Z33 放射性物质与放射强度分析测试方法 标准查询与下载

ISO 18589-6:2009 环境中放射性的测量.土壤.第6部分:总α和总β活性的测量

Measurement of radioactivity in the environment - Soil - Part 6: Measurement of gross alpha and gross beta activities

ASTM E1760-09 含放射性残余物的松散材料的无约束处理的标准指南

Materials encountered during D&D may contain residual radioactivity varying in amounts from that in irradiated fuel to barely detectable quantities in or on building materials. It is clear that highly radioactive materials have to be disposed as radioactive waste pursuant to 10 CFR 60 and 10 CFR 61. Conversely, it is not reasonable to expend a disproportionate amount of resources to isolate materials that contain minute quantities of radioactive materials that will not cause even statistically measurable health effects. This guide provides a rationale and methodology for distinguishing between materials that contain sufficient radioactivity to warrant isolation of some type (storage awaiting decay, near-surface disposal, disposal with intruder protection, or placement in a deep repository) from materials with insignificant radioactive content. Materials with insignificant radioactive content can be recycled in the economy or disposed of in conventional (landfill) facilities without adverse health effects. Materials that meet the criteria identified in this guide are not simply excluded from regulation because they do not fall precisely in the regulatory scope. They are sufficiently free of radioactive material so that no further efforts at control are justified for radiation protection purposes. Therefore, the release of materials for unrestricted use in accordance with this guide meets the criteria for being an “as low as reasonably achievable” (ALARA) activity. For the purpose of this guide, the return of materials containing residual radioactivity to society without regulatory restrictions is referred to as “unrestricted release based on the absence of the credible potential for adverse health effects.” This guide asserts that materials recycled this way will have no statistically measurable health effects regardless of use. It does not guarantee that the materials are suitable for use in every possible application, for example, trace amounts of radionuclides in materials may not be acceptable for certain photographic and electronic applications. This guide also asserts that the owner of the materials is responsible for ensuring that society''s criteria for “no measurable health effects” is met before release, and that the responsibility for providing materials with the purity required for a special application rests not with the owner, but with the developer of that application.1.1 This guide covers the techniques for obtaining approval for release of materials encountered in decontamination and decommissioning (D&D) from restricted use. This would be addressed in the decommissioning plan (E 1281). It applies to materials that do not meet any of the requirements for regulatory control because of radioactivity content. Fig. 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. Provisio......

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

KS I ISO 10849:2008 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

이 표준은 소각 시설과 같은 고정 오염원에서 배출되는 질소 산화물에 대한 자동 측정 시스템

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

JIS K 0311 AMD 1:2008 固定辐射源中4至8-氯代二苯并-对二氧芑、4至8-氯代二苯并呋喃和类二氧芑的多氯联苯并含量的测定方法(修改件1)

This translation has been made based on the original Japanese Industrial Standard revised by the Minister of Economy, Trade and Industry through deliberations at the ,Japanese Industrial Standards Committee in accordance with the Industrial Standardization Law. Consequently, JlS K 0311:2005 is partially replaced with this Amendment.

Method for determination of tetra-through octachlorodibenzo-p-dioxins, tetra-through octachlorodibenzofurans and dioxin-like polychlorinatedbiphenyls in stationary source emissions (Amendment 1)

DIN 25457-7:2008 放射性废料和核设备部件的释放用放射性测量方法.第7部分:(核)场

Activity measurement methods for the release of radioactive waste materials and nuclear facility components - Part 7: (Nuclear) sites

EJ/T 1204.2-2006 电离辐射测量探测限和判断阈的确定 第2部分:考虑样品处理影响的计数测量

本部分使用统计学方法规定了两个表征着给定错误概率的统计值，用以评估考虑、样品处理影响的电离辐射测量中的探测能力。 本部分适用于考虑样品处理影响的计数测量。

Determination of the detection limit and decision threshold for ionizing radiation measurements Part 2: Counting measurements with allowance for the influence of sample treatment

EJ/T 1204.3-2006 电离辐射测量探测限和判断阈的确定 第3部分:忽略样品处理影响的高分辨率γ能谱法计数测量

本部分规定了两个表征给定错误概率的统计值，用以在不考虑样品处理的影响的情况下，利用高分辨率γ能谱法进行电离辐射测量中，对探测能力进行评估。 本部分适用于利用高分辨率γ能谱进行计数测量时探测限和判断阙的确定。

