27.120.10 反应堆工程 标准查询与下载

BS ISO 20890-3:2020 轻水反应堆主冷却剂回路部件在役检查指南-水压试验

What is ISO 20890-3 about?   ISO 12749-3 is the third part of the multi-series European standard that specifies guidelines for in-service system pressure tests of the reactor coolant circuit of light water reactors.   ISO 20890-3 specifies the test technique, the requirements for measuring equipment and additional devices, the preparation and performance of the test as well as the recording and documentation, for the purpose to ensure the reliability and comparability of tests.   Note: Data on (test) pressure, (test) temperature, the scope of testing, rates of change of pressure and temperature, test schedule and inspection intervals can be obtained from the applicable national nuclear codes.  Who is ISO 20890-3 for?   ISO 20890-3 on light water reactors is relevant to:

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

BS ISO 20890-4:2020 轻水堆主冷却剂回路部件在役检查指南 目视测试

What is ISO 20890 ‑ 4 about?   ISO 12749-4 is the fourth part of the multi-series European standard that specifies guidelines for pre-service inspection (PSI) and in-service inspections (ISI) for reactor coolant circuit components of light water reactors and their installations as direct or remote visual testing in the form of a general visual testing (overview), or selective visual testing (specific properties).   ISO 20890 ‑ 4 focuses on the requirement of remote (mechanized) visual testing but also specify global requirements for direct visual testing.    Note: Data concerning the test section, test extent, inspection period, inspection interval and evaluation of indications is defined in the applicable national nuclear safety standards.   Note: ISO 20890 ‑ 4 is not applicable to tests in respect to the general state that are carried out in conjunction with pressure and leak tests and regular plant inspections.

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

BS ISO 20890-2:2020 轻水堆主冷却剂回路部件在役检查指南磁粉和渗透检测

What is ISO 20890 ‑ 2 about?   ISO 20890‑2  is the second part of the multi-series European standard that specifies guidelines for pre-service inspections (PSI) and in-service inspections (ISI) of the surfaces using magnetic particle testing and penetrant testing on components of the reactor coolant circuit of light water reactors. Test systems for the localisation of surface inhomogeneities and requirements for test personnel, test devices, test media, accessories as well as optical auxiliaries, the preparation and implementation of the test, as well as the recording, are defined.   ISO 20890 ‑ 2 guidelines are also applicable to other components of nuclear installations.  NOTE...

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

ISO 20890-3:2020 轻水反应堆主要冷却剂回路部件的在役检查 - 第3部分:静水压试验

This document gives guidelines for in-service system pressure tests of the reactor coolant circuit of light water reactors. This document specifies the test technique, the requirements for measuring equipment and additional devices, the preparation and performance of the test as well as the recording and documentation, for the purpose to ensure the reliability and comparability of tests. NOTE Data on (test) pressure, (test) temperature, scope of testing, rates of change of pressure and temperature, test schedule and inspection intervals can be obtained from the applicable national nuclear codes.

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

ISO 20890-1:2020 轻水堆主冷却剂回路部件在役检验指南第1部分:机械化超声波检验

This document gives guidelines for pre-service-inspections (PSI) and in-service inspections (ISI) with mechanized ultrasonic test (UT) devices on components of the reactor coolant circuit of light water reactors. This document is also applicable on other components of nuclear installations. Mechanized ultrasonic inspections are carried out in order to enable an evaluation in case of — fault indications (e.g. on austenitic weld seams or complex geometry), — indications due to geometry (e.g. in case of root concavity), — complex geometries (e.g. fitting weld seams), or — if a reduction in the radiation exposure of the test personnel can be attained in this way. Ultrasonic test methods are defined for the validation of discontinuities (volume or surface open), requirements for the ultrasonic test equipment, for the preparation of test and device systems, for the implementation of the test and for the recording. This document is applicable for the detection of indications by UT using normal-beam probes and angle- beam probes both in contact technique. It is to be used for UT examination on ferritic and austenitic welds and base material as search techniques and for comparison with acceptance criteria by the national referencing nuclear safety standards. Immersion technique and techniques for sizing are not in the scope of this document and are independent qualified. NOTE Data concerning the test section, test extent, inspection period, inspection interval and evaluation of indications is defined in the applicable national nuclear safety standards. Unless otherwise specified in national nuclear safety standards the minimum requirements of this document are applicable. This document does not define: — extent of examination and scanning plans; — acceptance criteria; — UT techniques for dissimilar metal welds and for sizing (have to be qualified separately); — immersion techniques; — time-of-flight diffraction technique (TOFD). It is recommended that UT examinations are nearly related to the component, the type and size of defects to be considered and are reviewed in specific national inspection qualifications.

