Z33 放射性物质与放射强度分析测试方法 标准查询与下载

NF M60-790-5*NF EN ISO 18589-5:2021 环境中放射性的测量. 土壤. 第5部分: 锶90. 使用比例计数或液体闪烁计数的试验方法

Measurement of radioactivity in the environment - Soil - Part 5 : strontium 90 - Test method using proportional counting or liquid scintillation counting

HY/T 235-2018 海洋环境放射性核素监测技术规程

Technical specification for marine environmental radionuclide monitoring

DIN EN 13284-1:2018 固定源辐射.小范围粉尘质量浓度测定.第1部分:手工称重法;德文版本EN 13284-1-2017

This European Standard specifies the standard reference method (SRM) for the measurement of low dust concentration in ducted gaseous streams in the concentrations below 50 mg/m3 at standard conditions. This European Standard is primarily developed and validated for gaseous streams emitted by waste incinerators. More generally, it can be applied to gases emitted from other stationary sources, and to higher concentrations. If the gases contain unstable, reactive or semi-volatile substances, the measurement depends on the sampling and filter treatment conditions. This method has been validated in field tests with special emphasis to dust concentrations around 5 mg/m3. The results of the field tests are presented in Annex A.

Stationary source emissions - Determination of low range mass concentration of dust - Part 1: Manual gravimetric method; German version EN 13284-1:2017

ASTM C1475-17 测定土壤中镎237的标准指南

5.1 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 9. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Guide for Determination of Neptunium-237 in Soil

DIN 6873-5:2015 放射治疗疗程规化系统.第5部分:特征稳定性试验

Radiotherapy treatment planning systems - Part 5: Constancy testing of characteristics

BS ISO 18589-7:2013 环境中放射性的测量. 土壤. 伽玛射线放射性核素的就地测量

Measurement of radioactivity in the environment. Soil. In situ measurement of gamma-emitting radionuclides

ISO 18589-7:2013 环境中放射性的测量.土壤.第7部分:gamma放射活性的现场测量

This part of 18589 specifies the identification of radionuclides and the measurement of their activity in soil using in situ gamma spectrometry with portable systems equipped with germanium or scintillation detectors.

Measurement of radioactivity in the environment.Soil.Part 7: In situ measurement of gamma-emitting radionuclides

DIN EN 12619:2013 固定源排放.测定废气中低浓度全部气态有机碳的质量浓度.连续火焰电离探测器法.德文版本EN 12619-2013

Stationary source emissions - Determination of the mass concentration of total gaseous organic carbon - Continuous flame ionisation detector method; German version EN 12619:2013

NF M60-771:2013 大气环境放射性的测定,空气:氡-222.第8部分:建筑物内的初步和补充调查方法

Measurement of radioactivity in the environment - Air : radon-222 - Part 8: methodologies for initial and additional investigations in buildings

NF M60-767:2012 环境中放射性的测量 - 空气: 氡-222 - 第5部分: 放射性浓度的连续测量法.

Measurement of radioactivity in the environment - Air : radon-222 - Part 5 : continuous measurement method of the activity concentration.

NF M60-768:2012 环境中放射性的测量 - 空气: 氡-222 - 第7部分: 评估表面蒸发率用累积法.

Measurement of radioactivity in the environment - Air : radon-222 - Part 7 : accumulation method for estimating surface exhalation rate.

DIN EN 15875:2012 废料特性描述.硫化物废料潜在酸性和中和性测定的静态试验.德文版 EN 15875-2011

Characterization of waste - Static test for determination of acid potential and neutralisation potential of sulfidic waste; German version EN 15875:2011

ASTM C1751-11 放射性废料槽取样的标准指南

Obtaining samples of high-level waste created during the reprocessing of spent nuclear fuels presents unique challenges. Generally, high-level waste is stored in tanks with limited access to decrease the potential for radiation exposure to personnel. Samples must be obtained remotely because of the high radiation dose from the bulk material and the samples; samples require shielding nbsp;nbsp;nbsp;for handling, transport, and storage. The quantity of sample that can be obtained and transported is nbsp;nbsp;nbsp;small due to the hazardous nature of the samples as well as their high radiation dose. Many high-level wastes have been treated to remove strontium (Sr) or cesium (Cs), or both, underwent liquid volume reductions through forced evaporation or have been pH modified, or both, to decrease corrosion of the tanks. These processes, as well as waste streams added from multiple process plant operations, often resulted in precipitation, and produced multiphase wastes that are heterogeneous. Evaporation of water from waste with significant dissolved salts concentrations has occurred in some tanks due to the high heat load associated with the high-level waste and by intentional evaporative processing, resulting in the formation of a saltcake or crusts, or both. Organic layers exist in some waste tanks, creating additional heterogeneity in the wastes. Due to these extraordinary challenges, substantial effort in research and development has been expended to develop techniques to provide grab samples of the contents of the high-level waste tanks. A summary of the primary techniques used to obtain samples from high-level waste tanks is provided in Table 1. These techniques will be summarized in this guideline with the assumption that the tank headspace is adequately ventilated during sampling. TABLE 1 High-Level Waste Tank Sampling Methods TechniqueMaterial TypeNotes SolidSlurryLiquid HAST in-tank needle orifice X Orifice as part of Reverse-Flow Diverter (RFD) Bottle on a String X X Dip sample Vacuum Pump X X Auger X X Only high viscosity slurries Sample Cup X X Manual system used at Savannah River Site to obtain salt-cake samples and hard sludges that don’t slump. Core Drilling Rotary Mode (Hanford Sampler) X X

