F70 辐射防护与监测综合 标准查询与下载

EJ/T 1193-2005 后处理厂退役源项调查取样技术准则

本标准规定了核燃料后处理厂退役源项调查的取样原则、取样点设计、取样方法、样品预处理、辐射防护和质量保证等技术要求。 本标准适用于核燃料后处理厂退役源项调查时构筑物、系统和设备的取样。其他类型的核设施退役源项调查取样可参考使用。

Technical criteria for sampling of source term survey for decommissioning of reprocessing plant

EJ/T 1183-2005 核空气净化系统碘吸附器净化系数的测定.放射性甲基碘法

本标准规定了用放射性甲基碘测定核空气净化系统碘吸附器净化系数的方法。 本标准适用于核空气净化系统碘吸附器的现场试验，也适用于单台碘吸附器在制造厂的性能试验，还适用于空气绝对压力小于1.4×10Pa的通风系统。

Verification of scrubbing coefficient of iodine adsorbers in nuclear air treatment systems By radioactive methyl iodide

ISO 19238:2004 辐射防护.进行细胞遗传学生物剂量测定的工作实验室的性能标准

This International Standard provides criteria for quality assurance and quality control, evaluation of the performance and the accreditation of biological dosimetry by cytogenetic service laboratories. This International Standard addresses a) the confidentiality of personal information, for the customer and the service laboratory, b) the laboratory safety requirements, c) the calibration sources and calibration dose ranges useful for establishing the reference dose-effect curves allowing the dose estimation from chromosome aberration frequency, and the minimum detection levels, d) the scoring procedure for unstable chromosome aberrations used for biological dosimetry, e) the criteria for converting a measured aberration frequency into an estimate of absorbed dose, f) the reporting of results, g) the quality assurance and quality control, h) informative annexes containing examples of a questionnaire, instructions for customers, a data sheet for recording aberrations and a sample report.

Radiation protection - Performance criteria for service laboratories performing biological dosimetry by cytogenetics

IEC 62022:2004 由车辆运输的可再利用或不可再利用材料中γ辐射的控制和检测用已装好的监测器

Defines an installed monitor for the control and detection of radioactivity of gamma emitters contained in recyclable or non-recyclable materials transported by vehicle, the conceptual requirements, general characteristics, mechanical characteristics, en

Installed monitors for the control and detection of gamma radiations contained in recyclable or non-recyclable materials transported by vehicles

ASTM D4537-04a 核设施涂层工作的质量和认证检验人员资格考核程序确立的标准指南

The requirements of this guide apply to personnel who perform coating work inspection during (1) fabrication, (2) receipt of items at the construction site, (3) construction, (4) pre-operational and startup testing, and (5) operational phases of nuclear facilities. It is the responsibility of each organization participating in the project to ensure that only those personnel within their respective organizations who meet the requirements of this guide are permitted to perform coating work inspection activities covered by this guide. The organization(s) responsible for establishing the applicable requirements for activities covered by this guide shall be identified, and the scope of their responsibility shall be documented. Delegation of this responsibility to other qualified organizations is permitted and shall be documented. It is the responsibility of the organization performing these activities to specify the detailed methods and procedures for meeting the requirements of this guide, unless they are otherwise specified in the contract documents. In the event of conflict, users of this guide must recognize that the licenseersquo;plant-specific quality assurance program and licensing commitments shall prevail with respect to the process of qualifying personnel performing inspection of coating work.1.1 This guide delineates the requirements for development of procedures for the qualification of personnel who perform inspection of coating work. These activities are accomplished to verify conformance to specified requirements for nuclear facility coating work whose satisfactory performance is required in order not to compromise safety-related coating systems.1.2 This guide provides a uniform interpretation of the intent of the requirements in ANSI/ASME N45.2.6 for the inspection of coating work in nuclear facilities.1.3 This guide meets the intent of ANSI/ASME NQA-1.1.4 It is the intent of this guide to provide a recommended basis for qualification, not to mandate a singular basis for all qualifications. Variations or simplifications of the qualifications described in this guide may be appropriate for special coating work other than safety-related coating systems. Similarly, the qualification and certification process might be abbreviated for work of minor scope such as touch-up. 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 whoever uses this standard to consult and establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Establishing Procedures to Qualify and Certify Personnel Performing Coating Work Inspection in Nuclear Facilities

ASTM C1572-04 远程操作设备用干铅玻璃和注油铅玻璃辐射屏蔽窗组件的标准指南

Radiation Shielding Window Components: 4.1.1 Radiation shielding window components operability and long-term integrity are concerns that originate during the design, and fabrication sequences. Such concerns can only be addressed, or are most efficiently addressed during one or the other of these stages. The operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions. 4.1.2 This standard is intended as a supplement to other standards, and to federal and state regulations, codes, and criteria applicable to the design of radiation shielding window components.1.1 Intent1.1.1 This intent of this standard is to provide guidance for the design, fabrication, quality assurance, inspection, testing, packaging, shipping, installation and maintenance of radiation shielding window components. These window components include wall liner embedments, dry lead glass radiation shielding window assemblies, oil-filled lead glass radiation shielding window assemblies, shielding wall plugs, barrier shields, view ports, and the installation/extraction table/device required for the installation and removal of the window components.1.2 Applicability1.2.1 This standard is intended for those persons who are tasked with the planning, design, procurement, fabrication, installation, and operation of the radiation shielding window components that may be used in the operation of hot cells, high level caves, mini-cells, canyon facilities, and very high level radiation areas.1.2.2 This standard applies to radiation shielding window assemblies used in normal concrete walls, high-density concrete walls, steel walls and lead walls.1.2.3 The system of units employed in this standard is the metric unit, also known as SI Units, which are commonly used for International Systems, and defined, by ASTM/IEEE SI-10 Standard for Use of International System of Units. Common nomenclature for specifying some terms; specifically shielding, uses a combination of metric units and inch-pound units.1.2.4 This standard identifies the special information required by the Manufacturer for the design of window components. A1.1 shows a sample list of the radiation source spectra and geometry information, typically required for shielding analysis. A2.1 shows a detailed sample list of specific data typically required to determine the physical size, glass types, and viewing characteristics of the shielding window, or view port. A3 shows general window configuration sketches. Blank copies of A1.2 and A2.2 are found in the respective Annexes for the Owner-Operator''s use.1.2.5 This standard is intended to be generic and to apply to a wide range of configurations and types of lead glass radiation shielding window components used in hot cells. It does not address glovebox, water, x-ray glass or zinc bromide windows.1.3 Caveats1.3.1 Consideration shall be given when preparing the shielding window designs for the safety related issues discussed in the Hazards Sources and Failure Modes, Section ; such as dielectric discharge, over-pressurization, radiation exposure, contamination, and overturning of the extraction table/device.1.3.2 In many cases, the use of the word "shall" has been purposely used in lieu of "should" to stress the importance of the statements that have been made in this standard.1.3.3 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 requirements prior to use.

Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for Remotely Operated Facilities

ASTM C1174-04 地质处理高级核废料工程屏蔽系统中使用的包括废料的材料长期使用性能的预测的标准实施规程

1.1 This practice describes test methods and data analyses used to develop models for the prediction of the long-term behavior of materials, such as engineered barrier system (EBS) materials and waste forms, used in the geologic disposal of spent nuclear fuel (SNF) and other high-level nuclear waste in a geologic repository. The alteration behavior of waste form and EBS materials is important because it affects the retention of radionuclides by the disposal system. The waste form and EBS materials provide a barrier to release either directly (as in the case of waste forms in which the radionuclides are initially immobilized), or indirectly (as in the case of containment materials that restrict the ingress of groundwater or the egress of radionuclides that are released as the waste forms and EBS materials degrade).1.1.1 Steps involved in making such predictions include problem definition, testing, modeling, and model confirmation.1.1.2 The predictions are based on models derived from theoretical considerations, expert judgement, interpretation of data obtained from tests, and appropriate analogs.1.1.3 For the purpose of this practice, tests are categorized according to the information they provide and how it is used for model development and use. These tests may include but are not limited to the following:Attribute tests to measure intrinsic materials properties,Characterization tests to measure the effects of material and environmental variables on behavior,Accelerated tests to accelerate alteration and determine important mechanisms and processes that can affect the lifetime licensed performance of waste form and EBS materials,Service condition tests to confirm the appropriateness of the model and variables for anticipated disposal conditions,Confirmation tests to verify the predictive capacity of the model, andTests or analyses performed with analog materials to identify important mechanisms, verify the appropriateness of an accelerated test method, and to confirm long-term model predictions.1.2 The purpose of this practice is to provide methods for developing models that can be used for the prediction of materials behavior over the long periods of time pertinent to the service life of a geologic repository as part of the basis for performance assessment of the repository.1.3 This practice also addresses uncertainties in materials behavior models and their impact on the confidence in the performance assessment.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 requirements prior to use.

