17.240;27.120.20 标准查询与下载

ASTM E1819-15 核设施退役环境监控计划的标准指南

5.1 Use of this guide will ensure that the potential impact on the surrounding environment from planned decommissioning activities has been properly assessed. 5.2 Use of this guide will ensure that the adequacy of environmental sampling has been assessed for location, frequency, analytical techniques, and media type to monitor the environment and to detect site-related releases and their impact. 1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.

Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities

IEC 60951-2:2009 核电站.重要安全性仪器仪表.核电厂事故及事故后辐射监测设备.第2部分:废气和通风气体放射能的连续离线监控设备

This part of IEC 60951 provides general guidance on the design principles and performance criteria for equipment for continuous off-line monitoring of radioactivity in gaseous effluents and ventilation air used in nuclear power plants for accident and post-accident conditions. General requirements for technical characteristics@ test procedures@ radiation characteristics@ electrical@ mechanical@ and environmental characteristics are given in IEC 60951-1. These requirements are applicable in this part unless otherwise stated. This standard is applicable to: ? noble gas activity monitors intended to measure the volumetric activity of radioactive noble gases in gaseous effluents at the discharge point and the variation of volumetric activity with time during accident and post-accident conditions. The monitor may also be used for the determination of the total discharge of noble gas activity over a given period; ? noble gas@ aerosol and specific nuclide (commonly iodine@ in its different forms: inorganic iodine@ organic iodine and iodine sticking on dust) monitors intended to measure the volumetric activity in air or gas systems (control room ventilation@ reactor leakage collection@ drywell ventilation exhaust@ fuel handling building ventilation exhaust@ reactor building ventilation purge exhaust) and detect any significant increase of radioactivity during or after an accident. This standard is only applicable to continuous off-line measurement@ i.e. monitors whose detector measures a representative proportion of the main effluent or ventilation stream at some remote location (sampling assembly). It does not apply to monitors with the detector positioned in or adjacent to the effluent or ventilation stream@ which are within the scope of IEC 60951-4. Sample extraction and laboratory analysis@ which are essential to a complete programme of effluent monitoring@ are not within the scope of this standard.

Nuclear power plants - Instrumentation important to safety - Radiation monitoring system for accident and post-accident conditions - Part 2: Equipment for continuous off-line monitoring of radioactivity in gaseous effluents and ventilation air

IEC 60951-1:2009 核电站.重要安全性仪器仪表.事故和事故后环境辐射监控系统.第1部分:一般要求

This part of IEC 60951 provides general guidance on the design principles and performance criteria for equipment to measure radiation and fluid (gaseous effluents or liquids) radioactivity levels at nuclear power plants during and after an accident. This standard is limited to equipment for continuous monitoring of radioactivity in accident and post-accident conditions. The object of this standard is to lay down mandatory general requirements and give examples of acceptable methods for equipment for continuous monitoring of radioactivity within the plant during and after accident conditions in nuclear power plants using light water reactors. It specifies@ for the equipment described above@ the general characteristics@ general test procedures@ radiation@ electrical@ safety and environmental characteristics and the identification and certification of the equipment. If this equipment is part of a centralized system for continuous radiation monitoring in a nuclear facility@ there may be additional requirements from other standards related to this system. Sample extraction and laboratory analysis@ which are essential to a complete programme of effluent monitoring@ are not within the scope of this standard.

Nuclear power plants - Instrumentation important to safety - Radiation monitoring system for accident and post-accident conditions - Part 1: General requirements

IEC 60951-4:2009 核电站.重要安全性仪器仪表.事故及事故后环境的辐射监测.第4部分:流程中放射能的线内或线上监控设备

This part of IEC 60951 provides general guidance on the design principles and performance criteria for equipment for continuous in-line or on-line monitoring of radioactivity in process stream in nuclear power plants for accident and post-accident conditions. General requirements for technical characteristics@ test procedures@ radiation characteristics@ electrical@ mechanical@ and environmental characteristics are given in IEC 60951-1. These requirements are applicable in this part unless otherwise stated. IEC 60951-4 is only applicable to continuous in-line or on-line measurement@ i.e. monitors for which the detector measures radioactivity by being positioned in the process stream (i.e. immerged in) or adjacent to the process stream (i.e. viewing straight through a pipe or tank). It does not apply to monitors for which the detector measures a representative proportion of the stream at some remote location (sampling assembly)@ which are within the scope of IEC 60951-2. IEC 60951-4 is only applicable to monitors for accident and post-accident conditions. Process stream radiation monitoring equipment for normal and incident conditions are within the scope of IEC 60768.

Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post accident conditions - Part 4: Equipment for continuous in-line or on-line monitoring of radioactivity in process streams

BS IEC 60768:2009 核电站.重要安全性仪器装置.正常和事故状态下工艺物料流的放射性的连续网上或在线监控设备

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

GOST 29075-1991 原子能电站用的核仪表制造系统.一般要求

Nuclear instrumentation systems for nuclear power stations. General requirements

ISO 7753:1987 核能 临界探测和报警系统的性能和检验要求

Is applicable to all operations with plutonium, uranium 233, uranium enriched in the 235 isotope, and other fissionable materials. Does not require separate additional instrumentation when the operating instrumentation of the facilities meets its requirements. Is principally concerned with gamma-radiation rate-sensing systems. Annex A refers to the specification of a minimum accident of concern, annex B provides examples of application, and annex C provides guidance for development of emergency plans. Does not include details of administrative steps or specific design and description of instrumentation.

Nuclear energy; Performance and testing requirements for criticality detection and alarm systems

GOST 27452-1987 原子能电站辐射安全的控制装置.一般技术要求

Safety radiation control apparatus for nuclear power stations. General technical requirements

GOST 26344.0-1984 原子能电站用核仪器生产装置.一般规定

Nuclear instrumentation for nuclear power stations. Basic principles

ANSI/IEEE 317:1983 核电站安全壳结构的电气贯穿组件

Prescribes the requirements for the design, construction, qualification, test, and installation of electric penetration assemblies in nuclear containment structures for stationary nuclear power generating stations

Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations