F81 通用核仪器 标准查询与下载

ANSI N43.10-2001 全景湿源存储γ辐照器(IV类)和干源存储γ辐照器(II类)的安全设计和使用

Applies to panoramic, wet source storage gamma irradiators (Category IV) and dry source storage gamma irradiators (Category II) that contain sealed gamma emitting sources for the irradiation of objects or materials. The standard establishes the criteria

Safe Design and Use of Panoramic, Wet Source Storage Gamma Irradiators (Category IV) and Dry Source Storage Gamma Irradiators (Category II)

ANSI N43.15-2001 独立湿源存储γ辐照器(III类)的安全设计和使用

Applies to self-contained, wet-source storage irradiators (Category III) that contain sealed gamma emitting sources for the irradiation of objects or materials. The standard establishes the criteria to be used in the proper design, fabrication, installat

Safe Design and Use of Self-Contained Wet Source Storage Gamma Irradiators (Category III)

DIN 25462:2000 放射性核素特殊环境测量用现场伽玛射线光谱测定法

The document deals with in-situ-gamma-ray spectrometry for nuclide specific environmental measurements of contaminations. The procedure is an evident and effective means to detect contaminations in the ground by gamma irradiating radionuclides and the resulting ambient dose rate of local single radionuclides. This is especially valid for dry or wet fall out/wash out contaminations.

In-situ-gamma-ray spectrometry for nuclide specific environmental measurements

ASTM C1463-00(2007) 化学和放射化学分析用含辐射和混合杂质的溶解玻璃的标准规程

1.1 These practices cover techniques suitable for dissolving glass samples that may contain nuclear wastes. These techniques used together or independently will produce solutions that can be analyzed by inductively coupled plasma atomic emission spectroscopy (ICP-AES), inductively coupled plasma mass spectrometry (ICP-MS), atomic absorption spectrometry (AAS), radiochemical methods and wet chemical techniques for major components, minor components and radionuclides.1.2 One of the fusion practices and the microwave practice can be used in hot cells and shielded hoods after modification to meet local operational requirements.1.3 The user of these practices must follow radiation protection guidelines in place for their specific laboratories.1.4 Additional information relating to safety is included in the text.1.5 The dissolution techniques described in these practices can be used for quality control of the feed materials and the product of plants vitrifying nuclear waste materials in glass.1.6 These practices are introduced to provide the user with an alternative means to Test Methods C 169 for dissolution of waste containing glass in shielded facilities. Test Methods C 169 is not practical for use in such facilities and with radioactive materials.1.7 The ICP-AES methods in Test Methods C 1109 and C 1111 can be used to analyze the dissolved sample with additional sample preparation as necessary and with matrix effect considerations. Additional information as to other analytical methods can be found in Test Method C 169.1.8 Solutions from this practice may be suitable for analysis using ICP-MS after establishing laboratory performance criteria.1.9 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 18.

Standard Practices for Dissolving Glass Containing Radioactive and Mixed Waste for Chemical and Radiochemical Analysis

ASTM C1463-00 化学和放射化学分析用含辐射和混合杂质的溶解玻璃的标准规程

1.1 These practices cover techniques suitable for dissolving glass samples that may contain nuclear wastes. These techniques used together or independently will produce solutions that can be analyzed by inductively coupled plasma atomic emission spectroscopy (ICP-AES), inductively coupled plasma mass spectrometry (ICP-MS), atomic absorption spectrometry (AAS), radiochemical methods and wet chemical techniques for major components, minor components and radionuclides.1.2 One of the fusion practices and the microwave practice can be used in hot cells and shielded hoods after modification to meet local operational requirements.1.3 The user of these practices must follow radiation protection guidelines in place for their specific laboratories.1.4 Additional information relating to safety is included in the text.1.5 The dissolution techniques described in these practices can be used for quality control of the feed materials and the product of plants vitrifying nuclear waste materials in glass.1.6 These practices are introduced to provide the user with an alternative means to Test Methods C 169 for dissolution of waste containing glass in shielded facilities. Test Methods C 169 is not practical for use in such facilities and with radioactive materials.1.7 The ICP-AES methods in Test Methods C 1109 and C 1111 can be used to analyze the dissolved sample with additional sample preparation as necessary and with matrix effect considerations. Additional information as to other analytical methods can be found in Test Method C 169.1.8 Solutions from this practice may be suitable for analysis using ICP-MS after establishing laboratory performance criteria.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 .

