27.120.01 核能综合 标准查询与下载

T/CIRA 1-2019 γ辐照装置退役规范

本标准除了“前言”和“附录”外，分为10章，即“范围”、“规范性引用文件”、“术语和定义”、“总则”、“退役目标”、“退役准备”、“退役实施”、“退役终态”、“质量保证和文件管理”以及“应急”。 其中，总则明确了γ辐照装置退役的总原则以及辐射防护原则、废物最小化原则、场址开放原则等。 退役目标，主要参考了核安全导则HAD 401/07《γ辐照装置退役》、GB 18871《电离辐射防护与辐射源安全基本标准》、GB 10252《γ辐照装置的辐射防护与安全规范》以及GBZ 167《放射性污染的物料解控和场址开放的基本要求》的内容，并针对60Co、137Cs两种类型的γ辐照装置进行细分。规定了“场址退役目标”、“清洁解控水平”、“个人剂量约束值”等。 退役准备，在参考了核安全导则HAD 401/07《γ辐照装置退役》的内容基础上，结合退役实践，给出了退役需要做的准备工作。提出了“退役资金筹措”、“运行历史资料收集”、“源项调查”、“退役方案编制”、“放射源移送”、 “环境影响评价”等退役准备工作的要求。 退役终态，提出了退役工作实施后项目竣工环境保护验收的要求、步骤和后续手续办理。包括“终态环境保护验收监测报告”、“退役总结报告”的编写，现场验收要求以及“辐射安全许可证注销或变更”手续的办理。 质量保证和文件管理，提出了“文件管理”等。质量保证提出了确保退役顺利实施的保障性措施。 应急，提出了应急预案和应急行动等程序性文件。

Specifications for decommissioning of gamma irradiation facilities

ASTM D8157-19 核电厂I级涂层服务用涂层的评定试验的标准指南

1.1 This guide provides an approach to identifying the need for and development of a test document to qualify coatings for Coating Service Level I (CSLI) service in nuclear power plants. 1.2 It is the intent of this guide to provide a recommended basis for establishing a coatings qualification test document, not to mandate a singular basis for all test documents. Variations or simplifications of the process described in this guide may be appropriate for any given operating or new construction nuclear power plant depending on its licensing commitments. 1.3 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered 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 Qualification Testing of Coatings Used in Coating Service Level I in Nuclear Power Plants

T/ZZB 0910-2018 胶带型辐射交联聚乙烯泡沫塑料

本标准规定了胶带型辐射交联聚乙烯泡沫塑料的术语和定义、基本要求、技术要求、试验方法、检验规则、标志、包装、运输和贮存、质量承诺。 本标准适用于制作泡绵胶带的软质或半硬质辐射交联聚乙烯泡沫塑料。

Radiation crosslinked polyethylene foam for tape

NB/T 20517-2018 核电厂培训领域业绩目标和评估准则

Nuclear power plant training area performance objectives and evaluation criteria

IEC 63047:2018 核仪器辐射探测和测量用列表式数字数据采集的数据格式

This international standard specifies the format of binary list-mode data at the output of digital data acquisition devices used for the detection and measurement of radiation. Such data acquisition devices may employ digital signal processors (DSPs) and field-programmable gate arrays (FPGAs) in combination with memory and a communication interface with a computer. This document is applicable to those data acquisition devices which are able to record and present interaction data of radiation in detectors on an event-per-event basis@ with data stored in an output file or streamed to a remote computer. Such list-mode data typically contains timestamp and energy information@ but may also contain digital signals or properties like rise time or sub-areas of signals computed by the DSP or FPGA from the signal samples. It is not the scope of this document to specify the communication protocol between data acquisition hardware and the instrument drivers. Instead@ it specifies a standard format for the presentation of data acquired by one or more acquisition devices@ to the user or user application. This document only specifies the binary formatting of data. The formatted data may be sent or stored as specified by other protocols. Also@ commands to control data acquisition devices are not included in this document. This document does not put requirements on encryption or authentication of data. However@ data is canonically encoded in the format of this document@ which allows the application of data security algorithms. This document does not replace IEC 62755. This document provides optional mechanisms to include IEC 62755 formatted data into list-mode data. This document does not apply to data acquisition devices used as instrumentation and control systems in nuclear power plants@ nor other safety-critical applications. It is also not intended for medical applications.