Determination of the detection limit and decision threshold for ionizing radiation measurements Part 3: Counting measurements by high resolution gamma spectrometry, neglecting the influence of sample treatment

EJ/T 1204.4-2006 电离辐射测量探测限和判断阈的确定 第4部分:忽略样品处理影响的线性标度模拟率表测

本部分规定了适当的统计值，用以评估在忽略样品处理影响、使用线性标度的模拟率表进行电离辐射测量的探测能力。为此使用统计学方法规定了两个表征着给定错误概率的统计值。 本部分适用于线性标度的模拟脉冲计数率的测量。

Determination of the detection limit and decision threshold for ionizing radiation measurements Part 4: Fundamentals and application to measurements by use of linear-scale analogue ratemeters, without the influence of sample treatment

EJ/T 1204.1-2006 电离辐射测量探测限和判断阈的确定 第1部分:忽略样品处理影响的计数测量

本部分使用统计学方法规定了两个表征着给定错误概率的统计值，用以评估忽略样品处理影响的电离辐射测量中的探测能力。 本部分适用于忽略样品处理影响的计数测量。

Determination of the detection limit and decision threshold for ionizing radiation measurements Part 1: Counting measurements, neglecting the influence of sample treatment

ANSI/ANS 6.4-2006 核电站的混凝土辐射屏蔽的核分析和设计导则

The standard contains methods and data needed in design of concrete shielding required for protection of personnel and equipment against the effects of gamma rays and neutrons. Specific guidance is given regarding attenuation calculations, shielding design, and standards of documentation.

Concrete Radiation Shielding for Nuclear Power Plants, Guidelines on the Nuclear Analysis and Design of

DIN EN 14255-2:2006 非相干光辐射下个人辐照量的测量和评估.第2部分:工作地点内人工光源发出的可见光和红外线辐射.德文版本EN 14255-2-2005

This European Standard specifies procedures for the measurement and assessment of personal exposures to visible (VIS) and infrared (IR) radiation emitted by artificial sources, where adverse effects cannot be readily excluded. NOTE 1 Adverse effects will normally not occur in exposures caused by normal lighting or room heating. This European Standard applies to VIS- and IR- exposures in indoor and outdoor workplaces. It does not apply to VIS- and IR-exposures in leisure time. This European Standard does not apply to VIS- and IR- exposures caused by the sun. NOTE 2 Part 3 of this standard will deal with UV-exposures caused by the sun. This European Standard does not specify VIS- and IR-exposure limit values. It supports the application of limit values set by national regulations or international recommendations. This European Standard applies to VIS- and IR- exposures by artificial incoherent sources, which emit spectral lines as well as continuous spectra. This European Standard does not apply to coherent radiation sources. NOTE 3 Coherent optical radiation sources are covered by standards for lasers, like EN 60825-1 etc. This European Standard applies to visible (VIS) and infrared (IR) radiation exposures in the wavelength band 380 nm to 3 pm. It also applies to radiation exposures that may present a blue-light hazard in the wavelength band 300 nm to 700 nm. This European Standard does not apply to other effects of which the action spectra lie solely within the UV-region 180 nm to 400 nm. NOTE 4 Part 1 of EN 14255 addresses these effects. This European Standard does not apply to radiation emissions of products. NOTE 5 For radiation emissions of products other standards apply, such as EN 12198 for radiation emissions of machinery, EN 60335-2-27 for household appliances for skin exposures to ultraviolet and infrared radiation and CIE S009 for the safety of lamps and lamp systems. This European Standard does not apply to heat stress, i.e. long term heating of the humans body with strain of the cardiac/circular system caused by climatic environmental conditions including VIS/IR radiation.

Measurement and assessment of personal exposures to incoherent optical radiation - Part 2: Visible and infrared radiation emitted by artificial sources in the workplace; English version of DIN EN 14255-2:2006-03

NF M60-805-3:2005 核能.环境中放射性的测量.水.第3部分:用α液体闪烁法测定水中铀的浓度

Nuclear energy - Measurement of radioactivity in the environment - Water - Part 3 : measurement of the concentration of uranium in water by alpha liquid scintillation.