Standard Practices for Dissolving Glass Containing Radioactive and Mixed Waste for Chemical and Radiochemical Analysis

BS ISO 15556:1999 辐射处理用剂量系统的选择和校正指南

1 This guide provides the basis for selecting and cali-brating dosimctry systems used to measure absorbed dose in gamma-ray or X-ray fields and in electron beams used for radiation processing. It discusses the types of dosimetry systems that may be employed during calibration or on a routine basis as part of quality assurance in commercial radiation processing of products. This guide also discusses interpretation of absorbed dose and briefly outlines the uncertainties associated with the dosimetry measurements. The details of the calibration of the analytical instrumenta-tion are addressed in individual dosimetry system standard practices. 2 The absorbed-dose range covered is from about 1 Gy (100 rad) to 1 MGy (100 Mrad). Source energies covered are from 0.1 to 50 MeV photons and electrons. 3 Standard practices and guides for specific dosimetry systems and applications are covered in other standards. Dosimetry for radiation processing with neutrons or heavy charged particles is not covered in this guide. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Guide for selection and calibration of dosimetry systems for radiation processing

BS ISO 15566:1998 丙氨酸-EPR剂量测定系统的使用规程

1 This practice covers materials description, dosimeter preparation, instrumentation, and procedures for using the alanine-EPR dosimetry system for measuring the absorbed dose in materials irradiated with photons and electrons. The system is based on electron paramagnetic resonance (EPR) spectroscopy of the amino acid alanine. It is classified as a reference standard dosimetry system (see Guide E 1261). 2 This practice covers alanine-EPR dosimetry systems for dose measurements under the following conditions: 2.1 The absorbed dose range is between 1 and 10 Gy. 2.2 The absorbed dose rate is up to 10 Gy s for continuous radiation fields and up to 10 Gy s for pulsed radiation fields (1, 2). 2.3 The radiation energy range for photons is between 0.1 and 50 MeV and for electrons is between 0.3 and 50 MeV (1, 2). 2.4 The irradiation temperature is between -60 and +90℃ (2, 3). 3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for informa-tion only. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for use of the alanine-EPR dosimetry system

BS ISO 15561:1998 重铬酸盐剂量测定系统的使用规程

1 This practice covers the preparation, testing, and procedure for using the acidic aqueous silver dichromate dosimetry system to measure absorbed dose in water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the dichromate system. It is classified as a reference standard dosimetry system (see Guide E 1261). 2 This practice describes the spectrophotometric anal-ysis procedures for the dichromate system. 3 This practice applies only to γ-rays, x-rays, and high energy electrons. 4 This practice applies provided the following condi-tions are satisfied: 4.1 The absorbed dose range is from 2 × 10 to 5 × 10 Gy. 4.2 The absorbed dose rate does not exceed 600 Gy/ pulse with a pulse repetition rate not to exceed 12.5 Hz, or does not exceed an equivalent dose rate of 7.5 kGy/s from continuous sources (1). 4.3 For radionuclide gamma-ray sources, the initial photon energy shall be greater than 0.6 MeV. For bremsstrahlung photons, the initial energy of the electrons used to produce the bremsstrahlung photons shall be equal to or greater than 2 MeV. For electron beams, the initial electron energy shall be greater than 8 MeV. Note 1—The lower energy limits given are appropriate for a cylindrical dosimeter ampoule of 12 mm diameter. Corrections for displacement effects and dose gradient across the ampoule may be required for electron beams (2). The dichromate system may be used at lower energies by employing thinner (in the beam direction) dosimeter containers (see ICRU Report 35). 4.4 The irradiation temperature of the dosimeter shall be above 0℃ and should be below 80℃. Note 2—The temperature coefficient of dosimeter response is known only in the range of 5℃ to 50℃ (see 10.1.8). Use outside this range is not recommended. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use. Specific precau-tionary statements are given in Note 6.

