-02R20. 2 The boldface numbers in parentheses refer to a list of references at the end of this standard. Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States 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. addition, Guide E1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E1760 and E1278, and provides a more detailed approach for the release of concrete. 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 Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

ASTM C992-20a 池环境中核燃料贮存架用硼基中子吸收材料系统的标准规范

1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system. 1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials. 1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 6 0.2 % by weight (depending upon the geological origin of the boron). Boron enriched in boron-10 could also be used. 1.4 The materials systems described herein shall be functional (that is, always be capable to maintain a boron-10 areal density such that subcriticality is maintained depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool). 1.5 Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations. 1.6 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. 1.7 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 Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment

ISO 12749-1:2020 核能词汇第1部分:通用术语

This document contains the terms, definitions, notes to entry and examples corresponding to the basic concepts of the nuclear energy, nuclear technologies, and radiological protection subject fields. It provides the minimum essential information for each cross-cutting concept represented by a single term. NOTE A full understanding of concepts goes with a background knowledge of nuclear energy, nuclear technologies, and radiological protection. It is intended to facilitate communication and promote common understanding.

Nuclear energy — Vocabulary — Part 1: General terminology

IEC 60050-395:2014/AMD2:2020 修改件2.国际电工词汇（IEV）.第395部分:核仪器.物理现象 基本概念 仪器 系统 设备和探测器

Amendment 2 - International Electrotechnical Vocabulary (IEV) - Part 395: Nuclear instrumentation - Physical phenomena, basic concepts, instruments, systems, equipment and detectors

ISO/TS 23406:2020 核部门.为提供对核安全重要的产品和服务的组织提供质量管理体系审核和认证的机构的要求

Nuclear sector — Requirements for bodies providing audit and certification of quality management systems for organizations supplying products and services important to nuclear safety (ITNS)

ASTM C992-20 池环境中核燃料贮存架用硼基中子吸收材料系统的标准规范

Standard Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment