F60 核反应堆综合 标准查询与下载

ANSI/IEEE 344:2004 核电站1E级设备防震鉴定的推荐实施规范

Describes recommended practices for establishing seismic qualification procedures that will yield quantitative data to demonstrate that the Class 1E equipment can meet its performance requirements during and/or following one safe shutdown earthquake (SSE) event preceded by a number of operating basis earthquake (OBE) events.

Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations

NF M60-806-2:2005 核能.环境中放射性的测量.水.第2部分:水中锶90放射性测定.钇90的有机溶剂萃取和β放射性的测量

Nuclear energy - Measurement of radioactivity in the environment - Water - Part 2 : measurement of strontium 90 activity in water - organic solvent extraction of yttrium 90 and measurement of beta activity.

NF M60-806-1:2005 核能.环境中放射性的测量.水.第1部分:水中锶90放射性测定.用硝酸对锶进行放射化学分离和钇90β放射性的测量

Nuclear energy - Measurement of radioactivity in the environment - Water - Part 1 : measurement of strontium 90 activity in water - Radiochemical separation of strontium by nitric acid and measurement of yttrium 90 beta activity.

EJ/T 1014-2005 核反应堆稳态中子反应率分布和反应性的确定

本标准规定了确定核反应堆稳态中子反应率分布和反应性的计算步骤、验证计算系统有效性的方法以及编写报告文件的内容和要求。 本标准适用于压水堆、沸水堆、液态金属堆、重水堆和高温气冷堆的稳态中子反应率分布和反应性的确定。 本标准涉及的内容范围以框图彩式表示在图1中。根据基础实验数据和理论模型计算得到的评价数据系，以及在此基础上制作的应用无关的平均数据系不在本标准范围内。

Determination of steady state neutron reaction rate distributions and reactivity of nuclear reactors

EJ/T 562-2005 核安全有关的操作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有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有关功能(以下简称安全功能)的可信动作应达到的时间要求。 本标准适用于验证操纵员手动动作所需的响应时间，以防止设计基准事件的后果超过设计要求。 本标准适用的范围，仅限于与导致紧急停堆有关、且按规定在安全分析报告(SAR)中经过分析的设计基准事件所涉及的核安全有关的操纵员动作。 本标准不适用于确定操作规程或培训中的操纵员实际动作时间，也不作为操纵员配备和资格审查的依据。

Time response design criteria for safety-related operator actions

ANSI/IEEE 1289:2004 核电站用基于计算机的监测和控制显示器的设计中的人因工程的应用指南

Provides system design considerations, identifies information display and control techniques for use with computer-based displays, and provides human factors engineering guidance for the use of these techniques in nuclear power generating stations.

Guide for the Application of Human Factors Engineering in the Design of Computer-Based Monitoring and Control Displays for Nuclear Power Generating Stations

ASTM C1615-05 高放射性物质工作屏蔽室中远程操作用机械驱动系统的标准指南

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. 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. This standard is intended to be generic and to apply to a wide range of types and configurations of mechanical drive systems.1.1 Intent1.1.1 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 Applicability1.2.1 This standard is intended to be applicable to equipment used under one or more of the following conditions: The materials handled or processed constitute a significant radiation hazard to man or to the environment.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.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. 1.2.2 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 ASTM/IEEE SI-10 Standard for Use of International System of Units. 1.3 User Caveats1.3.1 This standard is not a substitute for applied engineering skills, proven practices and experience. Its purpose is to provide guidance.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. 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 and health practices, and determine the applicability of regulatory limitations prior to use.

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

ASTM D5411-05 反应堆冷却剂中放射性核素混合物每次蜕变的平均能量(E)计算的标准规范

1.1 This practice applies to the calculation of the average energy per disintegration (E) for a mixture of radionuclides in reactor coolant water.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, which 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Practice for Calculation of Average Energy Per Disintegration (E) for a Mixture of Radionuclides in Reactor Coolant

ASTM E2005-05 标准和参考中子场中反应堆剂量测定的基准检测的标准指南

1.1 This guide covers facilities and procedures for benchmarking neutron measurements and calculations. Particular sections of the guide discuss: the use of well-characterized benchmark neutron fields to calibrate integral neutron sensors; the use of certified-neutron-fluence standards to calibrate radiometric counting equipment or to determine interlaboratory measurement consistency; development of special benchmark fields to test neutron transport calculations; use of well-known fission spectra to benchmark spectrum-averaged cross sections; and the use of benchmarked data and calculations to determine the uncertainties in derived neutron dosimetry results.

Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields

ASTM D5163-05a 核电厂运行时使用的I级涂层性能监测程序制定的标准指南

1.1 This guide covers procedures for establishing a program to monitor the performance of Coating Service Level I coating systems in operating nuclear power plants. Monitoring is an on going process of evaluating the condition of the in-service coating systems.1.2 It is the intent of this guide to provide a recommended basis for establishing a coatings monitoring program, not to mandate a singular basis for all programs. Variations or simplifications of the program described in this guide may be appropriate for each operating nuclear power plant depending on their licensing commitments. Similar guidelines are applicable for Coating Service Level III and other areas outside containment.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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Establishing Procedures to Monitor the Performance of Service Level I Coatings in an Operating Nuclear Power Plant

ASTM E2006-05 轻水反应堆计算的基准检测的标准指南

1.1 This guide covers general approaches for benchmarking neutron transport calculations in light water reactor systems. A companion guide (Guide E 706-IIE1) 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 surveillance. Particular sections of the guide discuss: the use of well-characterized 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 reactory fluences with a higher degree of confidence. 1.2 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Benchmark Testing of Light Water Reactor Calculations

BS IEC 60709:2004 核电站.重要的安全仪器和控制系统.隔离

Defines the technical requirements to be met for Isystems important to safety and their cables, in order to achieve adequate physical separation between redundant sections of a system and between a system and another system.

Nuclear power plants - Instrumentation and control systems important to safety - Separation

BS IEC 62241:2004 核电站.主要控制室.警报功能和表示

Provides the functional requirements for the alarm systems in the main control room of nuclear power plants. Establishes the human factors requirements and the design guidelines for alarm presentation for the main control room of nuclear power plants.

Nuclear power plants - Main control room - Alarm functions and presentation

BS IEC 62138:2004 核电站.重要的安全仪器和控制.执行B类或C类功能的基于计算机系统的软件方面

Provides requirements for the software of computer-based Isystems performing functions of safety category B or C as defined by IEC 61226. Complements IEC 60880 and IEC 60880-2, which provide requirements for the software of computer-based Isystems performing functions of safety category A. Is also consistent with, and complementary to, IEC 61513.

Nuclear power plants - Instrumentation and control important for safety - Software aspects for computer-based systems performing category B or C functions

KS C IEC 60951-5:2004 核电站.事故中和事故后辐射情况的监控设备.第5部分:轻水反应堆核电站中空气中的放射性

IEC 60951 시리즈의 규격은 경수형 원자력 발전소에서 사고 상황 동안 또는 후에

Nuclear power plants-Radiation monitoring equipment for accident and post-accident conditions-Part 5:Radioactivity of air in light water nuclear power plants

KS C IEC 61500:2004 核电站.安全控制系统及装置.多道传递的数据传送的功能要求

이 규격은 원자력 발전소에서 범주 A 시스템의 기기 간 또는 범주 A 시스템과 범주 B

Nuclear power plants-Instrumentation and control systems important to safety-Functional requirements for multiplexed data transmission

ISO 17873:2004 核设施.除核反应堆之外的核装置用通风系统的设计和运行标准

This International Standard specifies the applicable requirements concerning the design and use of ventilation systems in nuclear installations such as hot cells, nuclear fuel fabrication and examination laboratories, plutonium-handling facilities, reprocessing plants, enrichment facilities, nuclear-waste treatment stations, storage facilities, etc. The purpose of ventilation and containment systems is to and ensure safety functions and protect workers, public and environment against the spread of radioactive contamination resulting from the operational processes of these installations. This International Standard does not apply to the containment envelope of nuclear power plants and some research reactors where high pressure can occur during accident scenarios. It does apply to auxiliary rooms of these facilities. The requirements for the design and use of ventilation systems that ensure safety functions in nuclear reactors will be developed in another International Standard.

Nuclear facilities - Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors

IEEE 690-2004 核电站1E级线路用电缆系统的设计和安装

Provides direction for the design and installation of safety related electrical cable systems, including associated circuits, in nuclear power generating stations.

Standard for the Design and Installation of Cable Systems for Class 1E Circuits in Nuclear Power Generating Stations

KS C IEC 60557:2004 核反应堆领域的IEC术语

이 규격은 원자력 계측을 다루는 향후 국제(IEC) 규격에 이용되는 용어의 목록을 상세

IEC terminology in the nuclear reactor field

KS C IEC 60744:2004 核电厂的安全逻辑装置.特性和试验方法

이 규격은 보호 계통에서 이용하는 안전 논리 집합체의 시험, 제작 및 설계 원칙을 포함

Safety logic assemblies of nuclear power plants－Characteristics and test methods