Practice for use of a dichromate dosimetry system

BS ISO 15561:1999 重铬酸盐剂量测定系统的使用规程

1 This practice covers the preparation, testing, and procedure for using the acidic aqueous silver dichromate dosimetry system to measure absorbed dose in water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the dichromate system. It is classified as a reference standard dosimetry system (see Guide E 1261). 2 This practice describes the spectrophotometric anal-ysis procedures for the dichromate system. 3 This practice applies only to γ-rays, x-rays, and high energy electrons. 4 This practice applies provided the following condi-tions are satisfied: 4.1 The absorbed dose range is from 2 × 10 to 5 × 10 Gy. 4.2 The absorbed dose rate does not exceed 600 Gy/ pulse with a pulse repetition rate not to exceed 12.5 Hz, or does not exceed an equivalent dose rate of 7.5 kGy/s from continuous sources (1). 4.3 For radionuclide gamma-ray sources, the initial photon energy shall be greater than 0.6 MeV. For bremsstrahlung photons, the initial energy of the electrons used to produce the bremsstrahlung photons shall be equal to or greater than 2 MeV. For electron beams, the initial electron energy shall be greater than 8 MeV. Note 1—The lower energy limits given are appropriate for a cylindrical dosimeter ampoule of 12 mm diameter. Corrections for displacement effects and dose gradient across the ampoule may be required for electron beams (2). The dichromate system may be used at lower energies by employing thinner (in the beam direction) dosimeter containers (see ICRU Report 35). 4.4 The irradiation temperature of the dosimeter shall be above 0℃ and should be below 80℃. Note 2—The temperature coefficient of dosimeter response is known only in the range of 5℃ to 50℃ (see 10.1.8). Use outside this range is not recommended. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use. Specific precau-tionary statements are given in Note 6.

Practice for use of a dichromate dosimetry system

BS ISO 15566:1999 丙氨酸-EPR剂量测定系统的使用规程

1 This practice covers materials description, dosimeter preparation, instrumentation, and procedures for using the alanine-EPR dosimetry system for measuring the absorbed dose in materials irradiated with photons and electrons. The system is based on electron paramagnetic resonance (EPR) spectroscopy of the amino acid alanine. It is classified as a reference standard dosimetry system (see Guide E 1261). 2 This practice covers alanine-EPR dosimetry systems for dose measurements under the following conditions: 2.1 The absorbed dose range is between 1 and 10 Gy. 2.2 The absorbed dose rate is up to 10 Gy s for continuous radiation fields and up to 10 Gy s for pulsed radiation fields (1, 2). 2.3 The radiation energy range for photons is between 0.1 and 50 MeV and for electrons is between 0.3 and 50 MeV (1, 2). 2.4 The irradiation temperature is between -60 and +90℃ (2, 3). 3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for informa-tion only. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for use of the alanine-EPR dosimetry system

BS ISO 15571:1999 辐射处理过程中γ辐射设备剂量测定操作规程

1 This practice outlines dosimetric procedures to be followed in irradiator characterization, process qualification, and routine processing in a gamma irradiation facility. These procedures ensure that all product processed with ionizing radiation from isotopic gamma sources receive absorbed doses within a predetermined range. Other procedures re-lated to irradiator characterization, process qualification, and routine processing that may influence absorbed dose in the product are also discussed. Information about effective or regulatory dose limits is not within the scope of this document. Note 1—Dosimetry is one component of a total quality assurance program for adherence to good manufacturing practices. Specific applications of gamma radiation processing may require additional controls. 2 This practice describes general procedures applicable to all gamma radiation processing requiring absorbed doses within a predetermined range. For procedures specific to food irradiation, see Practice E 1204. The sterilization of medical devices is a regulated irradiation process with specific process control requirements. These requirements, including specific dosimetry requirements for medical device sterilization, are given in Refs (1) and (2). Guidelines for medical device sterilization are given in Refs (3) and (4). 3 For guidance in the selection, calibration, and use of specific dosimeters, and interpretation of absorbed dose in the product from dosimetry measurements, see Guide E 1261 and Practices E 666, E 668, E 1026, E 120S, E 1275, E 1276, E 1310, E 1400, E 1401, E 1538, E 1540, E 1607, and E 1650. For discussion of radiation dosimetry for gamma rays, see ICRU Report 14. 4 This standard does not purport to address all of the safely concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appro-priate safely and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for dosimetry in a gamma irradiation facility for radiation processing

BS ISO 15555:1999 硫酸高铈-三价铈剂量测定系统使用规程

1 This practice covers the preparation, testing, and procedure for using the ceric-cerous sulfate dosimetry system to measure absorbed dose in water when exposed to ionizing radiation. For simplicity, the system will be referred to as the ceriocerous system. It is classified as a reference standard dosimetry system (see Guide E 1261). 2 This practice describes both the spectrophotometric and the potentiometric readout procedures for the ceric-cerous systems. 3 This practice applies only to γ rays, X-rays, and high energy electrons. 4 This practice applies provided the following are satis-fied: 4.1 The absorbed-dose range shall be between 5 × 10 and 5 × 10 Gy (1). 4.2 The absorbed-dose rate shall be less than 10 Gy/s (1). 4.3 For radiomiclide gamma-ray sources, the initial photon energy shall be greater than 0.6 MeV. For bremsstrahlung photons, the initial energy of the electrons used to produce the bremsstrahlung photons shall be equal to or greater than 2 MeV. For electron beams, the initial electron energy shall be greater than 8 MeV. Note 1—The lower energy limits are appropriate for a cylindrical dosimeter ampoule of 12-mm diameter. Corrections for dose gradients across an ampoule of that diameter or less are not required. The ceru-cerous system may be used at lower energies by employing thinner (in the beam direction) dosimeter containers (see ICRU Report 35). 4.4 The irradiation temperature of the dosimeter should be between 0 and 62℃. 5 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for use of a ceric-cerous sulfate dosimetry system

BS ISO 15572:1999 辐射处理过程中剂量测定的不确定性评估指南

1 This guide defines possible sources of error in dosimetry performed in gamma, x-ray (bremsstrahlung) and electron irradiation facilities and offers procedures for esti-mating the resulting magnitude of the uncertainties in the measurement results. Basic concepts of measurement, esti-mate of the measured value of a quantity, "true" value, error and uncertainty are defined and discussed. Components of uncertainty are discussed and methods are given for evalu-ating and estimating their values. How these contribute to the standard uncertainty in the reported values of absorbed dose are considered and methods are given for calculating the combined standard uncertainty and an estimate of overall (expanded) uncertainty. The methodology for evalu-ating components of uncertainty follows ISO procedures (see 2.3). The traditional concepts of precision and bias are not used. Examples are given in five appendixes. 2 This guide assumes a working knowledge of statistics. Several statistical texts are included in the references (1, 2,3, 4). 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Guide for estimating uncertainties in dosimetry for radiation processing

BS ISO 15573:1998 能量在80KeV和300KeV之间的辐射处理用电子束设备剂量测定操作规程

1 This practice covers dosimetric procedures to be followed to determine the performance of low energy (300 keV or lest) single-gap electron beam radiation processing facilities. Other practices and procedures related to facility characterization, product qualification, and routine pro-cessing are also discussed. 2 The electron energy range covered in this practice is from 80 keV to 300 keV. Such electron beams can be generated by single-gap self-contained thermal filament or plasma source accelerators. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for dosimetry in an electron-beam facility for radiation processing at energies between 80 keV and 300 keV

