27.120.10 反应堆工程 标准查询与下载

KS C IEC 61224-2022 核反应堆 电阻温度探测器（RTD）的响应时间 原位测量

Nuclear reactors－Response time in resistance temperature detectors(RTD)－In situ measurements

KS C IEC 60231-2022 核反应堆仪表的一般原理

General principles of nuclear reactor instrumentation

KS C IEC 60231A-2022 核反应堆仪表总原理 出版物60231(1967)第一增补

General principal of nuclear reactor instrumentation－First supplement to publication 60231(1967)

KS A ISO 10979-2022 核动力反应堆燃料组件的识别

Identification of fuel assemblies for nuclear power reactors

KS C IEC 60231D-2022 第四补充：压水堆仪表原理

Fourth supplement：Principles of instrumentation for pressurized water reactors

ASTM C1725-17(2022) 热电池专用支持设备和工具的标准指南

1.1 Intent: 1.1.1 This guide presents practices and guidelines for the design and implementation of equipment and tools to assist assembly, disassembly, alignment, fastening, maintenance, or general handling of equipment in a hot cell. Operating in a remote hot cell environment significantly increases the difficulty and time required to perform a task compared to completing a similar task directly by hand. Successful specialized support equipment and tools minimize the required effort, reduce risks, and increase operating efficiencies. 1.2 Applicability: 1.2.1 This guide may apply to the design of specialized support equipment and tools anywhere it is remotely operated, maintained, and viewed through shielding windows or by other remote viewing systems. 1.2.2 Consideration should be given to the need for specialized support equipment and tools early in the design process. 1.2.3 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. 1.3 Caveats: 1.3.1 This guide is generic in nature and addresses a wide range of remote working configurations. Other acceptable and proven international configurations exist and provide options for engineer and designer consideration. Specific designs are not a substitute for applied engineering skills, proven practices, or experience gained in any specific situation. 1.3.2 This guide does not supersede federal or state regulations, or both, or codes applicable to equipment under any conditions. 1.3.3 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 Hot Cell Specialized Support Equipment and Tools

ASTM C1533-15(2022) 热电池设备一般设计考虑的标准指南

1.1 Intent: 1.1.1 The intent of this guide is to provide general design and operating considerations for the safe and dependable operation of remotely operated hot cell equipment. Hot cell equipment is hardware used to handle, process, or analyze nuclear or radioactive material in a shielded room. The equipment is placed behind radiation shield walls and cannot be directly accessed by the operators or by maintenance personnel because of the radiation exposure hazards. Therefore, the equipment is operated remotely, either with or without the aid of viewing. 1.1.2 This guide may apply to equipment in other radioactive remotely operated facilities such as suited entry repair areas, canyons or caves, but does not apply to equipment used in commercial power reactors. 1.1.3 This guide does not apply to equipment used in gloveboxes. 1.2 Applicability: 1.2.1 This guide is intended for persons who are tasked with the planning, design, procurement, fabrication, installation, or testing of equipment used in remote hot cell environments. 1.2.2 The equipment will generally be used over a longterm life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded. 1.2.3 The system of units employed in this standard is the metric unit, also known as SI Units, which are commonly used for International Systems, and defined by IEEE/ASTM SI 10: American National Standard for Use of the International System of Units (SI): The Modern Metric System. 1.3 Caveats: 1.3.1 This guide does not address considerations relating to the design, construction, operation, or safety of hot cells, caves, canyons, or other similar remote facilities. This guide deals only with equipment intended for use in hot cells. 1.3.2 Specific design and operating considerations are found in other ASTM documents. 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 General Design Considerations for Hot Cell Equipment

ASTM C1615/C1615M-17(2022) 热电池设施中远程操作的机械驱动系统的标准指南

1.1 Intent: 1.1.1 The intent of this standard is to provide general guidelines for the design, selection, quality assurance, installation, operation, and maintenance of mechanical drive systems used in remote hot cell environments. The term mechanical drive systems used herein, encompasses all individual components used for imparting motion to equipment systems, subsystems, assemblies, and other components. It also includes complete positioning systems and individual units that provide motive power and any position indicators necessary to monitor the motion. 1.2 Applicability: 1.2.1 This standard is intended to be applicable to equipment used under one or more of the following conditions: 1.2.1.1 The materials handled or processed constitute a significant radiation hazard to man or to the environment. 1.2.1.2 The equipment will generally be used over a longterm life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded. 1.2.1.3 The equipment can neither be accessed directly for purposes of operation or maintenance, nor can the equipment be viewed directly, for example, without radiation shielding windows, periscopes, or a video monitoring system (Guides C1572 and C1661). 1.2.2 The values stated in either SI units or inch-pound units are to be regarded separately as standard. The values stated in each system may not be exact equivalents; therefore, each system shall be used independently of the other. Combining values from the two systems may result in non-conformance with the standard. 1.3 User Caveats: 1.3.1 This standard is not a substitute for applied engineering skills, proven practices and experience. Its purpose is to provide guidance. 1.3.1.1 The guidance set forth in this standard relating to design of equipment is intended only to alert designers and engineers to those features, conditions, and procedures that have been found necessary or highly desirable to the design, selection, operation and maintenance of mechanical drive systems for the subject service conditions. 1.3.1.2 The guidance set forth results from discoveries of conditions, practices, features, or lack of features that were found to be sources of operational or maintenance problems, or causes of failure. 1.3.2 This standard does not supersede federal or state regulations, or both, and codes applicable to equipment under any conditions. 1.3.3 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 Mechanical Drive Systems for Remote Operation in Hot Cell Facilities