JIS K 0311:2005 固定辐射源中4至8-氯代二苯并-对二氧芑、4至8-氯代二苯并呋喃和类二氧芑的多氯联苯并的含量测定方法

この規格は，燃焼，化学反応などに伴って煙道，煙突及びダクト(以下，ダクトという。)に排出される排ガス中のテトラからオクタクロロジべンゾーパラージオキシン及びテトラからオクタクロロジべンゾフラン並びにダイオキシン様(よう)PCB(以下，ダイオキシン類という。)のガスクロマトグラフ質量分析計(以下, GU/MSという。)を用いた測定方法について規定する。ここで用いるGC/MSは，ガスクロマトグラフ(GC)のカラムにキャピラリーカラムを用い，分解能が10 000以上である二重収東形質量分析計(MS)の装置とする。 この規格におけるGC/MSの検出下限は，装置，測定条件によって変動はあるが，四塩素化物及び五塩素化物で0.1 pg，六塩素化物及び七塩素化物で0.2 pg，八塩素化物で0.5 pg，ダイオキシン様PCBで0.2 pg以下である。

Method for determination of tetra-through octachlorodibenzo-p-dioxins, tetra-through octachlorodibenzofurans and dioxin-like polychlorinatedbiphenyls in stationary source emissions

DIN CEN/TS 14793:2005 固定源辐射.交替法与参照法比较的实验室内验证过程

This Technical Specification defines a validation procedure to show if an alternative method might be used instead of the standard reference method.

Stationary source emission - Intralaboratory validation procedure for an alternative method compared to a reference method; German version CEN/TS 14793:2005

DIN EN 14255-1:2005 非相干光辐射下个人辐照量的测量和评估.第1部分:工作地点内人工光源发出的紫外线辐射

Measurement and assessment of personal exposures to incoherent optical radiation - Part 1: Ultraviolet radiation emitted by artificial sources in the workplace; German version EN 14255-1:2005

ISO 18589-1:2005 环境中辐射性的测量.土壤.第1部分:一般指南和定义

This part of ISO 18589 specifies the general requirements to carry out radionuclides tests on soil sample, including sampling. This part of ISO 18589 is addressed to people responsible for determining the radioactivity present in soils for the purpose of radiation protection. This may concern soils from gardens and farmland, urban or industrial sites, as well as soil not affected by human activities. This part of ISO 18589 is applicable to all laboratories regardless of the number of personnel or the extent of the scope of testing activities. When a laboratory does not undertake one or more of the activities covered by this part of ISO 18589, such as planning, sampling or testing, the requirements of those clauses do not apply. This part of ISO 18589 is to be used in conjunction with other parts of ISO 18589 that outline the setting up of programmes and sampling techniques, methods of general processing of samples in the laboratory and also methods for measuring the radioactivity in soil. Its purpose is the following: — define the main terms relating to soils, sampling, radioactivity and its measurement; — describe the origins of the radioactivity in soils; — define the main objectives of the study of radioactivity in soil samples; — present the principles of studies of soil radioactivity; — identify the analytical and procedural requirements when measuring radioactivity in soil. This part of ISO 18589 is applicable if radionuclide measurements for the purpose of radiation protection are to be made in the following cases: — initial characterization of radioactivity in the environment; — routine surveillance of the impact of nuclear installations or of the evolution of the general territory; — investigations of accident and incident situations; — planning and surveillance of remedial action; — decommissioning of installations or clearance of materials. This part of ISO 18589 is not intended to cover scientific investigations of soil radioactivity and therefore does not apply to aspects of such measurements.

Measurement of radioactivity in the environment - Soil - Part 1: General guidelines and definitions

ASTM C1475-05(2010)e1 土壤中镎237检测的标准指南

A soil sampling and analysis program provides a direct means of determining the concentration and distribution of radionuclides in soil. The presence and extent of neptunium-237 is of particular interest because it is one of the more mobile transuranics in terms of migration and plant uptake. Since soil is an integrator and a reservoir on long-lived radionuclides, and serves as an intermediary in several pathways of potential importance to humans, knowledge of the concentration of neptunium-237 in soil is essential.1.1 This guide covers the determination of neptunium-237 in soil by means of radiochemical separations and alpha spectrometry. This guide provides options in the selection of sample preparation, separation, and measurement. Although neptunium-237 is not a component of global fallout, it is a product of production reactors and spent fuel processing. This guide is designed for analysis of ten grams of soil previously collected and treated in accordance with Practices C998 and C999. Larger-size samples of environmental soil may also be analyzed, as long as the concentrations of interferences such as uranium and thorium are at or near environmental concentrations. Depending on the choice of a sample dissolution method, all chemical forms of neptunium may not be completely solubilized. This guide should allow the determination of neptunium-237 concentrations from sub becquerel per gram levels to applicable standards depending on count time, sample size, detector efficiency, background, and tracer yield. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 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 8.

