Z33 放射性物质与放射强度分析测试方法 标准查询与下载

DIN EN 13284-2:2004 固定源辐射.粉尘的小范围质量浓度的测定.第2部分:自动测量系统

This Part of EN 13284 specifies specific requirements on automated measuring systems (AMS) for dust monitoring. It is derived from EN 14181 which is the general document on the quality assurance of AMS. It is only applicable in conjunction with EN 14181. The standard specifies test criteria for the QAL1 and specific requirements for QAL2, QAL3 and AST for dust AMS used for proving that the dust emissions from a source are compliant with emission limits below 50 mg/m3 (standard conditions) in ducted gaseous streams. This part of EN 13284 is applicable by direct correlation with the standard reference method (SRM) described in EN 13284-1.#,,#

Stationary source emissions - Determination of low range mass concentration of dust - Part 2: Automated measuring systems; German version EN 13284-2:2004

BS ISO 14850-1:2004 核能.废弃物包装件的活性测量.带公开几何条件的整体模型中的高分辨率γ光谱测定法

This part of ISO 14850 describes a procedure for measurements of gamma-emitting radionuclide activity in the following homogeneous objects: — unconditioned waste, including process waste (filters, control rods, etc.), dismantling waste, etc.; — waste conditioned in various matrices (bitumen, hydraulic binder, thermosetting resins, etc.), notably in the form of 100 I, 200 I, 400 I or 800 I drums, and test specimens or samples, (vitrified waste); — waste packaged in a container, notably technological waste. It also specifies the calibration of the gamma spectrometry chain. The gamma energies used generally range from 0,05 MeV to 3 MeV.

Nuclear energy - Waste-packages activity measurement - High-resolution gamma spectrometry in integral mode with open geometry

DIN EN 14385:2004 固定源辐射.As、Cd、Cr、Co、Cu、Mn、Ni、Pb、Sb、TI和V总辐射量的测定

The document specifies a manual reference method for the determination of the mass concentration of specific elements in exhaust gases from hazardous waste incinerators. The method is applicable for the concentration range of each of the specific elements of 0,001 mg/m3 to 0,5 mg/m3. Specific elements according to this European standard are antimony (Sb), arsenic (As), cadmium (Cd), chromium (Cr), cobalt (Co), copper (Cu), lead (Pb), manganese (Mn), nickel (Ni), thallium (Tl), and vanadium (V).

Stationary source emissions - Determination of the total emission of As, Cd, Cr, Co, Cu, Mn, Ni, Pb, Sb, TI and V; German version EN 14385:2004

ASTM C1109-04 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 C 1220. 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.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 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 Practice for Analysis of Aqueous Leachates from Nuclear Waste Materials Using Inductively Coupled Plasma-Atomic Emission Spectrometry

ASTM E1026-04e1 使用弗里克标准剂量测定系统的标准实施规范

1.1 This practice covers the procedures for preparation, testing and using the acidic aqueous ferrous ammonium sulfate solution dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. The system will be referred to as the Fricke system. It is classified as a reference-standard dosimetry system (see ISO/ASTM 51261).1.2 The practice describes the spectrophotometric analysis procedures for the Fricke dosimeter.1.3 This practice applies only to gamma rays, x-rays (bremsstrahlung), and high-energy electrons.1.4 This practice applies provided the following are satisfied:1.4.1 The absorbed dose range shall be from 20 to 400 Gy (1).1.4.2 The absorbed-dose rate does not exceed 10 6 Gys1 (2).1.4.3 For radioisotope gamma-ray sources, the initial photon energy is greater than 0.6 MeV. For x-rays (bremsstrahlung), the initial energy of the electrons used to produce the photons is equal to or greater than 2 MeV. For electron beams, the initial electron energy is greater than 8 MeV (see ICRU Reports 34 and 35).Note 18212;The lower energy limits given are appropriate for a cylindrical dosimeter ampoule of 12-mm outside diameter. Corrections for dose gradients across an ampoule of that diameter or less are not required.1.4.4 The irradiation temperature of the dosimeter should be within the range of 10 to 60C.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 Practice for Using the Fricke Reference-Standard Dosimetry System