BS ISO 10645:2022 核能 轻水反应堆 非回收核燃料中的衰变热能

1   Scope This document provides the basis for calculating the decay heat power of non-recycled nuclear fuel of light water reactors. For this purpose the following components are considered: — the contribution of the fission products from nuclear fission; — the contribution of the actinides; — the contribution of isotopes resulting from neutron capture in fission products. This document applies to light water reactors (pressurized water and boiling water reactors) loaded with a nuclear fuel mixture consisting of 235 U and 238 U. Application of the fission product contribution to decay heat developed using this document to other thermal reactor designs, including heavy water reactors, is permissible provided that the other contributions from actinides and neutron capture are determined for the specific reactor type. Its application to recycled nuclear fuel, like mixed-oxide or reprocessed uranium, is not permissible. The calculation procedures apply to decay heat periods from 0 s to 10 9  s.

Nuclear energy. Light water reactors. Decay heat power in non-recycled nuclear fuels

ISO 23018:2022 核反应堆辐射防护和屏蔽计算的群平均中子和γ射线截面

This document provides guidance in the preparation, verification, and validation of group-averaged neutron and gamma-ray cross sections for the energy range and materials of importance in radiation protection and shielding calculations for nuclear reactors1) , see also Annex A.

Group-averaged neutron and gamma-ray cross sections for radiation protection and shielding calculations for nuclear reactors

ISO 10645:2022 核能.轻水反应堆.非循环核燃料中的衰变热功率

This document provides the basis for calculating the decay heat power of non-recycled nuclear fuel of light water reactors. For this purpose the following components are considered: — the contribution of the fission products from nuclear fission; — the contribution of the actinides; — the contribution of isotopes resulting from neutron capture in fission products. This document applies to light water reactors (pressurized water and boiling water reactors) loaded with a nuclear fuel mixture consisting of 235U and 238U. Application of the fission product contribution to decay heat developed using this document to other thermal reactor designs, including heavy water reactors, is permissible provided that the other contributions from actinides and neutron capture are determined for the specific reactor type. Its application to recycled nuclear fuel, like mixed-oxide or reprocessed uranium, is not permissible. The calculation procedures apply to decay heat periods from 0 s to 109 s.

Nuclear energy — Light water reactors — Decay heat power in non-recycled nuclear fuels

EN ISO 10270:2022 金属和合金的腐蚀.核动力反应堆用锆合金的水溶液腐蚀试验

This document specifies: a) the determination of mass gain; b) the surface inspection of products of zirconium and its alloys when corrosion is tested in water at 360 °C or in steam at or above 400 °C; c) the performance of tests in steam at 10,3 MPa. This document is applicable to wrought products, castings, powder metallurgy products and weld metals. This method has been widely used in the development of new alloys, heat-treating practices and for the evaluation of welding techniques. It is applicable for use in its entirety to the extent specified for a product acceptance test, rather than merely a means of assessing performance in service.

Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors (ISO 10270:2022)

ISO 10270:2022 金属和合金的腐蚀.核电反应堆用锆合金的水腐蚀试验

This document specifies: a) the determination of mass gain; b) the surface inspection of products of zirconium and its alloys when corrosion is tes ted in water at 360 °C or in s team at or above 400 °C; c) the performance of tes ts in s team at 10, 3 MPa. This document is applicable to wrought products, cas tings, powder metallurgy products and weld metals. This method has been widely used in the development of new alloys, heat-treating practices and for the evaluation of welding techniques . It is applicable for use in its entirety to the extent specified for a product acceptance tes t, rather than merely a means of assessing performance in service.

Corrosion of metals and alloys — Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors

ASTM E2006-22 轻水反应堆计算基准测试的标准指南

1.1 This guide covers general approaches for benchmarking neutron transport calculations for pressure vessel surveillance programs in light water reactor systems. A companion guide (Guide E2005) covers use of benchmark fields for testing neutron transport calculations and cross sections in well controlled environments. This guide covers experimental benchmarking of neutron fluence calculations (or calculations of other exposure parameters such as dpa) in more complex geometries relevant to reactor pressure vessel surveillance. Particular sections of the guide discuss: the use of wellcharacterized benchmark neutron fields to provide an indication of the accuracy of the calculational methods and nuclear data when applied to typical cases; and the use of plant specific measurements to indicate bias in individual plant calculations. Use of these two benchmark techniques will serve to limit plant-specific calculational uncertainty, and, when combined with analytical uncertainty estimates for the calculations, will provide uncertainty estimates for reactor fluences with a higher degree of confidence. 1.2 Although this guide and the companion guide, Guide E2005, are focused on power reactors, the principle of this guide is also applicable to non-power light water reactor pressure vessel surveillance programs. 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 Benchmark Testing of Light Water Reactor Calculations

ASTM D7727-21 反应堆冷却剂中放射性氙裂变产物剂量当量氙（DEX）计算的标准实施规程

1.1 This practice applies to the calculation of the dose equivalent to 133 Xe in the reactor coolant of nuclear power reactors resulting from the radioactivity of all noble gas fission products. 1.2 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. 1.3 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 Practice for Calculation of Dose Equivalent Xenon (DEX) for Radioactive Xenon Fission Products in Reactor Coolant

LST 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)

DIN 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）；英文版 EN ISO 18229:2021

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

Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors (ISO 18229:2018); English version EN ISO 18229:2021

UNI EN 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

KS A ISO 10645-2021 核能 轻水堆 核燃料衰变热功率的计算

Nuclear energy－Light water reactors－Calculation of the decay heat power in nuclear fuels

OENORM 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)