A58 电离辐射计量 标准查询与下载

JJG 393-2003 辐射防护用X、γ辐射剂量当量(率)仪和监测仪

X and Gamma Radiation Dose Equivalent (Rate) Meters and Monitors Used in Radiation Protection

ASTM ISO/ASTM 51631-03 电子束剂量计测量和剂量计校准用量热剂量测定法系统使用的标准惯例

4.1 This practice is applicable to the use of a calorimeter for the measurement of absorbed dose in electron beams, the qualification of electron irradiation facilities, periodic checks of operating parameters of electron irradiation facilities, and calibration of other dosimeters in electron beams. NOTE 1 - For additional information of the use of dosimetry in electron accelerator facilities, see ISO/ASTM Practices 51431 and 51649, and ICRU Reports 34 and 35, and Refs (1-3).4 4.2 The calorimeters described in this practice are not primary-standard dosimeters. They may be used as transferstandard dosimeters or as internal standards at an electron beam irradiation facility, or may be routine dosimeters used for routine dose measurements. The calorimeters are calibrated by comparison with transfer-standard dosimeters. 4.3 The dose measurement is based on the measurement of the temperature rise in an absorber (calorimetric body) irradiated by an electron beam. Different absorbing materials are used, but the response is usually defined in terms of dose to water. 4.4 The absorbed dose in other materials irradiated under equivalent conditions may be calculated. Procedures for making such calculations are given in ASTM Practices E 666 and E 668, ISO/ASTM Guide 51261, and Ref (1). 4.5 The average absorbed dose in the volume of the calorimetric body is measured. Dose gradients may occur in this volume and may have to be considered when estimating dose in other materials. 4.6 The calorimetric bodies of the calorimeters described in this practice are made from low atomic number materials. The electron fluences within these calorimetric bodies will be approximately equal when irradiated with electron beams of 1.5 MeV or higher. Calibration in terms of dose to water is possible for these calorimeters. 4.6.1 Calorimeters for use at industrial electron accelerators have been constructed using graphite, polystyrene or a Petri dish filled with water as the calorimetric body (4-10). The thickness of the calorimetric body shall be less than the range of the electrons for the specified material. 4.6.2 Polymeric materials other than polystyrene may be used for calorimetric measurements. Polystyrene is used because it is known to be resistant to radiation (11) and because no exo- or endothermic reactions take place (12).1.1 This practice covers the preparation and use of semi-adiabatic calorimeters for measurement of absorbed dose and routine dosimeter calibration when irradiated with electrons for radiation processing applications. The calorimeters are either transported by a conveyor past a scanned electron beam or are stationary in a broadened beam. 1.2 This practice applies to electron beams in the energy range from 1.5 to 12 MeV.1.3 The absorbed dose range depends on the absorbing material and the irradiation and measurement conditions. Minimum dose is approximately 100 Gy and maximum dose is approximately 50 kGy.1.4 The averaged absorbed-dose rate range shall generally be greater than 10 Gys1.1.5 The temperature range for use of these calorimeters depends on the thermal resistance of the materials, on the calibration range of the temperature sensor, and on the sensitivity of the measurement device.1.6 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 Use of Calorimetric Dosimetry Systems for Electron Beam Dose Measurements and Routine Dosimeter Calibration

ASTM D3648-03 放射性测量规程

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 E666-03 γ或X辐射吸收剂量计算的标准实施规范

The absorbed dose is a more meaningful parameter than exposure for use in relating the effects of radiation on materials. It expresses the energy absorbed by the irradiated material per unit mass, whereas exposure is related to the amount of charge produced in air per unit mass. Absorbed dose, as referred to here, implies that the measurement is made under conditions of charged particle (electron) equilibrium (see Appendix X1). In practice, such conditions are not rigorously achievable but, under some circumstances, can be approximated closely. Different materials, when exposed to the same radiation field, absorb different amounts of energy. Using the techniques of this standard, charged particle equilibrium must exist in order to relate the absorbed dose in one material to the absorbed dose in another. Also, if the radiation is attenuated by a significant thickness of an absorber, the energy spectrum of the radiation will be changed, and it will be necessary to correct for this. Note 18212;For comprehensive discussions of various dosimetry methods applicable to the radiation types and energies and absorbed dose rate ranges discussed in this method, see ICRU Reports 14, 21, and 34.1.1 This practice presents a technique for calculating the absorbed dose in a material from knowledge of the radiation field, the composition of the material, (1-5) and a related measurement. The procedure is applicable for X and gamma radiation provided the energy of the photons fall within the range from 0.01 to 20 MeV.1.2 A method is given for calculating the absorbed dose in a material from the knowledge of the absorbed dose in another material exposed to the same radiation field. The procedure is restricted to homogeneous materials composed of the elements for which absorption coefficients have been tabulated (2). It also requires some knowledge of the energy spectrum of the radiation field produced by the source under consideration. Generally, the accuracy of this method is limited by the accuracy to which the energy spectrum of the radiation field is known.1.3 The results of this practice are only valid if charged particle equilibrium exists in the material and at the depth of interest. Thus, this practice is not applicable for determining absorbed dose in the immediate vicinity of boundaries between materials of widely differing atomic numbers. For more information on this topic, see Practice E 1249.1.4 Energy transport computer codes exist that are formulated to calculate absorbed dose in materials more precisely than this method. To use these codes, more effort, time, and expense are required. If the situation warrants, such calculations should be used rather than the method described here.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 Calculating Absorbed Dose From Gamma or X Radiation