ASTM E1026-04 使用弗里克标准剂量测定系统的标准实施规范

1.1 This practice covers the procedures for preparation, testing and using the acidic aqueous ferrous ammonium sulfate solution dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. The system will be referred to as the Fricke system. It is classified as a reference-standard dosimetry system (see ISO/ASTM 51261).1.2 The practice describes the spectrophotometric analysis procedures for the Fricke dosimeter.1.3 This practice applies only to gamma rays, x-rays (bremsstrahlung), and high-energy electrons.1.4 This practice applies provided the following are satisfied:1.4.1 The absorbed dose range shall be from 20 to 400 Gy (1.1.4.2 The absorbed-dose rate does not exceed 10 6 Gys1 (2).1.4.3 For radioisotope gamma-ray sources, the initial photon energy is greater than 0.6 MeV. For x-rays (bremsstrahlung), the initial energy of the electrons used to produce the photons is equal to or greater than 2 MeV. For electron beams, the initial electron energy is greater than 8 MeV (see ICRU Reports 34 and 35). Note 18212;The lower energy limits given are appropriate for a cylindrical dosimeter ampoule of 12-mm outside diameter. Corrections for dose gradients across an ampoule of that diameter or less are not required.1.4.4 The irradiation temperature of the dosimeter should be within the range of 10 to 60176;C.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 Practice for Using the Fricke Reference Standard Dosimetry System

ANSI/ANS 16.1-2003 用短期试验法测量已固化的低放射性废物的浸出性

This standard provides a uniform procedure to measure and index the release of radionuclides from waste forms as a result of leaching in demineralized water for five days (seven data points). The results cannot be interpreted to apply to any specific environmental situation except through correlative studies of actual disposal site conditions.

Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure

NF X43-329:2003 固定源排放 排放时多环芳烃的采样和测量

Émissions de sources fixes - Prélèvement et mesurage d'hydrocarbures aromatiques polycycliques à l'émission

ASTM C1571-03(2012) 热处理用放射性和/或危险废弃物表征的标准指南

This guide identifies methods to determine the physical and chemical characteristics of a variety of hazardous and/or radioactive wastes including heavy metal contaminated wastes. These wastes can be in the physical form of sludges (wet or dry), spent waste water filter aids, waste water filter cakes, incinerator ashes (wet or dry), incinerator blowdown (wet or dry), asbestos, resins, zeolites, soils, unset or unsatisfactory cementitious waste forms in need of remediation, lead paint wastes, radioactively or non-radioactively contaminated asbestos, geologic mill tailings (also known as byproduct materials) and other naturally occurring or accelerator produced radioactive materials (NORM and NARM), etc. and combinations of the above. This guide may not be applicable to piping, duct work, rubble, debris waste or wastes containing these components. This guide identifies the physical and chemical characteristics useful for developing high temperature thermal treatment methodologies for a variety of hazardous and/or radioactive process wastes and soils including heavy metal contaminated wastes. The waste characteristics can be used to (1) choose and develop the thermal treatment methodology, (2) determine if waste pretreatment is needed, (3) aid in development of thermal treatment process control, (4) develop surrogate waste formulations, (5) perform treatability studies, (6) determine processing regions (envelopes) of acceptable waste form composition, and/or (7) perform pilot scale testing with actual or surrogate waste, and/or (8) determine the composition and concentrations of off-gas species for regulatory compliance. This guide identifies applicable test methods that can be used to measure the desired characteristics of the hazardous and/or radioactive wastes described in 4.1. The analyses discussed in this standard can be performed by a variety of techniques depending on equipment availability. For example, Gas Chromatograph Mass Spectrometry (GC/MS) can be used to measure the amount and type of off-gas species present. However, this standard assumes that such sophisticated equipment is unavailable for radioactive or hazardous waste service due to potential contamination of the equipment. The analyses recommended are, therefore, the simplest and least costly analyses that can be performed and still considered adequate. Not every characteristic given in this guide is necessary for every waste (see Fig. 1). Cation analysis is necessary for every waste in order to determine whether the final waste form will be a homogeneous glass, a glass-ceramic, or a slag (see Appendix X1). Waste Analysis Method A is applicable when it is desired to know the amount and type of volatiles to be expected during thermal treatment and their compatibility with the thermal treatment and off-gas unit materials of construction and design capacity. These methods may be used to determine incinerator off-gas composition and concentrations. Waste analysis Method A is applicable when it is necessary to know the amount of organics in the waste independently of the amount of other volatile constituents present for safety concerns. These methods may be used to determine incinerator off-gas composition and concentrations. Waste analysis Method A is applicable when it is necessary to know if molten salt formation and accumulation in a thermal treatment unit in the presence of water vapor may be a safety concern. Waste Analysis Methods B and C are applicable when it is desired to only know the amount of volatiles to be expected during thermal treatment, for example, when speciation of the volatiles and potential molten salt formation is not of concern. These methods may be used to determi......

