F82 堆用核仪器 标准查询与下载

NB/T 20055-2011 核电厂安全重要仪表和控制系统执行B类和C类功能的计算机软件

本标准规定了核电厂安全重要仪表和控制(I&C)系统执行B类和C类功能的计算机软件的要求。 本标准适用于核电厂基于计算机的系统的软件生命周期中的每个阶段。

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

ASTM D7013/D7013M-11 核表面量规校准设施装配的标准指南

To establish a proper calibration area for nuclear surface gauges. To reduce the chance of improper calibration. Note 18212;The quality of the results produced by this standard is dependent on the competence of the personnel performing it, and the suitability of the equipment and facilities used. Agencies that meet the criteria of practice D3740 are generally considered capable of competent and objective testing/inspection/etc. Users of this standard are cautioned that compliance with practice D3740 does not in itself assure a means of evaluating some of those factors.1.1 This guide outlines procedures for setup of a nuclear gauge calibration facility in either a shielded bay or an unshielded areaGuide A and Guide B, respectively. 1.2 This guide does not attempt to describe the calibration techniques or methods. It is assumed that this guide will be used by persons familiar with the operations of the gauge and in performing proper calibration, service and maintenance. 1.3 This guide does not attempt to address maintenance or service procedures related to the gauge. 1.4 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. 1.5 This guide 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 guide to establish appropriate safety, and health practices and determine the applicability of regulatory limitations prior to use. 1.6 This guide offers an organized collection of information or a series of options and does not recommend a specific course of action. This document cannot replace education or experience and should be used in conjunction with professional judgment. Not all aspects of this guide may be applicable in all circumstances. This ASTM standard is not intended to represent or replace the standard of care by which the adequacy of a given professional service must be judged, nor should this document be applied without consideration of a project’s many unique aspects. The word “Standard” in the title of this document has been approved through ASTM consensus process. 1.7 All observed and calculated values shall conform to the guidelines for significant digits and rounding established in practice D6026. 1.7.1 The method used to specify how data are collected, calculated, or recorded in this standard is not directly related to the accuracy to which the data can be applied in the design or other uses, or both. How one applies the results obtained using this standard is beyond its scope.

Standard Guide for Calibration Facility Setup for Nuclear Surface Gauges

ASTM E1214-11 反应堆容器监测所用的熔丝温度监测器的使用标准指南,E 706(IIIE)

Temperature monitors are used in surveillance capsules in accordance with Practice E 2215 to verify the estimated value of the surveillance specimen irradiation temperature. Temperature monitors are needed to give evidence of overheating of surveillance specimens beyond the expected temperature. Because overheating causes a reduction in the amount of neutron radiation damage to the surveillance specimens, this overheating could result in a change in the measured properties of the surveillance specimens that would lead to an unconservative prediction of damage to the reactor vessel material. The magnitude of the reduction of radiation damage with overheating depends on the composition of the material and time at temperature. Guide E 900 provides an accepted method for quantifying the temperature effect. Because the evidence from melt wire monitors gives no indication of the duration of overheating above the expected temperature as indicated by melting of the monitor, the significance of overheating events cannot be quantified on the basis of thermal monitors alone. Indication of overheating does serve to alert the user of the data to further evaluate the irradiation temperature exposure history of the surveillance capsule. This guide is IIIE of Master Matrix E 706 that relates several standards used for irradiation surveillance of light water reactor vessel materials. It is intended primarily to amplify the requirements of Practice E 185 in the design of temperature monitors for the surveillance program. It may also be used in conjunction with Practice E 2215 to evaluate the post-irradiation test measurements..1.1 This guide describes the application of melt wire temperature monitors and their use for reactor vessel surveillance of light-water power reactors as called for in Practice E 185.1.2 The purpose of this guide is to recommend the selection and use of the common melt wire technique where the correspondence between melting temperature and composition of different alloys is used as a passive temperature monitor. Guidelines are provided for the selection and calibration of monitor materials; design, fabrication, and assembly of monitor and container; post-irradiation examinations; interpretation of the results; and estimation of uncertainties.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. (See Note 1.)

Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E 706 (IIIE)

DIN EN 60709:2010 核电站.对安全致关重要的测试设备和控制系统.分离(IEC 60709-2004);德文版本EN 60709-2010

Nuclear power plants - Instrumentation and control systems important to safety - Separation (IEC 60709:2004); German version EN 60709:2010

NB/T 20026-2010 核电厂安全重要仪表和控制系统总体要求

本标准适用于新核电厂的I＆C,也适用于已有核电厂的I＆C的升级或改造。 对已有核电厂,仅有一部分要求是适用的,而这部分应在任何项目开始时予以确定。

Nuclear power plants-Instrumentation and control for systems important to safety-General requirements for systems

DIN EN 62138:2010 核电站. 对安全性重要的仪表与控制. 计算机系统B类或C功能软件软件的运行; 德文版本 EN 62138: 2009

This standard provides requirements for the software of computer-based I&C systems supporting functions of safety categories B and C as defined by DIN IEC 61226 (VDE 0491-1). It is not a general-purpose software engineering guide but is aimed to provide requirements that the software of I&C systems of safety classes 2 and 3 must meet to achieve the systems safety objectives. For requirements which are not specific to software the standard refers to DIN IEC 61513 (VDE 0491-2).

Nuclear power plants - Instrumentation and control important for safety - Software aspects for computer-based systems performing category B or C functions (IEC 62138:2004); German version EN 62138:2009

DIN EN 60880:2010 核电站. 对安全性至关重要的仪器仪表和控制系统. 执行A类功能的计算机系统的软件问题（IEC 60880: 2006）; 德文版本EN 60880: 2009

This Standard provides provides requirements for the software of computer-based I&C systems performing category A functions of nuclear power plants as defined by DIN IEC 61226 (VDE 0491-1). Purpose of the requirements is the application of highly reliable software. The standard addresses each stage of software generation and documentation, including requirements specification, design, implementation, verification, validation and operation.

Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions (IEC 60880:2006); German version EN 60880:2009

BS EN 61500:2011 核电站.对安全重要的仪器和控制系统.系统执行A类功能的数据通信

Nuclear power plants. Instrumentation and control important to safety. Data communication in systems performing category A functions

BS EN 60880:2009 核电站.对安全重要的仪器和控制系统.形成A类功能的基于计算机系统的软件问题

This International Standard provides requirements for the software of computer-based I&C systems of nuclear power plants performing functions of safety category A as defined by IEC 61226. According to the definition in IEC 61513, I&C systems of safety class 1 are basically intended to support category A functions, but may also support functions of lower categories. However the system requirements are always determined by the functions of the highest category implemented. For software of I&C system performing only category B and C functions in NPP as defined by IEC 61226, requirements and guidance of IEC 62138 are applicable. This standard provides requirements for the purpose of achieving highly reliable software. It addresses each stage of software generation and documentation, including requirements specification, design, implementation, verification, validation and operation. The principles applied in developing these requirements include: – best available practices; – top-down design methods; – modularity; – verification of each phase; – clear documentation; – auditable documents; – validation testing. Additional guidance and information on how to comply with the requirements of the main part of this standard is given in Annexes A to I.

Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions

IEEE 497-2010 核电站事故监测仪器装置标准

Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations

ASTM E1005-10 反应堆容器监控用辐射测量监控仪应用和分析的标准试验方法E 706(IIIA)

