F09 卫生、安全、劳动保护 标准查询与下载

ASTM D7167-05 运行的核电厂中与安全有关的覆层设备III级里衬系统性能监测程序确定用标准指南

Establishment of an in-service linings monitoring program permits planning and prioritization of lining maintenance work as needed to maintain lining integrity and performance in nuclear Coating Service Level III lining systems. For additional information on nuclear maintenance coating work, refer to Manual on Maintenance Coatings for Nuclear Power Plants.7 A linings monitoring program enables early identification and detection of potential problems in lining systems. Some Coating Service Level III lining systems may be known in advance to be suspect, deficient, or degraded. Monitoring lining performance will assist in developing follow-up procedures to resolve any significant deficiency relative to lining work. Degraded linings may generate debris under normal operation and testing or during upset conditions that could adversely affect the performance of the safety-related systems. In most cases, the consequence of the debris generation is flow blockage, essential heat transfer reduction, or both; ultimately leading to degradation of equipment or system performance. A linings monitoring program may be required to fulfill licensing commitments for Coating Service Level III lining work.1.1 This guide covers procedures for establishing a program to monitor the performance of Coating Service Level III lining (and coating) systems in operating nuclear power plants. Monitoring is an ongoing process of evaluating the condition of the in-service lining systems.1.2 Coating Service Level III lining systems subject to this guide are generally those applied to metal substrates comprising raw water or condensate-quality water wetted (that is, full or intermittent immersion) surfaces in systems that include:1.2.1 Service water piping upstream of safety-related components,1.2.2 Service water pump internals (draft tube, volutes, and diffusers),1.2.3 Service water heat exchangers including the channels, pass partitions, tubesheets, end bells, and covers1.2.4 Service water strainers, and1.2.5 Reactor water storage tanks (RWSTs) and refuel cavity water storage tanks.1.3 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 any given operating nuclear power plant depending on its licensing commitments. Similar guidelines may be applicable for certain Coating Service Level II applications such as fluid immersion systems.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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Establishing Procedures to Monitor the Performance of Safety-Related Coating Service Level III Lining Systems in an Operating Nuclear Power Plant

ISO 14943:2004 核燃料技术.核临界安全的相关管理标准

This International Standard provides criteria for the administration of nuclear criticality-safety-related activities for operations which take place outside of reactors and for which there exists a potential for criticality accidents. The responsibilities of management, supervision, and the nuclear criticality-safety staff are addressed. The Objectives and characteristics of operating and emergency procedures are included in this International Standard.

Nuclear fuel technology - Administrative criteria related to nuclear criticality safety

DIN 25475-1:2004 核设施.操作监控.第1部分:松动部件检测用结构噪声监测

Nuclear facilities - Operational monitoring - Part 1: Monitoring of structure-borne sound for loose parts detection

DL/T 833-2003 民用核承压设备焊工资格考核规则

Code for welder qualification of civil nuclear pressure-resistant equipment

DIN 25475-2:2001 核设施.操作监控.第2部分:压水反应堆中初级冷却剂回路振动检测用振动监控

The document contains requirements for the vibration monitoring system, its initial start-up, the monitoring procedure and the documentation.

Nuclear facilities - Operational monitoring - Part 2: Vibration monitoring for early detection of changes in the vibrational behaviour of the primary coolant circuit in pressurized water reactors

DIN 25410:2001 核设施.元件表面清洁度

This document applies to components and systems of nuclear facilities. The surface cleanliness of crucial importance since impurities may lead to malfunction and material damages. For this reason clean condition areas are provided. These clean condition areas are divided into 3 cleanness classes, each of which is designated by its respective graphic symbol. In addition, the document describes the measures to be taken to obtain, maintain or re-establish the surface cleanliness during manufature, transport, installation and initial operation.#,,#

Nuclear facilities - Surface cleanliness of components

DIN 25403-5:2000 处理和搬运核燃料时的临界安全性.第5部分:239二氧化钚-轻水混合物的临界数据

The document specifies requirements relating to criticality safety during the processing and handling of fissile material, in particular criticality data for plutonium dioxid light-water mixtures. The given numerical values and curves shall be used on a isolated system of plutonium dioxide (PuO) homogeniously distributed in light water with the isotope combination 100% Pu 239 and 95% Pu 239/5% Pu 240 with maximum reflection by light water.#,,#

Criticality safety in processing and handling fissile materials - Part 5: Criticality data for plutonium 239 dioxide light-water-mixtures

DIN 25403-3:2000 处理和搬运核燃料时的临界安全性.第3部分:钚239金属-轻水混合物的临界数据

Criticality safety in processing and handling fissile materials - Part 3: Criticality data for plutonium 239 metal light-water-mixtures

DIN 25403-6:2000 处理和搬运核燃料时的临界安全性.第6部分:钚239硝酸盐-轻水混合物的临界数据

Criticality safety in processing and handling fissile materials - Part 6: Criticality data for plutonium 239 nitrate light-water-mixtures

ANSI/ANS 1-2000 临界试验的操作

This standard provides for the safe conduct of critical experiments. Such experiments study neutron behavior in a fission device where the energy produced is insufficient to require auxiliary cooling, and the power history is such that the inventory of long-lived fission products is insignificant.

