Z33 放射性物质与放射强度分析测试方法 标准查询与下载

ASTM C1109-98 使用电感耦合等离子-原子发射光谱法对核废料中浸出液分析试验方法

1.1 This test method is applicable to the determination of low concentration and trace elements in aqueous leachate solutions produced by the leaching of nuclear waste materials. 1.2 The nuclear waste material may be a simulated (nonradioactive) solid waste form or an actual solid radioactive waste material. 1.3 The leachate may be deionized water or any natural or simulated leachate solution containing less than 1% total dissolved solids. 1.4 The analysis must be conducted with an inductively coupled plasma-atomic emission spectrometer. 1.5 The values stated in SI units are to be regarded as the standard. 1.6 This standard does not purport to address all of the safety problems, 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 Test Method for Analysis of Aqueous Leachates from Nuclear Waste Materials Using Inductively Coupled Plasma-Atomic Emission Spectrometry

NF X43-326:1997 固定源辐射.PCDDS/PCDFS的质量浓度的测定.第3部分:鉴定和合格评定

Stationary source emissions. Determination of the mass concentration of PCDDs/PCDFs. Part 3 : identification and quantification.

NF X43-325:1997 固定源辐射.PCDDS/PCDFS的质量浓度的测定.第2部分:萃取和提纯

Stationary source emissions. Determination of the mass concentration of PCDDs/PCDFs. Part 2 : extraction and clean-up.

NF X43-324:1997 固定源辐射.PCDDS/PCDFS的质量浓度的测定.第1部分:取样

Stationary source emissions. Determination of the mass concentration of PCDDs/PCDFs. Part 1 : Sampling.

AWS FACT SHEET NO. 2-1997 放射

Radiation

Radiation

ISO 10849:1996 固定源排放 氮氧化物质量浓度的测定 自动监测系统工作特性

Specifies the fundamental structure and the most important performance characteristics of automated measuring systems for oxides of nitrogen to be used on stationary source emissions, for example combustion plants. The procedures to determine the performance characteristics are also specified.

Stationary source emissions - Determination of the mass concentration of nitrogen oxides - Performance characteristics of automated measuring systems

ASTM D5928-96(2010)e1 放射性废弃物筛选的标准试验方法

Most facilities disposing or utilizing waste materials are prohibited from handling wastes that contain radioactive materials. This test method provides the user a rapid method for screening waste material samples in the field or laboratory for the presence or absence of radioactivity at user-established criteria. It is important to these facilities to be able to verify generator-supplied information that radioactive or mixed wastes have not been included in shipments of waste materials.1.1 This test method covers the screening for α–, β–, and γ radiation above ambient background levels or user-defined criteria, or both, in liquid, sludge, or solid waste materials. 1.2 This test method is intended to be a gross screening method for determining the presence or absence of radioactive materials in liquid, sludge, or solid waste materials. It is not intended to replace more sophisticated quantitative analytical techniques, but to provide a method for rapidly screening samples for radioactivity above ambient background levels or user-defined criteria, or both, for facilities prohibited from handling radioactive waste. 1.3 This test method may not be suitable for applications such as site assessments and remediation activities. 1.4 The values stated in SI units are to be regarded as the standard. 1.5 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 Test Method for Screening of Waste for Radioactivity

ASTM E1760-96 含放射性残余物的松散材料的无约束处理的标准导则

1.1 This guide covers the techniques for obtaining approval for release of materials encountered in decontamination and decommissioning (Dand;and;D) from restricted use. It applies to materials that do not meet any of the requirements for regulatory control because of radioactivity content. Figure 1 shows the logic diagram for determining the materials that could be considered for release. Materials that negotiate this logic tree are referred to as "candidate for release based on dose." 1.2 The objective of this guide is to provide a methodology for distinguishing between material that must be carefully isolated to prevent human contact from that that can be recycled or otherwise disposed of. It applies to material in which the radioactivity is dispersed more or less uniformly throughout the volume of the material (termed residual in bulk form) as opposed to surface contaminated objects. 1.3 Surface contaminated objects are materials externally contaminated with radioactive material. Provisions already exist for their release for recycle if it can be shown that they meet applicable federal and state regulations for surface contamination. Regulatory Guide 1.86 and DOE Order 5400.5 specify the upper limits for radioactive surface contamination on material to be released for unrestricted use. 1.4 The release of material containing residual radioactive material (except for 226 Ra) in bulk form (for example, soil or slightly activated metal) is based on the demonstration that the dose to a member of the public will be lower than a specified value (proposed by the petitioner or to be determined by future regulation) for its intended use and lower than a second specified value (also proposed by the petitioner or to be determined by future regulation) via the most restrictive plausible scenario. The first proposed value should be lower than the second since the dose to any member of the public (via the intended use scenario) will almost certainly be realized, whereas the dose from the alternate scenario will only accrue if an unintended (and presumably less probable) circumstance arises. Federal regulation already exists for the release of 226 Ra contaminated soils. 1.5 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 Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity

ASTM E1760-96(2003) 含放射性残余物的松散材料的无约束处理的标准导则

1.1 This guide covers the techniques for obtaining approval for release of materials encountered in decontamination and decommissioning (DD) from restricted use. It applies to materials that do not meet any of the requirements for regulatory control because of radioactivity content. shows the logic diagram for determining the materials that could be considered for release. Materials that negotiate this logic tree are referred to as "candidate for release based on dose."1.2 The objective of this guide is to provide a methodology for distinguishing between material that must be carefully isolated to prevent human contact from that that can be recycled or otherwise disposed of. It applies to material in which the radioactivity is dispersed more or less uniformly throughout the volume of the material (termed residual in bulk form) as opposed to surface contaminated objects.1.3 Surface contaminated objects are materials externally contaminated with radioactive material. Provisions already exist for their release for recycle if it can be shown that they meet applicable federal and state regulations for surface contamination. Regulatory Guide 1.86 and DOE Order 5400.5 specify the upper limits for radioactive surface contamination on material to be released for unrestricted use.1.4 The release of material containing residual radioactive material (except for 226Ra) in bulk form (for example, soil or slightly activated metal) is based on the demonstration that the dose to a member of the public will be lower than a specified value (proposed by the petitioner or to be determined by future regulation) for its intended use and lower than a second specified value (also proposed by the petitioner or to be determined by future regulation) via the most restrictive plausible scenario. The first proposed value should be lower than the second since the dose to any member of the public (via the intended use scenario) will almost certainly be realized, whereas the dose from the alternate scenario will only accrue if an unintended (and presumably less probably) circumstance arises. Federal regulation already exists for the release of 226Ra contaminated soils

Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity

ASTM E1760-96(2003)e1 含放射性残余物的松散材料的无约束处理的标准导则

1.1 This guide covers the techniques for obtaining approval for release of materials encountered in decontamination and decommissioning (DD) from restricted use. It applies to materials that do not meet any of the requirements for regulatory control because of radioactivity content. shows the logic diagram for determining the materials that could be considered for release. Materials that negotiate this logic tree are referred to as "candidate for release based on dose."1.2 The objective of this guide is to provide a methodology for distinguishing between material that must be carefully isolated to prevent human contact from that that can be recycled or otherwise disposed of. It applies to material in which the radioactivity is dispersed more or less uniformly throughout the volume of the material (termed residual in bulk form) as opposed to surface contaminated objects.1.3 Surface contaminated objects are materials externally contaminated with radioactive material. Provisions already exist for their release for recycle if it can be shown that they meet applicable federal and state regulations for surface contamination. Regulatory Guide 1.86 and DOE Order 5400.5 specify the upper limits for radioactive surface contamination on material to be released for unrestricted use.1.4 The release of material containing residual radioactive material (except for 226Ra) in bulk form (for example, soil or slightly activated metal) is based on the demonstration that the dose to a member of the public will be lower than a specified value (proposed by the petitioner or to be determined by future regulation) for its intended use and lower than a second specified value (also proposed by the petitioner or to be determined by future regulation) via the most restrictive plausible scenario. The first proposed value should be lower than the second since the dose to any member of the public (via the intended use scenario) will almost certainly be realized, whereas the dose from the alternate scenario will only accrue if an unintended (and presumably less probably) circumstance arises. Federal regulation already exists for the release of 226Ra contaminated soils

Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity

JIS Z 4507:1995 发射性表面污染的污燃和除污燃指数的测试及计算方法

Testing and calculating methods of contamination and decontamination index of radioactive surface contamination

EJ/T 900-1994 水中总β放射性测定.蒸发法

Determination of total β radioactivity in water Evaporation method

ASTM D5608-94 用于低水平放射性废物场所的现场设备去污染标准规范

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

DIN 6873-5:1993 放射治疗疗程规化系统.稳定性检验

The document describes constancy tests of quality characteristics of computer assisted treatment planning systems. The area of application is distinguished and general comments on the tests are given. Test procedures, test conditions, and test frequencies are given in a table for hardware components (input, output) as well as for software components (basic data, calculated dose values). Test procedures and test conditions are formulated in order to take account of the variety of planning systems.

Radiotherapy treatment planning systems; constancy testing

ISO 9271:1992 放射性污染表面的去污 纺织品去污剂试验方法

Gives definitions. Specifies the principle, the apparatus, the preparation of the test sample, the test agents and procedure, calculation of results, the test report and the consideration of other properties.

Decontamination of radioactively contaminated surfaces; testing of decontamination agents for textiles

NF M60-750:1989 放射性污染的表面去污.检测和评价去污难易程度的方法

Decontamination of radioactively contaminated surfaces. Method for testing and assessing the ease of decontamination.