F79 防护用具与设备 标准查询与下载

KS A ISO 8529-2:2007 参考中子辐射.第2部分:与以辐射场基本量有关的辐射保护装置的校准规则

이 규격은 KS A ISO 8529-1에 설명된 중성자 선원에 대한 출발점으로서 교정 선원

Reference neutron radiations-Part 2:Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field

KS K ISO 8194:2007 辐射防护.辐射污染防护服.设计、选择、检验和使用

이 규격은 고체 입자, 분진, 가스 또는 증기와 같은 액체 또는 고체 물질 또는 대기 오염

Radiation protection-Clothing for protection against radioN contamination-Design, selection, testing and use

JIS Z 4810:2005 放射性污染防护用橡胶手套

この規格は，原子力関連の事業所において使用する放射性汚染防護用ゴム手袋(以下，手袋という。)について規定する。

Protective rubber gloves for radioactive contamination

EJ/T 1175.1-2004 密封箱室部件.第1部分:手套接盘、封袋接盘、手套孔盖、封带孔盖、密封环及可互换件

Components for containment enclosures - Part 1: Glove/bag ports, bungs for glove/bag ports, enclosure rings and interchangeable units

EJ/T 1175.2-2004 密封箱室部件.第2部分:手套、焊封袋、剑式机械手护套及主从机械手护套

Components for containment enclosures - Part 2: Gloves, welded bags, gaiters for remote handling tongs and for manipulators

EJ/T 1175.3-2004 密封箱室部件.第3部分:转运装置-平板门、气闸小室、双盖转运装置、废物桶密封连接机构

Components for containment enclosures - Part 3: Transfer systems such as plain doors, airlock chambers, double door transfer systems, leaktight connections for waste drums

BS ISO 14152:2001 中子辐射防护屏蔽.设计原则和选择适用材料的考虑

This International Standard presents the general methodology governing the design of neutron radiation protection shielding and the choice of neutron radiation protection shielding materials. This International Standard is applicable to facilities and operations where neutron sources are located and used, and where workers are occupationally exposed. These operations and facilities vary considerably in design and purpose. These facilities and operations include, but are not limited to: — nuclear power plants; — research reactors; — particle accelerators and neutron generators; — fusion research facilities; — transportation packaging for radioactive materials operations; — medical treatment and research facilities and applications; — industrial applications such as use of devices for measuring and detecting moisture and density level; — space applications; — calibration facilities; — radiographic installations; — nuclear fuel cycle installations (reprocessing plants, plutonium solution handling facilities, shielded cells, waste storage, etc.). The criteria for the design of neutron shielding and the choice of shielding materials contained in this International Standard should be applied to the design of neutron radiation protection shielding systems in such facilities.

Neutron radiation protection shielding - Design principles and considerations for the choice of appropriate materials

KS A ISO 8529-3:2002 参考中子辐射.第3部分:区域及个人剂量计的校正和对中子能作用及入射角的反应测定

이 규격은 기준 중성자 방사선을 이용한 공간 및 개인 방호기기인 선량률계 및 방호 준위 선

Reference neutron radiations－Calibration of area and personal dosimeters and determination of their response as a function of neutron energy and angle of incidence

KS A ISO 8529-1:2002 基准中子辐射.第1部分:特性和生产方法

이 규격은 방사선 방호 목적으로 사용되는 열중성자에서부터 20 MeV 에너지 범위까지의

Reference neutron radiations-Characteristics and methods of production

ANSI N323D-2002 已安装的辐射防护仪器

Contains requirements for installed radiation protection instrumentation.

Installed Radiation Protection Instrumentation

JIS Z 4808:2002 操作放射性物质搬运用手套箱

この規格は，放射性物質を取扱う事案所において，作業者及び作業環境の保護のために放射件物質の閉じ込めに使用されるグローブボックスについて規定する。

Glove box for handling of radioactive substance

EJ/T 1108-2001 密封箱室设计原则

Design principles for containment enclosures

ASTM D5608-01(2006) 用于低辐射放射性废弃物场所现场设备净化用标准实施规程

The primary objectives of work at low-level radioactive waste sites are the protection of personnel, prevention of the spread of contamination, minimization of additional wastes, protection of sample data quality, and the unconditional release of equipment used. Preventing the contamination of equipment used at low-level radioactive waste sites and the decontamination of contaminated equipment are key aspects of achieving these goals. This practice provides guidance in the planning of work to prevent contamination and when necessary, for the decontamination of equipment that has become contaminated. The benefits include: 5.3.1 Minimizing the spread of contamination within a site and preventing the spread outside of the work area. 5.3.2 Reducing the potential exposure of workers during the work and the subsequent decontamination of equipment. 5.3.3 Minimizing the amounts of additional wastes generated during the work, including liquid, or mixed wastes, including separation of the waste types, such as protective clothing, cleaning equipment, cleaning solutions, and protective wraps and drapes. 5.3.4 Improving the quality of sample data and reliability. This practice may not be applicable to all low-level radioactive waste sites, such as sites containing low-level radioactive wastes mixed with chemical or reactive wastes. Field personnel, with assistance from trained radiological control professionals, should have the flexibility to modify the decontamination procedures with due consideration for the sampling objectives, or if past experience supports alternative procedures for contamination protection or decontamination. This practice does not address the monitoring, protection, or decontamination of personnel working with low-level radioactive wastes. This practice does not address regulatory requirements that may control or restrict work, the need for permits or regulatory approvals, or the accumulation or handling of generated wastes.1.1 This practice covers the decontamination of field equipment used in the sampling of soils, soil gas, sludges, surface water, and ground water at waste sites known or suspected of containing low level radioactive wastes.1.2 This practice is applicable at sites where low level radioactive wastes are known or suspected to exist. This practice may also be applicable for the decontamination of equipment used in known or suspected transuranic, or mixed wastes when used by itself or in conjunction with Practice D 5088.1.3 Procedures are contained in this practice for the decontamination of equipment that comes into contact with the sample matrix (sample contacting equipment), and for ancillary equipment that has not contacted the sample, but may have become contaminated during use (non-contacting equipment).1.4 This practice is applicable to most conventional sampling equipment constructed of metallic and hard, smooth synthetic materials. Materials with rough or porous surfaces, or having a high sorption rate should not be used in radioactive waste sampling due to the difficulties with decontamination.1.5 In those cases where sampling will be periodically performed, such as sampling of wells, consideration should be given to the use of dedicated sampling equipment if legitimate concerns exist for the production of undesirable or unmanageable waste byproducts, or both, during the decontamination of tools and equipment.1.6 This practice does not address regulatory requirements for personnel protection or decontamination, or for the handling, labeling, shipping or storing of wastes, or samples. Specific radiological release requirements and limits must be determined by users in accordance with local, state and federal regulations.1.7 For additional information s......

Standard Practices for Decontamination of Field Equipment Used at Low Level Radioactive Waste Sites

ASTM D5608-01 用于低辐射放射性废弃物场所现场设备净化用标准实施规程

1.1 This practice covers the decontamination of field equipment used in the sampling of soils, soil gas, sludges, surface water, and ground water at waste sites known or suspected of containing low level radioactive wastes. 1.2 This practice is applicable at sites where low level radioactive wastes are known or suspected to exist. This practice may also be applicable for the decontamination of equipment used in known or suspected transuranic, or mixed wastes when used by itself or in conjunction with Practice D5088. 1.3 Procedures are contained in this practice for the decontamination of equipment that comes into contact with the sample matrix (sample contacting equipment), and for ancillary equipment that has not contacted the sample, but may have become contaminated during use (non-contacting equipment). 1.4 This practice is applicable to most conventional sampling equipment constructed of metallic and hard, smooth synthetic materials. Materials with rough or porous surfaces, or having a high sorption rate should not be used in radioactive waste sampling due to the difficulties with decontamination. 1.5 In those cases where sampling will be periodically performed, such as sampling of wells, consideration should be given to the use of dedicated sampling equipment if legitimate concerns exist for the production of undesirable or unmanageable waste byproducts, or both, during the decontamination of tools and equipment. 1.6 This practice does not address regulatory requirements for personnel protection or decontamination, or for the handling, labeling, shipping or storing of wastes, or samples. Specific radiological release requirements and limits must be determined by users in accordance with local, state and federal regulations. 1.7 For additional information see DOE Publication DOE/EH-0256T, DOE Order 5480.5, DOE Order 5480.11, and 10CFR, Part 834. 1.8 The values stated in SI units are to be regarded as the standard. 1.9 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. Specific precautionary statements are given in Section 6.

Standard Practice for Decontamination of Field Equipment Used at Low Level Radioactive Waste Sites

EJ/T 1096-1999 密封箱室密封性分级及其检验方法

Containment enclosures: Classification according to leak tightness and associated checking method

DIN EN 1073-1:1998 放射性污染防护服.第1部分:预防固体颗粒放射性污染的通风防护服的要求和试验方法

The documemt specifies the requirements and test methods for ventilated protective clothing protecting the wearer against particulate radioactive contamination. It does not apply for the protection against ionizing radiation and the protection of patients against contamination with radioactive substances by diagnostical and/or therapeutical measures.

Protective clothing against radioactive contamination - Part 1: Requirements and test methods for ventilated protective clothing against particulate radioactive contamination; German version EN 1073-1:1998

ARMY MIL-R-49421 A NOTICE 1-1997 DT-236()/PDR-75型放射性检测仪

This commercial item description covers brown kraft paper used for general wrapping applications.

RADIAC DETECTOR DT-236( )/PDR-75

IEC 61578:1997 辐射防护仪表 α和/或β气溶胶测量仪用氡补偿效应的校正和检测 试验方法

This International Standard is applicable to type test methods which permit calibration and measurement of the effectiveness of radon daughters' compensation of radioactive aerosol monitors. This standard defines aerosol characteristics used in these tests and applies the following procedures: - test method permitting the measurement of the response of the monitor relative to alpha and/or beta defined radioactive aerosols; - test method permitting the measurement of the response of the monitor relative to radon daughter-defined aerosols; - test method permitting the measurement of the effectiveness of radon compensation; - test method permitting the measurement of the response of the monitor relative to a mixture of aerosols constituted by radon daughters and by alpha and/or beta radioactive emitters. In addition, it specifies the requirements for acceptance.

Radiation protection instrumentation - Calibration and verification of the effectiveness of radon compensation for alpha and/or beta aerosol measuring instruments - Test methods

ISO 10647:1996 辐射防护用中子测量设备的校验和检定曲线程序

This International Standard specifies procedures for the calibration of neutron-measuring devices used for radiation protection purposes, and for determining their response as a function of energy, angle of incidence and dose equivalent rate, using the neutron reference radiations specified in ISO 8529. Since, according to ICRU Report 39 and ICRU Report 43, neutrons of all energies are strongly penetrating, area monitors should be calibrated in terms of ambient dose equivalent [H*(10)}, and individual dosemeters should be calibrated to measure individual dose equivalent, penetrating [Hp(10)]. The procedures given in this International Standard are, however, quite general, and may be used with any system of dose equivalent quantities. A diagrammatic scheme of the physical characteristics to be tested is given as annex A.

Procedures for calibrating and determining the response of neutron-measuring devices used for radiation protection purposes

JIS Z 4810:1995 放射性污染防护橡胶手套

Protective rubber gloves for radioactive contamination