Standard Guide for Sampling Radioactive Tank Waste

ASTM C1752-11 测量放射性溶液,泥浆,污泥的物理和流变特性的标准指南

Measurements performed in this guide are limited to radioactive solutions, slurries, and sludges as well as simulants designed to model the properties of these radioactive materials. Data obtained from the measurement and calculation of physical and rheological properties of radioactive solutions, slurries, and sludges are essential in developing appropriate nbsp;nbsp;nbsp;simulants for design and testing of retrieval, transport, mixing, and storage systems for treatment of radioactive materials. These data also provide input parameters for modeling the flow behavior, processing, transport, safety, and storage of these radioactive materials. Consistency in the handling of samples, measurement methods, and calculations is essential in obtaining reproducible results of rheological and physical property measurements. This guide will be used to measure or calculate the physical properties listed below. Bulk slurry density Settled solids density Centrifuged solids density Supernatant density Settling rate Volume percent centrifuged solids Volume percent settled solids after settling Undissolved solids content Dissolved solids content Weight percent centrifuged solids Weight percent total oxides Solids content of the centrifuged solids Total solids content This guide describes the process of performing measurement of the rheological properties. The rheological measurements and calculations described in this guide are limited to shear strength, shear stress versus shear rate, apparent viscosity, consistency, and yield stress. Due to the nature of some solutions, slurries, and sludges, not all of the measurements described in this standard may be applicable to all samples. For example, some sludges do not settle; therefore, settling rate measurements are not applicable for these samples.1.1 Intent: 1.1.1 The intent of this guide is to provide guidance for the measurement and calculation of physical and rheological properties of radioactive solutions, slurries, and sludges as well as simulants designed to model the properties of these radioactive materials. 1.2 Applicability: 1.2.1 This guide is intended for measurement of mass and volume of the solution, slurries, and sludges as well as dissolved solids content in the liquid fraction and solids content associated with the slurries and sludges. Particle size distribution is also measured. 1.2.2 This guide identifies the data required and the equations recommended for calculation of density (bulk, settled solids, supernatant, and centrifuged solids), settling rate, volume and weight percent of the centrifuged solids and settled solids, and the weight percent undissolved solids, dissolved solids, and total oxides. 1.2.3 This guide is intended for measurement of shear strength and shear stress as a function of shear rate. 1.2.4 Rheological property measurement guidelines in this guide are limited to rotational rheometers. 1.2.5 This guide is limited to measurements of viscous and incipient flow and does not include oscillatory rheometry. nbsp;nbsp;nbsp; 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 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 Measuring Physical and Rheological Properties of Radioactive Solutions, Slurries, and Sludges

ASTM C1000-11 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, background, and tracer yield. The chemical yield averaged 78 % in a single laboratory evaluation, and 66 % in an interlaboratory collaborative study. 1.4 The values stated in SI units are to be regarded as standard. The values given in parentheses are for information only. 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. A specific precautionary statement is given in Section 10.

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

ASTM D5608-10 用于低水平放射性废物场所的现场设备去污染标准规范

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: Minimizing the spread of contamination within a site and preventing the spread outside of the work area. Reducing the potential exposure of workers during the work and the subsequent decontamination of equipment. 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. 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, handling, or disposal of generated wastes.1.1 These practices cover 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). For sample contacting equipment there are four separate procedures (Procedure A through D) in Section 8. For non-contacting equipment, one procedure is presented as covered in Section 9. 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, s......

