F70 辐射防护与监测综合 标准查询与下载

BS ISO 3925:2014 非密封放射性物质.鉴别和证书

Unsealed radioactive substances. Identification and documentation

ASTM E636-14 核动力反应堆容器补充监测试验的标准实施指南, E706 40;IH41;

3.1 Practices E185 and E2215 describe a minimum program for the surveillance of reactor vessel materials, specifically mechanical property changes that occur in service. This guide may be applied in order to generate additional information on radiation-induced property changes to better assist the determination of the optimum reactor vessel operation schemes. 1.1 This guide discusses test procedures that can be used in conjunction with, but not as alternatives to, those required by Practices E185 and E2215 for the surveillance of nuclear reactor vessels. The supplemental mechanical property tests outlined permit the acquisition of additional information on radiation-induced changes in mechanical properties of the reactor vessel steels. 1.2 This guide provides recommendations for the preparation of test specimens for irradiation, and identifies special precautions and requirements for reactor surveillance operations and post-irradiation test planning. Guidance on data reduction and computational procedures is also given. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition. 1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E?706 40;IH41;

NF M60-444*NF ISO 16117:2013 核临界安全性.公设危险程度事故裂变数估计

Nuclear criticality safety - Estimation of the number of fissions of a postulated criticality accident

BS ISO 16117:2013 核临界安全. 假想临界事故的裂变数评估

Nuclear criticality safety. Estimation of the number of fissions of a postulated criticality accident

NF M60-526-1:2013 辐射防护.电离辐射可追溯性剂量的电子顺磁共振(EPR)光谱的最低标准.第1部分:通则

Radiological protection - Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation - Part 1: general principles

DIN 6802-6:2013 中子剂量学. 第6部分: 采用电离室对吸收剂量的测定方法

Neutron dosimetry.Part 6: Methods for determination of absorbed dose using ionisation chambers

ASTM E1475-13 数字放射性检查数据的计算机化传输数据域的标准指南

0

Standard Guide for Data Fields for Computerized Transfer of Digital Radiological Examination Data

KS A ISO 12790-1:2012 辐射防护.放射生物分析行为准则.第1部分:通用原则

이 표준은 방사선 생체분석 실험실의 품질보증 및 품질 관리, 성능평가 그리고 인증에 대한

Radiation protection-Performance criteria for radiobioassay-Part 1:General principles

KS A ISO 15382:2012 核能.放射线防护.核设备中弱贯穿放射线(特别β线)的外照射防护监视程序

이 표준은 원자력 시설에서 약투과성 방사선, 특히 베타 방사선, 외부 피폭에 대한 방사선

Nuclear energy-Radiation protection-Procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation

DIN 25415:2012 放射性污染表面.清除污染的解除检验和评价方法

Radioactively contaminated surfaces - Method for testing and assessing the ease of decontamination

NB/T 20137-2012 核电厂工作人员辐射防护培训规定

本标准规定了核电厂辐射工作人员、辐射防护人员、管理人员辐射防护培训的基本原则和要求。 其他反应堆设施工作人员辐射防护培训可参考本标准执行。

Regulation for staff training of radiation protection in nuclear power plants

NB/T 20130-2012 混凝土辐射屏蔽

本标准规定了用于辐射屏蔽目的的混凝土的辐射屏蔽设计、选材、建造等的特征要求。 本标准适用于放射性的实验室、放射化学站、试验装置，核电厂用于辐射屏蔽目的的混凝土。

Concrete radiation shielding

NB/T 20138-2012 核电厂个人和工作场所辐射监测

本标准规定了核电厂工作人员个人监测和工作场所辐射监测的要求，包括监测内容、监测要求、监测方法和监测结果的解释、质量保证和记录保存要求。 本标准适用于核电厂正常运行及检修时的工作人员和工作场所辐射监测。 核电厂以外的其它核反应堆运行单位可参照执行。

Individual monitoring and workplace monitoring of nuclear power plant

ISO 11320:2011 核临界安全性.应急准备状态和响应

This International Standard provides criteria for emergency preparedness and response to minimize consequences due to a nuclear criticality accident. The criticality safety of operations are evaluated in accordance with ISO 1709. This International Standard applies to a site with one or more facilities which might contain significant quantities and concentrations of fissile material. The extent to which this International Standard needs to be applied depends on the overall criticality risk presented by the facilities at the site. This International Standard does not apply to off-site transport and transit storage of packages with fissile material. This International Standard does not apply to sites with operating nuclear power plants or to facilities with research reactors which are licensed to become critical or near-critical, provided that there are no operations with fissile material external to the reactor for which a credible criticality accident risk exists. This International Standard can be applied to such sites and facilities in specific cases, if supported by site management and by licensing authorities.

Nuclear criticality safety - Emergency preparedness and response

JIS Z 4501:2011 X-射线防护装置的铅当量试验方法

Testing method of lead equivalent for X-ray protective devices

ANSI N13.30-2011 放射生物测定性能标准

This standard provides criteria for radiobioassay service laboratory quality assurance, performance evaluation, and accreditation. Criteria are included for determining bias, precision, and the minimum detectable amount of a measurement procedure. Technical standards for a performance testing program are provided. This standard provides useful and practical informatioin and guidance for users, providers, and regualators of radiobioassay services.

Performance Criteria of Radiobioassay

ANSI N2.1-2011 辐射符号

This standard is a revision of the old standard that was withdrawn in 1999. It provides guidance on the appropriate usage of the radiation symbol and the size, shape and color of the radiation symbol.

Radiation Symbol

BS IEC 60737:2010 核电站.重要安全性温度传感器的仪器仪表(炉内和主冷却剂回路).试验方法和特征

Nuclear power plants - Instrumentation important to safety Temperature sensors (in-core and primary coolant circuit) - Characteristics and test methods

ASTM C1572-10 远程操作设备的干铅玻璃和充油铅玻璃辐射屏蔽窗设备标准指南

Radiation Shielding Window Components: Radiation shielding window components operability and long-term integrity are concerns that originate during the design and fabrication sequences. Such concerns can only be addressed, or are most efficiently addressed, during one or the other of these stages. The 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 radiation shielding window components.1.1 Intent: 1.1.1 The intent of this standard is to provide guidance for the design, fabrication, quality assurance, inspection, testing, packaging, shipping, installation, and maintenance of radiation shielding window components. These window components include wall liner embedments, dry lead glass radiation shielding window assemblies, oil-filled lead glass radiation shielding window assemblies, shielding wall plugs, barrier shields, view ports, and the installation/extraction table/device required for the installation and removal of the window components. 1.2 Applicability: 1.2.1 This standard is intended for those persons who are tasked with the planning, design, procurement, fabrication, installation, and operation of the radiation shielding window components that may be used in the operation of hot cells, high level caves, mini-cells, canyon facilities, and very high level radiation areas. 1.2.2 This standard applies to radiation shielding window assemblies used in normal concrete walls, high-density concrete walls, steel walls and lead walls. 1.2.3 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 Standard for Use of International System of Units. Common nomenclature for specifying some terms; specifically shielding, uses a combination of metric units and inch-pound units.

Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities

BS ISO 27467:2009 核临界安全.假定危险事件的分析

Nuclear criticality safety - Analysis of a postulated criticality accident