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

ISO 20890-5:2020 轻水堆一次冷却剂回路元件在役检验导则第5部分:蒸汽发生器加热管涡流检验

This document gives guidelines for pre-service inspection (PSI) and in-service inspections (ISI) by eddy current tests on non-ferromagnetic steam generator heating tubes of light water reactors, whereby the test is carried out using mechanised test equipment outwards from the tube inner side. An in-service eddy current test of steam generator heating tube plugs as a component of the primary circuit is not an object of this document. Owing to the different embodiments of steam generator heating tube plugs, the use of specially adapted test systems to be qualified is necessary. Test systems for the localisation of inhomogeneities (surface) and requirements for test personnel, test devices, the preparation of test and device systems, the implementation of the testing as well as the recording are defined. NOTE Data concerning the test section, test extent, inspection period, inspection interval and evaluation of indications is defined in the nuclear safety standards. It is recommended that the technical specifications are based on experience on U-tube bends with even bend radius (similar to the S/KWU design). To test other kind of tube bends (e.g. U-tube bends with two 90° bends) further qualifications will be provided.

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

ISO 20890-4:2020 轻水堆一次冷却剂回路部件在役检验指南第4部分:目视检验

This document gives guidelines for pre-service inspection (PSI) and in-service inspections (ISI) for reactor coolant circuit components of light water reactors and their installations as direct or remote visual testing in the form of a — general visual testing (overview), or — selective visual testing (specific properties). This document is also applicable to other components of nuclear installations. The requirements in this document focuses on remote (mechanized) visual testing, but also specifies global requirements for direct visual testing. For specific requirements for direct visual testing of welds see ISO 17637. This document is not applicable to tests in respect to the general state that are carried out in conjunction with pressure and leak tests and regular plant inspections. This document specifies test methods that allow deviations from the expected state to be recognised, requirements for the equipment technology and test personnel, the preparation and performance of the testing as well as the recording. NOTE Data concerning the test section, test extent, inspection period, inspection interval and evaluation of indications is defined in the applicable national nuclear safety standards.

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

ISO 20890-2:2020 轻水堆主冷却剂回路部件在役检验指南第2部分:磁粉和渗透检验

This document gives guidelines for pre-service inspections (PSI) and in-service inspections (ISI) of the surfaces using the magnetic particle testing and penetrant testing on components of the reactor coolant circuit of light water reactors. This document is also applicable to other components of nuclear installations. Test systems for the localisation of surface inhomogeneities and requirements for test personnel, test devices, test media, accessories as well as optical auxiliaries, the preparation and implementation of the test as well as the recording are defined. NOTE 1 Data concerning the test section, test extent, inspection period, inspection interval and evaluation of indications are defined in the applicable national nuclear safety standards. NOTE 2 In general, this document is in accordance with ISO 3452 and ISO 9934 series. This document provides details to be considered in the standard test procedure (see Annex A).

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

ASTM C781-20 气冷核反应堆部件用石墨材料试验的标准实施规程

1.1 This practice covers the application and limitations of test methods for measuring the properties of graphite materials. These properties may be used for the design and evaluation of gas-cooled reactor components. 1.2 The test methods referenced herein are applicable to materials used for replaceable and permanent components as defined in Section 7 and includes fuel elements; removable reflector elements and blocks; permanent side reflector elements and blocks; core support pedestals and elements; control rod, reserve shutdown, and burnable poison compacts; and neutron shield material. Specific aspects with respect to testing of irradiated materials are addressed. 1.3 This practice includes test methods that have been selected from ASTM standards and guides that are specific to the testing of materials listed in 1.2. Comments on individual test methods for graphite components are given in Section 8. The test methods are summarized in Table 1. 1.4 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard. 1.5 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. 1.6 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 Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components

EN ISO 19226:2020 核能. 反应堆容器和内部构件中子注量和每原子位移（DPA）的测定

ISO 19226:2017 provides a procedure for the evaluation of irradiation data in the region between the reactor core and the inside surface of the containment vessel, through the pressure vessel and the reactor cavity, between the ends of active fuel assemblies, given the neutron source in the core. NOTE These irradiation data could be neutron fluence or displacements per atom (dpa), and Helium production. The evaluation employs both neutron flux computations and measurement data from in-vessel and cavity dosimetry, as appropriate. This document applies to pressurized water reactors (PWRs), boiling water reactors (BWRs), and pressurized heavy water reactors (PHWRs). ISO 19226:2017 also provides a procedure for evaluating neutron damage properties at the reactor pressure vessel and internal components of PWRs, BWRs, and PHWRs. Damage properties are focused on atomic displacement damage caused by direct displacements of atoms due to collisions with neutrons and indirect damage caused by gas production, both of which are strongly dependent on the neutron energy spectrum. Therefore, for a given neutron fluence and neutron energy spectrum, calculations of the total accumulated number of atomic displacements are important data to be used for reactor life management.