Conduct of Critical Experiments

ANSI/IEEE 379:2000 核能发电站安全系统单一故障判定准则的标准应用

Covers the application of the single-failure criterion to the electrical power, instrumentation, and control portions of nuclear power generating station safety systems.

Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems

EJ 1076-1998 低、中水平放射性固体废物容器.钢箱

Container for low-and intermediate - level radioactive solid wastes Steel box

EJ/T 1074-1998 核临界安全培训准则

Criteria for nuclear criticality safety training

BS 3598:1998 裂变材料.运输和加工临界安全性.推荐标准

This British Standard applies to all operations with fissile materials outside the core of an operational nuclear reactor and includes the manufacture, processing, handling, storage and movement of fissile materials. It is concerned with the limitations that have to be imposed on nuclear processes and equipment because the materials possess unique nuclear properties which can support nuclear chain reactions. This standard is also applicable to the use of fissile materials in an experimental sub-critical nuclear plantwhere, although the nuclear reactivity approaches the critical state, these materials are not provided with the shielding and control systems associated with a nuclear reactor and which are designed to ensure its safe operation. This standard does not replace any part of the regulations, standards and codes of practice which govern the overall operation of a nuclear process, but supplements them. It states the factors and technical criteria which form the basis on which the procedures relating to criticality safety should be established. It does not cover details of equipment, design or operational procedures, nor does it refer to the effects of ionizing radiations on man or materials or to sources of such radiations, either natural or as a result of nuclear chain reactions. This standard does not apply to fissile materials that are contained within the core of a nuclear reactor, which is governed by appropriate national and international regulations. It is, however, applicable to the process whereby fissile materials are transferred to or from a nuclear reactor or stored near it.

Fissile materials - Criticality safety in handling and processing - Recommendations

ANSI/IEEE 692:1997 核动力发电站安全系统的标准准则

Criteria are provided for the design of an integrated security system for nuclear power generating stations. Requirements are included for the overall system, interfaces, subsystems, and individual electrical and electronic equipment. Addresses equipment for security-related detection, surveillance, access control, communication, and data acquisition.

Standard Criteria for Security Systems for Nuclear Power Generating Stations

ANSI/ANS 8.3-1997 核临界事故报警系统

Applicable to all operations involving fissionable materials in which inadvertent criticality can occur and cause personnel to receive unacceptable exposure to radiation.This standard is not applicable to detection of criticality events where no excessive exposure to personnel is credible, nor to nuclear reactors or critical experiments. This standard does not include details of administrative actions or of emergency response actions that occur after alarm activation.

Criticality Accident Alarm System

ANSI/ANS 8.22-1997 限制和控制慢化剂基础上的核临界安全

This standard applies to limiting and controlling moderators to achieve criticality safety in operations with fissile materials in a moderator control area. This standard does not apply to concentration control of fissile materials.

Nuclear Criticality Safety Based on Limiting and Controlling Moderators

NF M60-302:1996 废物.用γ射线分光光谱法进行无损测量.表征鉴定和检验用封装废物中放射性核素活性的γ射线分光光谱法无损测量

WASTE. NON DESTRUCTIVE MEASUREMENTS BY GAMMA SPECTROMETRY. GAMMA SPECTROMETRY NON DESTRUCTIVE MEASUREMENTS OF THE ACTIVITY OF RADIONUCLIDES IN PACKAGED WASTE FOR CHARACTERIZATION AND INSPECTION PURPOSES.

ISO 12807:1996 放射性物质安全运输包装的泄漏检验

This International Standard describes a method for relating permissible activity release rates of the radioactive contents carried within a containment system to equivalent gas leakage rates under specified test conditions. This approach is called gas leakage test methodology. However, in this International Standard it is recognized that other methodologies might be acceptable. When other methodologies are to be used, it shall be shown that the methodology demonstrates that any release of the radioactive contents will not exceed the regulatory requirements. The use of any alternative methodology shall be by agreement with the competent authority. This International Standard provides both overall and detailed guidance on the complex relationships between an equivalent gas leakage test and a permissible activity release rate. Whereas the overall guidance is universally agreed upon, the use of the detailed guidance shall be agreed upon with the competent authority during the Type B package certification process. It should be noted that, for a given package, demonstration of compliance is not limited to a single methodology. While this International Standard does not require particular gas leakage test procedures, it does present minimum requirements for any test that is to be used. It is the responsibility of the package designer or consignor to estimate or determine the maximum permissible release rate of radioactivity to the environment and to select appropriate leakage test procedures that have adequate sensitivity. This International Standard pertains specifically to Type B packages for which the regulatory containment require-ments are specified explicitly.

Safe transport of radioactive materials - Leakage testing on packages

DL/T 5053-1996 火力发电厂劳动安全和工业卫生设计规程

Design code of labour safety and industrial hygiene for fossil fuel power plants