Radiometric monitors shall provide a proven passive dosimetry technique for the determination of neutron fluence rate (flux density), fluence, and spectrum in a diverse variety of neutron fields. These data are required to evaluate and estimate probable long-term radiation-induced damage to nuclear reactor structural materials such as the steel used in reactor pressure vessels and their support structures. A number of radiometric monitors, their corresponding neutron activation reactions, and radioactive reaction products and some of the pertinent nuclear parameters of these RMs and products are listed in Table 1. Table 2 provides data (35) on the cumulative and independent fission yields of the important fission monitors. Not included in these tables are contributions to the yields from photo-fission, which can be especially significant for non-fissile nuclides (23-29, 36-39). 1.1 This method describes general procedures for measuring the specific activities of radioactive nuclides produced in radiometric monitors (RMs) by nuclear reactions induced during surveillance exposures for reactor vessels and support structures. More detailed procedures for individual RMs are provided in separate standards identified in 2.1 and in Refs 11, 24-27. The measurement results can be used to define corresponding neutron induced reaction rates that can in turn be used to characterize the irradiation environment of the reactor vessel and support structure. The principal measurement technique is high resolution gamma-ray spectrometry, although X-ray photon spectrometry and Beta particle counting are used to a lesser degree for specific RMs (1-29). 1.1.1 The measurement procedures include corrections for detector background radiation, random and true coincidence summing losses, differences in geometry between calibration source standards and the RMs, self absorption of radiation by the RM, other absorption effects, radioactive decay corrections, and burn out of the nuclide of interest (1-10, 12-22). 1.1.2 Specific activities are calculated by taking into account the time duration of the count, the elapsed time between start of count and the end of the irradiation, the half life, the mass of the target nuclide in the RM, and the branching intensities of the radiation of interest. Using the appropriate half life and known conditions of the irradiation, the specific activities may be converted into corresponding reaction rates (24-30). 1.1.3 Procedures for calculation of reaction rates from the radioactivity measurements and the irradiation power time history are included. A reaction rate can be converted to neutron fluence rate and fluence using the appropriate integral cross section and effective irradiation time values, and, with other reaction rates can be used to define the neutron spectrum through the use of suitable computer programs (24-30). 1.1.4 The use of benchmark neutron fields for calibration of RMs can reduce significantly or eliminate systematic errors since many parameters, and their respective uncertainties, required for calculation of absolute reaction rates are common to both the benchmark and test measurements and therefore are self canceling. The benchmark equivalent fluence rates, for the environment tested, can be calculated from a direct ratio of the measured saturated activities in the two environments and the certified benchmark fluence rate (24-30). 1.2 This method is intended to be used in conjunction with ASTM Guide E844. The following existing or proposed ASTM practices, guides, and metho......

Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)

KS C IEC 60568:2009 核电站.仪器安全重要性.动力反应堆内中子注量率(通量)测量用堆芯仪表

이 표준은 방호, 정보 또는 제어와 같은 원자로 안전을 목적으로 설계된 온라인 노심 중성자

In-core instrumentation for neutron fluence rate(flux) measurements in power reactor

BS EN 60987:2009 核电厂.对安全重要的仪表和控制.基于计算机的系统硬件设计要求

Nuclear power plants - Instrumentation and control important to safety - Hardware design requirements for computer-based systems

DIN IEC 61772:2009 核电站控制室.视觉显示设备的应用(VDU)(IEC 61772:2009)

Nuclear power plants - Control rooms - Application of Visual Display Unit (VDU) (IEC 61772:2009)

BS IEC 61559-1:2009 核设施中的辐射防护仪器仪表.辐射和/或放射性活度连续监测的中央控制系统.一般要求

Radiation protection instrumentation in nuclear facilities - Centralized systems for continuous monitoring of radiation and/or levels of radioactivity - General requirements

BS IEC 60951-2:2009 核电厂.重要仪器仪表安全性.事故和事后处理的辐射监控.气体排出和流通空气中放射能的连续脱机监控设备

Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Equipment for continuous off-line monitoring of radioactivity in gaseous effluents and ventilation air

BS IEC 60951-4:2009 核电厂.重要安全性仪器仪表.事故和事后状况的辐射监控.过程流中放射能的连续联机或在线监控设备

Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Equipment for continuous in-line or on-line monitoring of radioactivity in process streams

BS IEC 60951-1:2009 核电站.重要安全性仪器仪表.意外事故和事后处理的辐射监控.一般要求

Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - General requirements

BS IEC 60988:2009 核电站.重要安全性仪器仪表.探测松动零件的声音监测系统:性能,设计标准和操作规程

Nuclear power plants - Instrumentation important to safety - Acoustic monitoring systems for detection of loose parts: Characteristics, design criteria and operational procedures

BS IEC 60951-3:2009 核电站.重要安全性仪器仪表.意外事故和事后处理的辐射监控.持续高射程范围γ辐射监测

Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Equipment for continuous high range area gamma monitoring