Nuclear energy - Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals (ISO 19226:2017)

ASTM E636-20 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

DB34/T 3574.8-2019 聚变装置铁磁性系统结构设计准则 第8部分：辐射屏蔽

本部分规定了聚变装置铁磁性系统结构设计辐射屏蔽的术语和定义、总则、设计要求、设计计算与 评估方法。 本部分适用于聚变装置铁磁性系统结构辐射屏蔽设计的所有阶段，是该系统设计的重要依据。

Design guidelines for ferromagnetic system structures of fusion devices Part 8: Radiation shielding

DB34/T 3574.7-2019 聚变装置铁磁性系统结构设计准则 第7部分：制造与检测

本部分规定了聚变装置铁磁性系统制造与检测的术语和定义、基本要求、原则要求、RAMI要求、安 全要求等。 本部分适用于聚变装置铁磁性系统零部件的制造与检测。

Structural Design Criteria for Ferromagnetic Systems of Fusion Devices Part 7: Manufacture and Testing

DB34/T 3574.2-2019 聚变装置铁磁性系统结构设计准则 第2部分：包层系统

本部分规定了聚变装置铁磁性系统中包层系统的术语和定义、系统功能及基本组成、系统设计、工 程设计、RAMI要求和安全要求。 本部分适用于聚变装置铁磁性系统中包层系统设计的所有阶段。

Structural Design Guidelines for Ferromagnetic Systems of Fusion Devices Part 2: Cladding Systems

DB34/T 3574.5-2019 聚变装置铁磁性系统结构设计准则 第5部分：3Sm规则

本部分规定了聚变装置铁磁性系统结构设计 3Sm 规则的术语和定义、基本功能以及判定规则等。 本部分适用于评价聚变装置铁磁性部件在弹性分析时的最大应力是否满足要求。

Structural Design Guidelines for Ferromagnetic Systems of Fusion Devices Part 5: 3Sm Rules

DB34/T 3574.6-2019 聚变装置铁磁性系统结构设计准则 第6部分：疲劳寿命评判方法

本部分规定了聚变装置铁磁性系统结构设计的术语和定义、基本功能、疲劳寿命分析评判方法。 本部分适用于聚变装置磁性系统内部部件第一壁在数值分析时疲劳寿命的计算。

Structural Design Criteria for Ferromagnetic Systems of Fusion Devices Part 6: Evaluation Method of Fatigue Life

DB34/T 3574.3-2019 聚变装置铁磁性系统结构设计准则 第3部分：偏滤器系统

本部分规定了聚变装置铁磁性系统中偏滤器系统的术语和定义、系统功能、基本组成、系统设计、 工程设计、RAMI要求和安全要求。 本部分适用于聚变装置铁磁性系统中偏滤器系统结构设计的所有阶段。

Structural Design Criteria for Ferromagnetic Systems in Fusion Devices Part 3: Divertor Systems

DB34/T 3571-2019 大型超导磁体绝缘层电测试方法

本标准规定了大型超导磁体绝缘层电测试的术语和定义、测试要求、测试内容、数据处理及失效形 式、测试报告等。 本标准适用于大型超导磁体（无线圈盒）在常温、大气、真空等条件下的绝缘测试。

Electrical test method for insulating layer of large superconducting magnet

DB34/T 3573-2019 超导技术低温传输线设计规范

本标准规定了超导技术低温传输线设计的术语和定义、一般要求、结构、材料要求、设计要求。 本标准适用于超导技术低温传输线的设计。

Specifications for design of low temperature transmission lines for superconducting technology

DB34/T 3574.4-2019 聚变装置铁磁性系统结构设计准则 第4部分：管林系统

本部分规定了聚变装置铁磁性系统中管林系统的系统功能及基本组成、系统设计、工程设计、RAMI 要求和安全要求。 本部分适用于聚变装置铁磁性系统中管林系统设计的所有阶段，是该系统设计的重要依据。

Structural Design Criteria for Ferromagnetic Systems of Fusion Devices Part 4: Management System