BS ISO 15569:1998 能量在300KeV和25MeV之间的辐射处理用电子束装置的剂量测定操作规程

1 This practice covers dosimetric procedures to be followed in facility characterization, process qualification, and routine processing using electron beam radiation to ensure that the entire product has been treated with an acceptable range of absorbed doses. Other procedures related to facility characterization (including equipment documen-tation), process qualification, and routine product processing that may influence and may be used to monitor absorbed dose in the product are also discussed. Note 1—For guidance in the selection and calibration of dosimeters, see Guide E 1261. For further guidance in the selection, calibration, and use of specific dosimeters, and interpretation of absorbed dose in the product from dosimetry, also see Practices E668, E 1275, E 1276, E1431. E 1607, E 1631, and E 16S0. For use with electron energies above 5 MeV, see Practices E 1026, E 1205, E 1401, E 1538, andE 1540 for discussions of specific large volume dosimeters. For discussion of radiation dosimetry for pulsed radiation, see ICRU Report 34. When considering a dosimeter type, be cautious of influences from dose rates and accelerator pulse rates and widths (if applicable). 2 The electron energy range covered in this practice is between 300 keV and 25 MeV, although there are some discussions for other energies. Note 2—For application of dosimetry in the characterization and operation of electron beam and X-ray (bremsstrahlung) irradiation facilities for food processing, see Practice E 1431. For application of dosimetry in the characterization and operation of irradiation facilities using X-ray radiation (bremsstrahlung), see Practice E 1608. 3 Dosimetry is one component of a total quality assur-ance program for adherence to good manufacturing prac-tices. Specific applications of electron beam radiation pro-cessing may require additional controls. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for dosimetry in an electron-beam facility for radiation processing at energies between 300 keV and 25 MeV

BS ISO 15568:1998 电子束剂量测量和剂量仪校正用热量计剂量测定系统的使用规程

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. 2 This practice applies to electron beams in the energy range from 4 to 12 MeV. 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. 4 The averaged absorbed dose rate range shall generally be greater than 10 Gy·s, but depends on the same conditions as above. 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. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for use of calorimetric dosimetry systems for electron beam dose measurements and dosimeter calibrations

BS ISO 15568:1999 电子束剂量测量和剂量仪校正用热量计剂量测定系统的使用规程

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. 2 This practice applies to electron beams in the energy range from 4 to 12 MeV. 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. 4 The averaged absorbed dose rate range shall generally be greater than 10 Gy·s, but depends on the same conditions as above. 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. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for use of calorimetric dosimetry systems for electron beam dose measurements and dosimeter calibrations

IEEE N42.14-1999 放射性核素的γ射线放射率测量用锗能谱仪的校正和使用

This standard establishes methods for the calibration and use of germanium (Ge) spectrometers for the measurement of gamma-ray energies and emission rates over the energy range from 59 keV to approximately 3000 keV, and the calculation of source activities from these measurements. This standard establishes minimum requirements for automated peak finding and methods for measuring the full-energy peak efficiency with calibrated sources.

Calibration and use of germanium spectrometers for the measurement of gammma-ray emission rates of radionuclides

DIN IEC 61336:1999 核测量仪器.使用电离辐射的厚度测量系统.定义和试验方法

Nuclear instrumentation - Thickness measurement systems utilizing ionizing radiation - Definitions and test methods (IEC 61336:1996)

ANSI N42.27-1999 固态γ放射源不均匀性的测定

The scope of this standard is limited to commercially-produced, solid radioactive flood sources intended to aid in the determination of the system field uniformity of scintillation cameras used in nuclear medicine. This standard is intended to provide a

Determination of Uniformity of Solid Gamma-Emitting Flood Sources