KS A ISO 11929-1:2002 电离辐射测量的检测限值和决定范围的测定.第1部分:无样本处理影响的技术测定原理与应用

이 규격은 시료 처리의 영향 없이 전리 방사선 측정에서 검출 능력 평가에 적절한 통계값을

Determination of the detection limit and decision threshold for ionizing radiation measurements-Part 1:Fundamentals and application to counting measurements without the influence of sample treatment

KS A ISO 11929-4:2002 电离辐射测量的检测限值和决定范围的测定.第4部分:样本处理不影响线形化合物速率计检测原理和应用

이 규격은 시료 처리의 영향 없이 선형 아날로그 선량계를 이용하여 전리 방사선 측정에서 검

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

KS A ISO 11929-2:2002 电离辐射测量的检测限值和决定范围的测定.第2部分:样本处理影响计数检测原理和应用

이 규격은 시료 처리의 영향 없이 전리 방사선 측정에서 검출 능력 평가에 적절한 통계값을

Determination of the detection limit and decision threshold for ionizing radiation measurements-Part 2:Fundamentals and application to counting measurements with the influence of sample treatment

KS A ISO 11929-3:2002 电离辐射测量的检测限值和决定范围的测定.第3部分:样本处理不影响高分解能γ光谱测定法计数检测原理和应用

이 규격에서는 시료 처리의 영향 없이 전리 방사선 측정에 있어서 고분해 감마 분광 분석의

Determination of the detection limit and decision threshold for ionizing radiation measurements-Part 3:Fundamentals and application to counting measurements by high resolution gamma spectrometry without the influence of sample treatment

KS A 4440-2002 放射性表面除污.除污的难易度测试与评估方法

이 국제 표준에 정의된 규정은 방사성 물질에 의해 오염된 표면의 시험에 적용한다. 이 시험

Decontamination of radioactively contaminated surface-Method for testing and assessing the ease of decontamination

KS A 4901-2002 X射线设备用放散射网格的特性

이 규격은 X선 패턴의 콘트라스트를 향상시키기 위해, 특히 환자 몸에서 발생된 산란 방사선

Characteristics of anti-scatter grids used in X-ray equipment

NF M60-516-1:2002 参考中子辐射.第1部分:生产的特性和方法

Reference neutron radiations - Part 1 : characteristics and methods of production.

ASTM E1297-02 通过铌的辐射活化测定快中子反应速率的标准试验方法

1.1 This test method describes procedures for measuring reaction rates by the activation reaction 93Nb(n,n) 93mNb.1.2 This activation reaction is useful for monitoring neutrons with energies above approximately 0.5 MeV and for irradiation times up to about 30 years.1.3 With suitable techniques, fast-neutron reaction rates for neutrons with energy distribution similar to fission neutrons can be determined in fast-neutron fluences above about 1016cm 2. In the presence of high thermal-neutron fluence rates (>10 12cm2183;s-1), the transmutation of 93mNb due to neutron capture should be investigated. In the presence of high-energy neutron spectra such as are associated with fusion and spallation sources, the transmutation of 93mNb by reactions such as (n,2n) may occur and should be investigated.1.4 Procedures for other fast-neutron monitors are referenced in Practice E 261.1.5 Fast-neutron fluence rates can be determined from the reaction rates provided that the appropriate cross section information is available to meet the accuracy requirements.1.6 The values stated in SI units are to be regarded as the standard.1.7 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium

ASTM ISO/ASTM 51631-02 电子束剂量计测量和剂量计校准用量热剂量测定法系统使用的标准惯例

1.1 This practice covers the preparation and use of semi-adiabatic calorimeters for measurement of absorbed dose in graphite, water, or polystyrene when irradiated with electrons. The calorimeters are either transported by a conveyor past a scanned electron beam or are stationary in a broadened beam. It also covers the use of these calorimeters to calibrate dosimeter systems in electron beams intended for radiation processing applications.1.2 This practice applies to electron beams in the energy range from 4 to 12 MeV.1.3 The absorbed dose range depends on the absorbing material and the irradiation and measurement conditions. Minimum dose is approximately 100 Gy and maximum dose is approximately 50 kGy.1.4 The averaged absorbed dose rate range shall generally be greater than 10 Gys1, but depends on the same conditions as above.1.5 The temperature range for use of these calorimeters depends on the thermal resistance of the materials and on the calibration range of the temperature sensor.1.6 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 Use of Calorimetric Dosimetry Systems for Electron Beam Dose Measurements and Dosimeter Calibrations

GOST R 8.594-2002 确保测量一致性的国家体系.辐射控制的度量确保.一般原则

State system for ensuring the uniformity of measurements. The metrological ensuring of radiation control. General principles

JJF 1016-2002 计量器具型式评价大纲编写导则

The Rules for Drafting Program of Pattern Evaluation of Measuring Instruments

JJG 969-2002 γ放射免疫计数器检定规程

Verification Regulation of Gamma Radioimmunoassay Counters

KS A 4504-2001 放射性表面污染评估

이 규격은 β선(최대 에너지가 0.15MeV 이상) 또는 &##61537; 선을 방출

Evaluation of radioactive surface contamination

KS A 4442-2001 水中γ线检测型监视器

이 규격은 방사선 방호를 목적으로 하여 시설의 배수계 등에서의 수중의 γ방출체의 방사능 농

Monitors for gamma emitting radionuclides in water

KS A 4812-2001 放射性气雾用高性能过滤器

이 규격은 방사성 에어로졸을 제거하는 목적으로, 원자력 시설 등의 배기계, 환기 공조 계통

HEPA Filters for radioactive aerosols

KS A 4441-2001 放射性表面污染测量仪

이 규격은 물체 표면 위의 방출체 또는 최대 에너지 0.15MeV 이상의 선을 방출하는 방

Portable radioactive surface contamination meter