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

ASTM C1562-10(2018) 临时核燃料干燥储存系统延长使用材料评估标准指南

1.1 Part of the total inventory of commercial spent nuclear fuel (SNF) is stored in dry cask storage systems (DCSS) under licenses granted by the U.S. Nuclear Regulatory Commission (NRC). The purpose of this guide is to provide information to assist in supporting the renewal of these licenses, safely and without removal of the SNF from its licensed confinement, for periods beyond those governed by the term of the original license. This guide provides information on materials behavior under conditions that may be important to safety evaluations for the extended service of the renewal period. This guide is written for DCSS containing light water reactor (LWR) fuel that is clad in zirconium alloy material and stored in accordance with the Code of Federal Regulations (CFR), at an independent spent-fuel storage installation (ISFSI).2 The components of an ISFSI, addressed in this document, include the commercial SNF, canister, cask, and all parts of the storage installation including the ISFSI pad. The language of this guide is based, in part, on the requirements for a dry SNF storage license that is granted, by the U.S. Nuclear Regulatory Commission (NRC), for up to 20 years. Although government regulations may differ for various nations, the guidance on materials properties and behavior given here is expected to have broad applicability. 1.2 This guide addresses many of the factors affecting the time-dependent behavior of materials under ISFSI service [10 CFR Part 72.42]. These factors are those regarded to be important to performance, in license extension, beyond the currently licensed 20-year period. Examples of these factors are given in this guide and they include materials alterations or environmental conditions for components of an ISFSI system that, over time, could have significance related to safety. For purposes of this guide, a license period of an additional 20 to 80 years is assumed. 1.3 This guide addresses the determination of the conditions of the spent fuel and storage cask materials at the end of the initial 20-year license period as the result of normal events and conditions. However, the guide also addresses the analysis of potential spent fuel and cask materials degradation as the result of off-normal, and accident-level events and conditions that may occur during any period. 1.4 This guide provides information on materials behavior to support continuing compliance with the safety criteria, which are part of the regulatory basis, for licensed storage of SNF at an ISFSI. The safety functions addressed and discussed in this standard guide include thermal performance, radiological protection, confinement, sub-criticality, and retrievability. The regulatory basis includes 10 CFR Part 72 and supporting regulatory guides of the U.S. Nuclear Regulatory Commission. The requirements set forth in these documents indicate that the following items were considered in the original licensing decisions: properties of materials, design considerations for normal and off-normal service, operational and natural events, and the bases for the original calculations. These items may require reconsideration of the safety-related arguments that demonstrate how the systems continue to satisfy the regulatory requirements. Further, to ensure continued safe operation, the performance of materials must be justified in relation to the effects of time, temperature, radiation field, and environmental conditions of normal and off-normal service. Arguments for long-term performance must account for materials alterations (especially degradations) that are expected during the service periods, which include the periods of the initial license and of the license renewal. This guide pertains only to structures, systems, and components important to safety during extended storage period and during retrieval functions, including transport and transfer operations. Materials information that pertains to safety functions, including retrieval functions, is pertinent to current regulations and to license renewal process, and this information is the focus of the guide. This guide is not intended to supplant the existing regulatory process. 1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the 1 This guide is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and High Level Waste. Current edition approved Sept. 1, 2018. Published October 2018. Originally approved in 2003. Last previous edition approved in 2010 as C1562 – 10. DOI: 10.1520/C1562-10R18. 2 In general fuels of higher burnup (>45 MWd/kgU) and MOX fuels are not included in this guide. Guidance for these fuels are expected to be included in an Annex to be written later. 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. 1 Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems

ASTM C1215-18 核工业用试验方法标准中精度和偏差说明的制备和解释的标准指南

1.1 This guide covers terminology useful for the preparation and interpretation of precision and bias statements. This guide does not recommend a specific error model or statistical method. It provides awareness of terminology and approaches and options to use for precision and bias statements. 1.2 In formulating precision and bias statements, it is important to understand the statistical concepts involved and to identify the major sources of variation that affect results. Appendix X1 provides a brief summary of these concepts. 1.3 To illustrate the statistical concepts and to demonstrate some sources of variation, a hypothetical data set has been analyzed in Appendix X2. Reference to this example is made throughout this guide. 1.4 It is difficult and at times impossible to ship nuclear materials for interlaboratory testing. Thus, precision statements for test methods relating to nuclear materials will ordinarily reflect only within-laboratory variation. 1.5 No units are used in this statistical analysis. 1.6 This guide does not involve the use of materials, operations, or equipment and does not address any risk associated. 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 Guide for Preparing and Interpreting Precision and Bias Statements in Test Method Standards Used in the Nuclear Industry

ASTM E1297-18 通过铌放射活性测定快中子反应速率的标准试验方法

1.1 This test method describes procedures for measuring reaction rates by the activation reaction 93 Nb(n,n')93m Nb. 1.2 This activation reaction is useful for monitoring neutrons with energies above approximately 0.5 MeV and for irradiation times up to about 48 years (three half-lives), provided that the analysis methods described in Practice E261 are followed. 1.3 With suitable techniques, fast-neutron reaction rates for neutrons with energy distribution similar to fission neutrons can be determined in fast-neutron fluences above about 1016 cm−2 . In the presence of high thermal-neutron fluence rates (>1012 cm−2 ·s−1 ), the transmutation of 93m Nb due to neutron capture should be investigated. In the presence of high-energy neutron spectra such as are associated with fusion and spallation sources, the transmutation of 93m Nb by reactions such as (n,2n) may occur and should be investigated. 1.4 Procedures for other fast-neutron monitors are referenced in Practice E261. 1.5 Fast-neutron fluence rates can be determined from the reaction rates provided that the appropriate cross section information is available to meet the accuracy requirements. 1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.7 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. 1.8 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 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium

ISO 19443:2018 质量管理体系 - 核能部门供应链中各组织应用ISO 9001和国际原子能机构GS-R要求的具体要求

1   Scope This International Standard specifies requirements for a quality management system when an organization: a) needs to demonstrate its ability to consistently provide products and services that meet customer and applicable statutory and regulatory requirements, and b) aims to enhance customer satisfaction through the effective application of the system, including processes for improvement of the system and the assurance of conformity to customer and applicable statutory and regulatory requirements. All the requirements of this International Standard are generic and are intended to be applicable to any organization, regardless of its type or size, or the products and services it provides. NOTE 1 In this International Standard, the terms “product” or “service” only apply to products and services intended for, or required by, a customer. NOTE 2 Statutory and regulatory requirements can be expressed as legal requirements. This International Standard applies to organizations supplying ITNS products or services. Application of this standard to organizations performing activities on a licensed nuclear site is subject to prior agreement by the Licensee. Requirements specified in this International Standard are complementary (not alternative) to customer and applicable statutory and regulatory requirements. 

Quality management systems — Specific requirements for the application of ISO 9001:2015 by organizations in the supply chain of the nuclear energy sector supplying products and services important to n

T/ZZB 0330-2018 普通型辐射交联聚乙烯泡沫塑料

本标准规定了普通型辐射交联聚乙烯泡沫塑料的术语和定义、基本要求、技术要求、试验方法、检验规则、标志、包装、运输和贮存、质量承诺。 本标准适用于无特殊性能要求（如阻燃、导电等）的软质或半硬质辐射交联聚乙烯泡沫塑料。

Radiation crosslinked ordinary polyethylene foam

DIN 25488:2018 热室用元件.遥控设计的要求

The document is valid for components, i.e. machines, apparatus, devices, remote handling devices and tools, which are used or remote handled in hot cells with lead or concrete shieldings. The document can also be applied to components in other areas of nuclear installations with the necessity for remote handling, such as reactors, fusion reactor power plants and high energy particle accelerators.

Components for hot cells - Requirements on design for remote handling

EJ/T 20149.1-2018 热室设备设计导则 第1部分：通用设计导则

Design Guidelines for Hot Cell Equipment Part 1: General Design Guidelines

GOST R 50.05.02-2018 核能使用符合性评估系统. 测试形式的符合性评估. 统一程序. 焊接接头和覆层表面的超声波检验

Conformity assessment system for the use of nuclear energy. Conformity assessment in the form of examination. Unified procedures. Ultrasonic examination of welded joints and cladded surfaces

GOST R 50.04.01-2018 核能使用符合性评估系统. 测试形式的符合性评估. 资格测试. 一般规定

Conformity assessment system for the use of nuclear energy. Conformity assessment in the form of testing. Qualification testing. General provisions

GOST R 50.05.04-2018 核能使用符合性评估系统. 测试形式的符合性评估. 统一程序. 奥氏体钢焊接接头超声波探伤

Conformity assessment system for the use of nuclear energy. Conformity assessment in the form of examination. Unified procedures. Ultrasonic examination of austenitic steel welded joints

GOST R 50.05.05-2018 核能使用符合性评估系统. 测试形式的符合性评估. 统一程序. 基材(半成品)超声波检验

Conformity assessment system for the use of nuclear energy. Conformity assessment in the form of examination. Unified procedures. Ultrasonic examination of base materials (semi-finished products)

GOST R 50.04.06-2018 核能使用符合性评估系统. 测试形式的符合性评估. 新材料(基础或焊接)的鉴定试验

Conformity assessment system for the use of nuclear energy. Conformity assessment in the form of testing. Qualification testing for new material (base or welding)

GOST R 50.05.03-2018 核能使用符合性评估系统. 测试形式的符合性评估. 统一程序. 单金属, 双金属和耐腐蚀覆层的超声波检查和厚度测量

Conformity assessment system for the use of nuclear energy. Conformity assessment in the form of examination. Unified procedures. Ultrasonic examination and thickness measurement of monometal, bimetal, and corrosion-resistant cladding

GOST R 50.05.06-2018 核能使用符合性评估系统. 测试形式的符合性评估. 统一程序. 磁粉探伤

Conformity assessment system for the use of nuclear energy. Conformity assessment in the form of examination. Unified procedures. Magnetic particles examination

BS IEC 62976:2017 工业无损检测设备 电子线性加速器

Industrial non-destructive testing equipment. Electron linear accelerator