Standard Practice for Prediction of the Long-Term Behavior of Materials, Including Waste Forms, Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste

ASTM E2381-04(2010) 在流态化床和流动溪放射处理中发射量测定标准指南

Dosimetric Techniques8212;The processes addressed here utilize a variety of techniques for the dynamic presentation of the product to the radiation source. This may involve gravitational flow or simple pneumatic transport about or past the radiation source. In the case of fluidized beds, the product may be presented to the radiation source while supported in a gaseous or liquid stream moving at relatively high velocities. This document provides a guide to the dosimetric techniques suitable for these processes. Food Products8212;Food products may be treated with ionizing radiation, such as energetic electrons from accelerators or gamma rays from 60Co or 137Cs sources, or X-rays, for numerous purposes, including control of parasites and pathogenic microorganisms, insect disinfestation, growth and maturation inhibition, and shelf-life extension. Note 18212;Food irradiation specifications usually include upper and lower limits of absorbed dose: a minimum to ensure the intended beneficial effect and a maximum to avoid product degradation. For a given application, one or both of these values may be prescribed by regulations that have been established on the basis of available scientific data. Therefore, it is necessary to determine the capability of an irradiation facility to process within these absorbed-dose limits prior to the irradiation of the food product. Once this capability is established, it may be necessary to monitor and record the dose range delivered to the product during each production run to verify compliance with the process specifications within a predetermined level of confidence. Randomized Flow8212;In a stream of randomized flow; i.e. turbulent instead of laminar, variations occur which lead to a dose distribution for the particles entrained in the stream. The “idealized” maximum and minimum doses possible can be calculated based upon knowledge of the applied dose rate, the product dwell time in the irradiation cell and the product or bed thickness. The experimentally determined maximum and minimum doses delivered to each particle, should not be confused with these idealized dose limits. Treatment range8212;The location of the product (or of the dosimeter) in the fluidized bed or stream will determine its absorbed dose during passage through the radiation field. The experimental dose measurements in the fluidized bed or stream will define the range of product dose. The desired effect imparted to the product by irradiation will then be based upon this range of product dose and not upon maximum or minimum dose. Note 28212;In situations where a randomized mixing within the fluidized bed occurs with the intention that the particles or fluid elements pass through several radiation zones and accumulate a total dose with different dose rates, maximum and minimum dose values are difficult to determine and must be based on the results for the experimental dosimetry irradiated with the product . In the case of fluids, stirring after processing results only in effective treatment at a mean dose; no max and min dose measurement. For example, lethality curves will be determined as a function of this range of product treatment to the product in the fluidized bed or stream as determined by dosimetric techniques.1.1 This guide describes several dosimetry systems and methods suitable for the documentation of the irradiation of product transpor......

Standard Guide for Dosimetry In Radiation Processing of Fluidized Beds and Fluid Streams

ASTM D3648-04 放射性测量的标准实施规范

This practice was developed for the purpose of summarizing the various generic radiometric techniques, equipment, and practices that are used for the measurement of radioactivity. GENERAL INFORMATION Top 1.1 These practices cover a review of the accepted counting practices currently used in radiochemical analyses. The practices are divided into four sections:Section General Information 6 to 11Alpha Counting 12 to 22Beta Counting 23 to 33Gamma Counting 34 to 411.2 The general information sections contain information applicable to all types of radioactive measurements, while each of the other sections is specific for a particular type of radiation.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.

Standard Practices for the Measurement of Radioactivity

ASTM E2381-04 液化床和液体流的辐射处理的剂量测定法的标准指南

1.1 This guide describes several dosimetry systems and methods suitable for the documentation of the irradiation of product transported as fluid or in a fluidized bed.1.2 The sources of penetrating ionizing radiation included in this guide are electron beams, x-rays (bremsstrahlung) and gamma rays.1.3 Absorbed doses from 10 to 100,000 gray are considered, including applications such as disinfestation, disinfection, bioburden reduction, sterilization, crosslinking and graft modification of products, particularly powders and aggregates.1.4 This guide does not purport to address the safety concerns, if any, associated with the use of fluidized beds and streams incorporating sources of ionizing radiation. It is the responsibility of the user of this guide to establish appropriate safety and health practices and to determine compliance with regulatory limitations prior to use.