Standard Guide for Characterization of Radioactive and/or Hazardous Wastes for Thermal Treatment

ASTM C1571-03 热处理用放射性和/或危险废弃物表征的标准指南

1.1 This guide identifies methods to determine the physical and chemical characteristics of radioactive and/or hazardous wastes before a waste is processed at high temperatures, for example, vitrification into a homogeneous glass ,glass-ceramic, or ceramic waste form. This includes waste forms produced by ex-situ vitrification (ESV), in-situ vitrification (ISV), slagging, plasma-arc, hot-isostatic pressing (HIP) and/or cold-pressing and sintering technologies. Note that this guide does not specifically address high temperature waste treatment by incineration but several of the analyses described in this guide may be useful diagnostic methods to determine incinerator off-gas composition and concentrations. The characterization of the waste(s) recommended in this guide can be used to (1) choose and develop the appropriate thermal treatment methodology, (2) determine if waste pretreatment is needed prior to thermal treatment, (3) aid in development of thermal treatment process control, (4) develop surrogate waste formulations, (5) perform treatability studies, (6) determine processing regions (envelopes) of acceptable waste form composition, (7) perform pilot scale testing with actual or surrogate waste, and/or (8) determine the composition and concentrations of off-gas species for regulatory compliance. The analyses discussed in this standard can be performed by a variety of techniques depending on equipment availability. For example, Gas Chromatograph Mass Spectrometry (GC/MS) can be used to measure the amount and type of off-gas species present. However, this standard assumes that such sophisticated equipment is unavailable for radioactive or hazardous waste service due to potential contamination of the equipment. The analyses recommended are, therefore, the simplest and least costly analyses that can be performed and still be considered adequate1.2 This guide is applicable to radioactive and/or hazardous wastes including but not limited to, high-level wastes, low-level wastes, transuranic (TRU) wastes, hazardous wastes, mixed (hazardous and radioactive) wastes, heavy metal contaminated wastes, and naturally occurring or accelerator produced radioactive material (NARM or NORM) wastes. These wastes can be in the physical form of wet sludges, dried sludges, spent waste water filter aids, waste water filter cakes, incinerator ashes (wet or dry), incinerator blowdown (wet or dry), wastewaters, asbestos, resins, zeolites, soils, unset or unsatisfactory cementitious wastes forms in need of remediation, lead paint wastes, etc. and combinations of the above. This guide may not be applicable to piping, duct work, rubble, debris waste or wastes containing these components.1.3 This guide references applicable test methods that can be used to characterize hazardous wastes, radioactive wastes, and heavy metal contaminated process wastes, waste forms, NARM or NORM wastes, and soils.1.4 These test methods must be performed in accordance with all quality assurance requirements for acceptance of the data.1.5 This standard may involve hazardous materials, operations, and equipment. 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 Characterization of Radioactive and/or Hazardous Wastes for Thermal Treatment

NF X43-341:2002 固定源辐射.测定单个有机化合物的质量浓度.活性碳和溶质吸收法

Stationary source emissions - Determination of the mass concentration of individual gaseous organic compounds - Activated carbon and solvent desorption method.