Standard Guide for Determination of Neptunium-237 in Soil

ASTM C1475-05 测定土壤中镎237的标准指南

A soil sampling and analysis program provides a direct means of determining the concentration and distribution of radionuclides in soil. The presence and extent of neptunium-237 is of particular interest because it is one of the more mobile transuranics in terms of migration and plant uptake. Since soil is an integrator and a reservoir on long-lived radionuclides, and serves as an intermediary in several pathways of potential importance to humans, knowledge of the concentration of neptunium-237 in soil is essential.1.1 This guide covers the determination of neptunium-237 in soil by means of radiochemical separations and alpha spectrometry. This guide provides options in the selection of sample preparation, separation, and measurement. Although neptunium-237 is not a component of global fallout, it is a product of production reactors and spent fuel processing. This guide is designed for analysis of ten grams of soil previously collected and treated in accordance with Practices C 998 and C 999. Larger-size samples of environmental soil may also be analyzed, as long as the concentrations of interferences such as uranium and thorium are at or near environmental concentrations. Depending on the choice of a sample dissolution method, all chemical forms of neptunium may not be completely solubilized. This guide should allow the determination of neptunium-237 concentrations from sub becquerel per gram levels to applicable standards depending on count time, sample size, detector efficiency, background, and tracer yield.1.2 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 8.

Standard Guide for Determination of Neptunium-237 in Soil

ASTM C1001-05 用α光谱分析法放化测定土壤中钚的标准试验方法

A soil sampling and analysis program provides a direct means of determining the concentration and distribution of radionuclides in soil. A soil analysis program has the most significance for the preoperational monitoring program to establish baseline concentrations prior to the operation of a nuclear facility. Soil analysis, although useful in special cases involving unexpected releases, is a poor technique for assessing small incremental releases and is therefore not recommended as a method for routine monitoring releases of radioactive material. Nevertheless, because soil is an integrator and a reservoir of long-lived radionuclides, and serves as an intermediary in several of the plutonium pathways of potential importance to humans, knowledge of the concentration of plutonium in soil is essential.1.1 This test method covers the determination of plutonium in soils at levels of detection dependent on count time, sample size, detector efficiency, background, and tracer yield. This test method describes one acceptable approach to the determination of plutonium in soil.1.2 This test method is designed for 10 g of soil, previously collected and treated as described in Practices C 998 and C 999, but sample sizes up to 50 g may be analyzed by this test method. This test method may not be able to completely dissolve all forms of plutonium in the soil matrix.1.3 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 hazard statements are given in Section 9.

Standard Test Method for Radiochemical Determination of Plutonium in Soil by Alpha Spectroscopy

ASTM C1000-05 用α光谱分析法放化测定土壤中铀同位素的标准试验方法

This test method is used to analyze soil for alpha-emitting uranium isotopes. It can be used to establish baseline uranium levels and to monitor depositions from nuclear facilities.1.1 This test method covers the determination of alpha-emitting uranium isotopes in soil. This test method describes one acceptable approach to the determination of uranium isotopes in soil.1.2 The test method is designed to analyze 10 g of soil; however, the sample size may be varied to 50 g depending on the activity level. This test method may not be able to completely dissolve all forms of uranium in the soil matrix. Studies have indicated that the use of hydrofluoric acid to dissolve soil has resulted in lower values than results using total dissolution by fusion.1.3 The lower limit of detection is dependent on count time, sample size, detector efficiency, background, and tracer yield. The chemical recovery averaged 78 % in a single laboratory evaluation, and 66 % in an interlaboratory collaborative study.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. A specific precautionary statement is given in Section 10.

Standard Test Method for Radiochemical Determination of Uranium Isotopes in Soil by Alpha Spectrometry