Standard Guide for Dosimetry In Radiation Processing of Fluidized Beds and Fluid Streams

ASTM D5163-04 核电厂运行时使用的I级涂层性能监督管理程序制定的标准指南

1.1 This guide covers procedures for establishing a program to monitor Coating Service Level I coating systems in operating nuclear power plants. Monitoring is an on going process of evaluating the condition of the in-service coating systems.1.2 It is the intent of this guide to provide a recommended basis for establishing a coatings monitoring program, not to mandate a singular basis for all programs. Variations or simplifications of the program described in this guide may be appropriate for each operating nuclear power plant depending on their licensing commitments. Similar guidelines are applicable for Service Level III and other areas outside containment.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.

Standard Guide for Establishing Procedures to Monitor the Performance of Service Level I Coatings in an Operating Nuclear Power Plant

ASTM D5163-04a 核电厂运行时使用的I级涂层性能监督管理程序制定的标准指南

1.1 This guide covers procedures for establishing a program to monitor Coating Service Level I coating systems in operating nuclear power plants. Monitoring is an on going process of evaluating the condition of the in-service coating systems.1.2 It is the intent of this guide to provide a recommended basis for establishing a coatings monitoring program, not to mandate a singular basis for all programs. Variations or simplifications of the program described in this guide may be appropriate for each operating nuclear power plant depending on their licensing commitments. Similar guidelines are applicable for Service Level III and other areas outside containment.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.

Standard Guide for Establishing Procedures to Monitor the Performance of Service Level I Coatings in an Operating Nuclear Power Plant

BS ISO 11338-2:2003 固定源辐射.气相和粒子相多环芳香烃的测定.样品准备、净化和测定

This part of ISO 11338 specifies procedures for sample preparation, clean-up and analysis for the determination of gas and particle-phase polycyclic aromatic hydrocarbons (PAH) in stack and waste gases. The analytical methods are capable of detecting sub-microgram concentrations of PAH per cubic metre of sample, depending on the type of PAH and the flue gas volume sampled. The methods described in this part of ISO 11338 are based on either high performance liquid chromatography (HPLC) or gas chromatography-mass spectrometry (GC-MS). NOTE ISO 11338-1 describes three methods and specifies minimum requirements for the sampling of PAH in stack and waste gases.

Stationary source emissions - Determination of gas and particle-phase polycyclic aromatic hydrocarbons - Sample preparation, clean-up and determination

BS ISO 11338-1:2003 固定源辐射.气体和粒子相多环芳香烃的测定.取样

This part of ISO 11338 describes methods for the determination of the mass concentration of polycyclic aromatic hydrocarbons (PAHs) in flue gas emissions from stationary sources such as aluminium smelters, coke works, waste incinerators, power stations, and industrial and domestic combustion appliances. This part of ISO 11338 describes three sampling methods, which are here regarded as of equivalent value, and specifies the minimum requirements for effective PAH sampling. The three sampling methods are the dilution method (A), the heated filter/condenser/adsorber method (B) and the cooled probe/adsorber method (C). All three methods are based on representative isokinetic sampling, as the PAHs are commonly associated with particles in flue gas. Information is provided to assist in the choice of the appropriate sampling method for the measurement application under consideration. This part of ISO 11338 is not applicable to the sampling of fugitive releases of PAHs. NOTE Methods for sample preparation, clean-up and analysis are described in ISO 11338-2 and are intended to be combined with one of the sampling methods described in this part of ISO 11338 to complete the whole measurement procedure.

Stationary source emissions - Determination of gas and particle-phase polycyclic aromatic hydrocarbons - Sampling

DIN 25482-11:2003 电离辐射测量的检测极限和判别阈.第11部分:反照率剂量仪测量法

Detection limit and decision threshold for ionizing radiation measurements - Part 11: Measurements using albedo dosimeters

DIN 25482-12:2003 电离辐射测量的检测极限和判别阈.第12部分:波谱伸展

This is intended to specify suitable values of statistics which allow an assessment of the detection capabilities in spectrometric nuclear radiation measurements and of the physical effect quantified by a measurand (for example a net of a spectrometric line in an alpha- or gamma-spectrum) which is determined by evaluation of a multichannel spectrum by unfolding methods. By use of one or multiple lines of a radionuclide activities or an activity concentration of this radionuclide can be evaluated with the help of a suitable model.

Detection limit and decision threshold for ionizing radiation measurements - Part 12: Unfolding of spectra

DIN 25482-13:2003 电离辐射测量的检测极限和判别阈.第13部分:移动物体的计数测量法

This standard specifies characteristical values, allowing an estimation of possible ionizing radiation on objects, moving during measurement relatively to the detector. Possible objects for a scanning measurement could be vehicles (i.e. railway carriages or ships), container, bulk articles (i.e. bags or luggage items) on a belt conveyor or during dispatching by a loading crane. Such measurements are normally made at frontier crossing points or near crossing trafic scanning rolling vehicles in order to detect unidentified or hidden radioactivites by measuring the increased pulse rate. This standard is based on the method of Bayes-Statistics.

Detection limit and decision threshold for ionizing radiation measurements - Part 13: Counting measurements on moving objects

NF M60-802-3:2002 核能.环境放射性测量.水.第3部分:通过液体闪烁测量β辐射物活性.同时出现氚和C14的特殊情况

Nuclear energy - Measurement of radioactivity in the environment - Water - Part 3 : beta emitters activity measurement by liquid scintillation - Particular case of simultaneous presence of tritium and carbon 14.

ISO 15382:2002 核能.放射性防护.外部受弱穿透辐射,特别是受到β辐射的核设施的辐射防护监测程序

This International Standard specifies a procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation and describes the procedure in radiation protection monitoring for external exposure to weakly penetrating radiation in nuclear installations. This radiation comprises β radiation, β radiation and conversion electron radiation as well as photon radiation with energies below 15 keV. This International Standard describes the procedure in radiation protection planning and monitoring as well as the measurement and analysis to be applied. It applies to regular nuclear power plant operation including maintenance, waste handling and decommissioning. The recommendations of this International Standard may also be transferred to other nuclear fields including reprocessing, if the area-specific issues are considered. This International Standard may also be applied to radiation protection at accelerator facilities and in nuclear medicine, biology and research facilities.

Nuclear energy - Radioprotection - Procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation

ASTM E1006-02 试验反应堆的物理放射量测定结果的分析和解释的标准实施规程,E 706(II)

The mechanical properties of steels and other metals are altered by exposure to neutron radiation. These property changes are assumed to be a function of chemical composition, metallurgical condition, temperature, fluence (perhaps also fluence rate), and neutron spectrum. The influence of these variables is not completely understood. The functional dependency between property changes and neutron radiation is summarized in the form of damage exposure parameters that are weighted integrals over the neutron fluence spectrum. The evaluation of neutron radiation effects on pressure vessel steels and the determination of safety limits require the knowlege of uncertainties in the prediction of radiation exposure parameters (for example, dpa (Practice E 693), neutron fluence greater than 1.0 MeV, neutron fluence greater than 0.1 MeV, thermal neutron fluence, etc.). This practice describes recommended procedures and data for determining these exposure parameters (and the associated uncertainties) for test reactor experiments. The nuclear industry draws much of its information from databases that come from test reactor experiments. Therefore, it is essential that reliable databases are obtained from test reactors to assess safety issues in Light Water Reactor (LWR) nuclear power plants.1.1 This practice covers the methodology summarized in to be used in the analysis and interpretation of physics-dosimetry results from test reactors.1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods.1.3 Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, exposure units, and neutron spectrum adjustment methods.1.4 This practice is directed towards the development and application of physics-dosimetry-metallurgical data obtained from test reactor irradiation experiments that are performed in support of the operation, licensing, and regulation of LWR nuclear power plants. It specifically addresses the physics-dosimetry aspects of the problem. Procedures related to the analysis, interpretation, and application of both test and power reactor physics-dosimetry-metallurgy results are addressed in Practices E 185, E 560, E 853, and E 1035, Guides E 900, E 2005E 2006and Test Method E 646.1.5 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 Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)