F60 核反应堆综合 标准查询与下载

GB/T 43062-2023 核能 反应堆压力容器和堆内构件中子注量和原子离位次数（dpa）的确定

Determination of neutron fluence and atomic dislocation number (dpa) of nuclear energy reactor pressure vessels and internal components

GB/T 41822-2022 核聚变堆高温承压部件的热氦检漏方法

本文件描述了核聚变堆高温承压部件在处于高温、内部承受高压氦气压强下的氦检漏试验方法。 本文件适用于核聚变堆高温承压部件、聚变堆真空室内部件、真空密封结构件和其他运行在高温环境下部件的密封性试验,以及其他领域高温或高温承压部件的密封性检测。

Hot helium leak test methods for high temperature pressure-bearing components in nuclear fusion reactors

GB/T 39226-2020 磁约束聚变大电流变流系统集成测试要求

本标准规定了磁约束聚变大电流变流系统集成的测试项目、测试条件、测试方法/流程及合格判定准则。 本标准适用于使用晶闸管的大于 10kA 的磁约束聚变大电流变流系统的集成测试。

Requirements on the integrated test for high power converter system of magnetic confinement fusion

BS IEC 61468:2021 核电厂.对安全重要的仪表系统. 堆芯测量仪表. 自给能中子探测器的特性和试验方法

Nuclear power plants. Instrumentation systems important to safety. In-core instrumentation: Characteristics and test methods of self-powered neutron detectors

DIN 25459:2021 核电站用加筋和预应力混凝土外壳

This preliminary standard applies to reinforced and prestressed concrete containment for nuclear power plants. This containment is the structural part of the confinement from the nuclear power plant. The safety function to be fulled by the confinement consists in ensuring that in

Reinforced and prestressed concrete containment for nuclear power plants

ANSI/ANS RA-S-1.4-2021 高级非轻水反应堆核电厂概率风险评估标准

Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants

EJ/T 20228-2018 超导聚变堆低温服役环境下奥氏体不锈钢的焊接工艺评定

Welding procedure qualification of austenitic stainless steel under low temperature service environment of superconducting fusion reactor

DIN 25459 Beiblatt 1:2018 核电站用加筋和预应力混凝土外壳.补充件1:解释

DIN 25459 applies to reinforced and prestressed concrete containment for nuclear power plants. This containment is the structural part of the confinement from the nuclear power plant. The safety function to be fulled by the confinement consists in ensuring that in the load cases specified the leak tightness remains at a level at wich, particulary under incedent conditions, the specified leakage rates are not exceeded. The supplement deals with questions to several clauses of DIN 25459 and gives explanations.

Reinforced and prestressed concrete containment for nuclear power plants; Supplement 1: Explanations

DIN EN 60780-323:2018 核设施.具有安全重要性的电气设备.鉴定(IEC/IEEE 60780-323-2016);德文版本EN 60780-323:2017

This standard represents the best international consensus on the subject of qualification of electrical equipment of safety systems in nuclear power plants. Its application is promoted internationally. In Germany the qualification generally apploes KTA-specifications, but the procedures and requirements described in this standard are also applicable in Germany.

Nuclear facilities - Electrical equipment important to safety - Qualification (IEC/IEEE 60780-323:2016); German version EN 60780-323:2017

BS IEC 61504:2017 核设施. 具有安全重要性的仪表和控制系统. 连续检测辐射和/或放射性水平的中心系统

Nuclear facilities. Instrumentation and control systems important to safety. Centralized systems for continuous monitoring of radiation and/or levels of radioactivity

DIN 25459 Beiblatt 1:2017 核电站用加筋和预应力混凝土外壳.补充件1:解释

DIN 25459 applies to reinforced and prestressed concrete containment for nuclear power plants. This containment is the structural part of the confinement from the nuclear power plant. The safety function to be fulled by the confinement consists in ensuring that in the load cases specified the leak tightness remains at a level at wich, particulary under incedent conditions, the specified leakage rates are not exceeded. The supplement deals with questions to several clauses of DIN 25459 and gives explanations.

Reinforced and prestressed concrete containment for nuclear power plants; Supplement 1: Explanations

ASTM C1615/C1615M-17 热室设施远程操作用机械传动系统的标准指南

4.1 Mechanical drive systems operability and long-term integrity are concerns that should be addressed primarily during the design phase; however, problems identified during fabrication and testing should be resolved and the changes in the design documented. Equipment operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions. 4.2 This standard is intended as a supplement to other standards, and to federal and state regulations, codes, and criteria applicable to the design of equipment intended for this use. 4.3 This standard is intended to be generic and to apply to a wide range of types and configurations of mechanical drive systems. 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 long-term 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 prac......

Standard Guide for Mechanical Drive Systems for Remote Operation in Hot Cell Facilities

IEEE 352-2016 核电站系统和其他核设施可靠性分析的一般原则指南

Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Systems and Other Nuclear Facilities

BS IEC/IEEE 60780-323:2016 核设施. 具有安全重要性的电气设备. 鉴定

Nuclear facilities. Electrical equipment important to safety. Qualification

NB/T 20379-2016 核电厂安全相关的操纵员动作时间响应设计准则

本标准规定了轻水堆核电厂设计中核安全相关的操纵员动作时间响应设计准则，规定了安全分析中操纵员触发和控制核安全功能的可信动作应达到的时间要求。 本标准适用于轻水堆核电厂确定在缓解导致紧急停堆的设计基准事件中所涉及的核安全相关的操纵员动作的最小响应时间间隔。其它堆型可参考使用。

Time response design criteria for safety-related operator actions in nuclear power plants

IEC/IEEE 60780-323:2016 核设施. 具有安全重要性的电气设备. 鉴定

This International Standard describes the basic requirements for qualifying electrical equipment important to safety and interfaces (electrical and mechanical) that are to be used in nuclear facilities. The principles, methods, and procedures described are intended to be used for qualifying equipment, maintaining and extending qualification, and updating qualification, as required, if the equipment is modified. The qualification requirements in this standard, when met, demonstrate and document the ability of equipment to perform safety function(s) under applicable service conditions, including design basis events and certain design extension conditions, and reduce the risk of environmentally induced common-cause equipment failure. This standard does not provide environmental stress levels or performance requirements. Other aspects, relating to quality assurance, selection and use of electronic devices, design and modification of digital systems are not part of this standard. Other IEC or IEEE standards that present qualification programmes for specific equipment, specific environments, or specific parts of the qualification programme may be used to supplement this standard, as applicable. The bibliography lists other standards related to equipment qualification.

Nuclear facilities - Electrical equipment important to safety - Qualification

EJ/T 20131-2016 船用核动力装置屏蔽泵状态监测一般要求

本标准规定了船用核动力装置反应堆冷却剂泵（以下简称屏蔽泵）状态监测的基本要求。 本标准适用于船用核动力装置屏蔽泵的状态监测，包括监测信号、监测系统、监测程序、报警设置、分析与诊断等。

General requirements for condition monitoring of marine nuclear power canned-motor pump

IEEE 383-2015 核电站用电缆质量鉴定和拼接

Qualifying Electric Cables and Splices for Nuclear Facilities

DIN EN 62241:2015 核电站.主要控制室.警报功能和表示(IEC 62241-2004);德文版本EN 62241-2015

Nuclear power plants - Main control room - Alarm functions and presentation (IEC 62241:2004); German version EN 62241:2015

DIN EN 61839:2015 核电厂.控制室的设计.功能分析和测定 (IEC 61839:2000);德文版本EN 61839-2014

Nuclear power plants - Design of control rooms - Functional analysis and assignment (IEC 61839:2000); German version EN 61839:2014