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

ASTM C1109-10 使用电感耦合等离子体原子发射光谱法分析核废料中浸出液的标准实施规程

This practice may be used to determine concentrations of elements leached from nuclear waste materials (glasses, ceramics, cements) using an aqueous leachant. If the nuclear waste material is radioactive, a suitably contained and shielded ICP-AES spectrometer system with a filtered exit-gas system must be used, but no other changes in the practice are required. The leachant may be deionized water or any aqueous solution containing less than 1 % total solids. This practice as written is for the analysis of solutions containing 1 % (v/v) nitric acid. It can be modified to specify the use of the same or another mineral acid at the same or higher concentration. In such cases, the only change needed in this practice is to substitute the preferred acid and concentration value whenever 1 % nitric acid appears here. It is important that the acid type and content of the reference and check solutions closely match the leachate solutions to be analyzed. This practice can be used to analyze leachates from static leach testing of waste forms using Test Method C1220. 1.1 This practice is applicable to the determination of low concentration and trace elements in aqueous leachate solutions produced by the leaching of nuclear waste materials, using inductively coupled plasma-atomic emission spectroscopy (ICP-AES). 1.2 The nuclear waste material may be a simulated (non-radioactive) 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 This practice should be used by analysts experienced in the use of ICP-AES, the interpretation of spectral and non-spectral interferences, and procedures for their correction. 1.5 No detailed operating instructions are provided because of differences among various makes and models of suitable ICP-AES instruments. Instead, the analyst shall follow the instructions provided by the manufacturer of the particular instrument. This test method does not address comparative accuracy of different devices or the precision between instruments of the same make and model. 1.6 This practice contains notes that are explanatory and are not part of the mandatory requirements of the method. 1.7 The values stated in SI units are to be regarded as the standard. 1.8 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 Practice for Analysis of Aqueous Leachates from Nuclear Waste Materials Using Inductively Coupled Plasma-Atomic Emission Spectrometry

ASTM C1207-10 无源中子符合计数法测定废弃物中钚的无损检验的标准试验方法

This test method is useful for determining the plutonium content of scrap and waste in containers ranging from small cans with volumes of the order of a mL to crates and boxes of several thousand liters in volume. A common application would be to 208-L (55-gal) drums. Total Pu content ranges from 10 mg to 6 kg (1). The upper limit may be restricted depending on specific matrix, calibration material, criticality safety, or counting equipment considerations. This test method is applicable for U.S. Department of Energy shipper/receiver confirmatory measurements (9), nuclear material diversion detection, and International Atomic Energy Agency attributes measurements (10). This test method should be used in conjunction with a scrap and waste management plan that segregates scrap and waste assay items into material categories according to some or all of the following criteria: bulk density, the chemical forms of the plutonium and the matrix, americium to plutonium isotopic ratio, and hydrogen content. Packaging for each category should be uniform with respect to size, shape, and composition of the container. Each material category might require calibration standards and may have different Pu mass limits. Bias in passive neutron coincidence measurements is related to item size and density, the homogeneity and composition of the matrix, and the quantity and distribution of the nuclear material. The precision of the measurement results is related to the quantity of nuclear material, the (α,n) reaction rate, and the count time of the measurement. For both benign matrix and matrix specific measurements, the method assumes the calibration reference materials match the items to be measured with respect to the homogeneity and composition of the matrix, the neutron moderator and absorber content, and the quantity of nuclear material, to the extent they affect the measurement. Measurements of smaller containers containing scrap and waste are generally more accurate than measurements of larger items. It is recommended that where feasible measurements be made on items with homogeneous contents. Heterogeneity in the distribution of nuclear material, neutron moderators, and neutron absorbers have the potential to cause biased results. The coincident neutron production rates measured by this test method are related to the mass of the even number isotopes of plutonium. If the relative abundances of these isotopes are not accurately known, biases in the total Pu assay value will result. Typical count times are in the range of 300 to 3600 s. Reliable results from the application of this method require training of the personnel who package the scrap and waste prior to measurement and of personnel who perform the measurements. Training guidance is available from ANSI 15.20, Guides , C1009, C1068, and C1490.1.1 This test method describes the nondestructive assay of scrap or waste for plutonium content using passive thermal-neutron coincidence counting. This test method provides rapid results and can be applied to a variety of carefully sorted materials in containers as large as several thousand liters in volume. The test method applies to measurements of 238Pu, 240Pu, and 242Pu and has been used to assay items whose total plutonium content ranges from 10 mg to 6 kg (1). 1.2 This test method requires knowledge of the rel......

Standard Test Method for Nondestructive Assay of Plutonium in Scrap and Waste by Passive Neutron Coincidence Counting

ISO 18589-5:2009 环境中放射性的测量.土壤.第5部分:锶90的测量

Measurement of radioactivity in the environment - Soil - Part 5: Measurement of strontium 90

ISO 18589-4:2009 环境中放射性的测量.土壤.第4部分:使用α光谱测定法测量钚同位素(钚238和钚239+240)

Measurement of radioactivity in the environment - Soil - Part 4: Measurement of plutonium isotopes (plutonium 238 and plutonium 239 + 240) by alpha spectrometry