DIN EN 13284-1:2002 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

This European Standard describes a reference method for the measurement of low dust content waste gases in the concentrations below 50 mg/m3 standard conditions. This method has been validated with special emphasis around 5 mg/m3 on an average half hour sampling time. This European Standard is primarily developed and validated for gaseous streams emitted by waste incinerators. More generally, it may be applied to waste gases emitted from stationary sources, and to higher concentrations.

Stationary source emissions - Determination of low range mass concentration of dust - Part 1: Manual gravimetric method; German version EN 13284-1:2001

ASTM C1000-00 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

1.1 This test method covers 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. 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

ASTM C1001-00 用α光谱分析法放化测定土壤中钚的标准试验方法

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 C998 and C999, 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 Sections 6 and 9.

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

JIS K 0311:1999 固定源发射中4至8-氯代二苯并-p-二氧芑、4至8-氯代二苯并呋喃和共面多氯联苯的测定方法

Method for determination of tetra- through octa-chlorodibenzo-p-dioxins, tetra- through octa-chlorodibenzofurans and coplanar polychlorobiphenyls in stationary source emissions

EJ/T 1094-1999 铀镭平衡系数测量规程

Measurement rules on uranium and radium equilibrium coefficient

EJ/T 1075-1998 水中总α放射性浓度的测定厚源法

Determination of gross alpha activity in water thick source method

BS EN 1934:1998 建筑物的热性能.用热流计隔热箱法测定热阻.圬工

This standard establishes the principles and criteria to be complied with for the determination of the laboratory steady-state heat transfer properties of masonry walls in a hot box by means of a heat flow meter mounted on one face of the masonry wall to be tested (i.e. the test specimen). It describes the apparatus, measurement technique and necessary data reporting. It does not, however, specify a particular apparatus design since requirements vary particularly in terms of size, and also to a lesser extent, in terms of operating conditions. The property that is measured is the surface-to-surface thermal resistance of the specimen, provided that the metering section of the heat flow meter covers a representative portion of the specimen, and the homogeneity criteria of 6.2.1 are met. From these measurements the thermal resistance for application in buildings is derived. The thermal transmittance of a masonry wall can then be calculated from this value with standardized surface coefficients. This standard is applicable to measurements on both dry and moist specimens, provided that the conditions indicated in 5.3.3 are met.The influence of moisture content on the thermal properties of masonry can be taken into account by measurements at different moisture contents of the specimen in the range of the practical moisture content including the dry state, which corresponds to the most frequent testing condition. The method is also suitable for horizontal elements such as ceilings and floors.

Thermal performance of buildings - Determination of thermal resistance by hot box method using heat flow meter - Masonry

BS ISO 11599:1998 含有包埋放射废物的液压粘合剂气孔和透气性的测定

This International Standard describes the principles and methodologies of measuring both gas open porosity and permeability of hydraulic binder-based matrices used for immobilization of radioactive waste. The measurements can be carried out by using different apparatus designed and constructed on the basis of a few recommended characteristics. The measurements can be performed on samples prepared in a laboratory or taken from industrial production. Samples can be obtained by moulding or by coring a block.

Determination of gas porosity and gas permeability of hydraulic binders containing embedded radioactive waste

EJ/T 349.4-1998 岩石中微量铀钍的测定.P₃₅₀-吸附树脂萃取色层连续分离分光光度法

Determination of micro Uranium and Thorium in rocks spectrophotometry by extraction chromatographic simultaneous separation with P-adsorbed resin