17.240 (Radiation measurements) 标准查询与下载

ASTM ISO/ASTM 51026-15 弗里克剂量测定系统的使用标准实施规程

4.1 The Fricke dosimetry system provides a reliable means for measurement of absorbed dose to water, based on a process of oxidation of ferrous ions to ferric ions in acidic aqueous solution by ionizing radiation (ICRU 80, PIRS-0815,(4)). In situations not requiring traceability to national standards, this system can be used for absolute determination of absorbed dose without calibration, as the radiation chemical yield of ferric ions is well characterized (see Appendix X3). 4.2 The dosimeter is an air-saturated solution of ferrous sulfate or ferrous ammonium sulfate that indicates absorbed dose by an increase in optical absorbance at a specified wavelength. A temperature-controlled calibrated spectrophotometer is used to measure the absorbance. 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 dosimetry system. The Fricke dosimetry system may be used as either a reference standard dosimetry system or a routine dosimetry system. 1.2 This practice is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for the Fricke dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628. 1.3 The practice describes the spectrophotometric analysis procedures for the Fricke dosimetry system. 1.4 This practice applies only to gamma radiation, X-radiation (bremsstrahlung), and high-energy electrons. 1.5 This practice applies provided the following are satisfied: 1.5.1 The absorbed dose range shall be from 20 to 400 Gy (1).2 1.5.2 The absorbed-dose rate does not exceed 106 Gy·s−1 (2). 1.5.3 For radioisotope gamma sources, the initial photon energy is greater than 0.6 MeV. For X-radiation (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. Note 1: The lower energy limits given are app......

Standard Practice for Using the Fricke Dosimetry System

ASTM D3648-14 测量放射性的标准操作规程

5.1 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. 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 8199;8199;8199;General Information 6 – 11 8199;8199;8199;Alpha Counting 12 – 22 8199;8199;8199;Beta Counting 23 – 33 8199;8199;8199;Gamma Counting 34 – 41 1.2 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 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 ......

Standard Practices for the Measurement of Radioactivity

ASTM E666-14 计算伽马或X辐射吸收剂量的标准实施规程

4.1 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. 4.2 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 1—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 34 and 80. 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)2,3 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. All 92 natural elements are tabulated in (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 E1249. 1.4 Energy transport computer codes4 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

ASTM ISO/ASTM 51650-13 醋酸纤维剂量测定系统使用的标准实施规程

The CTA dosimetry system provides a means for measuring absorbed dose based on a change in optical absorbance in the CTA dosimeter following exposure to ionizing radiation (5, 7-14). CTA dosimetry systems are commonly used in industrial radiation processing, for example in the modification of polymers and sterilization of health care products. CTA dosimeter film is particularly useful in absorbed dose mapping because it is available in a strip format and if measured using a strip measurement device, it can provide a dose map with higher resolution than using discrete points.1.1 This is a practice for using a cellulose triacetate (CTA) dosimetry system to measure absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water. The CTA dosimetry system is classified as a routine dosimetry system. 1.2 The CTA dosimeter is classified as a type II dosimeter on the basis of the complex effect of influence quantities on its response (see ASTM Practice E2628). 1.3 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ASTM E2628 “Practice for Dosimetry in Radiation Processing” for a CTA dosimetry system. It is intended to be read in conjunction with ASTM E2628. 1.4 This practice covers the use of CTA dosimetry systems under the following conditions: 1.4.1 The absorbed dose range is 10 kGy to 300 kGy. 1.4.2 The absorbed-dose rate range is 3 Gy/s to 4×1010 Gy/s (1). 1.4.3 The photon energy range is 0.1 to 50 MeV. 1.4.4 The electron energy range is 0.2 to 50 MeV. 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 Use of Cellulose Acetate Dosimetry Systems

ASTM E1894-13a 选择脉冲X射线源用的剂量测定系统的标准指南

4.1 Flash X-ray facilities provide intense bremsstrahlung radiation environments, usually in a single sub-microsecond pulse, which often fluctuates in amplitude, shape, and spectrum from shot to shot. Therefore, appropriate dosimetry must be fielded on every exposure to characterize the environment, see ICRU Report 34. These intense bremsstrahlung sources have a variety of applications which include the following: 4.1.1 Generation of X-ray and gamma-ray environments similar to that from a nuclear weapon burst. 4.1.2 Studies of the effects of X-rays and gamma rays on materials. 4.1.3 Studies of the effects of radiation on electronic devices such as transistors, diodes, and capacitors. 4.1.4 Vulnerability and survivability testing of military systems and components. 4.1.5 Computer code validation studies. 4.2 This guide is written to assist the experimenter in selecting the needed dosimetry systems (not all radiation parameters must be measured in a given experiment) for use at pulsed X-ray facilities. This guide also provides a brief summary of the information on how to use each of the dosimetry systems. Other guides (see Section 2) provide more detailed information on selected dosimetry systems in radiation environments and should be consulted after an initial decision is made on the appropriate dosimetry system to use. There are many key parameters which describe a flash X-ray source, such as dose, dose rate, spectrum, pulse width, etc., such that typically no single dosimetry system can measure all the parameters simultaneously. 1.1 This guide provides assistance in selecting and using dosimetry systems in flash X-ray experiments. Both dose and dose-rate techniques are described. 1.2 Operating characteristics of flash X-ray sources are given, with emphasis on the spectrum of the photon output. 1.3 Assistance is provided to relate the measured dose to the response of a device under test (DUT). The device is assumed to be a semiconductor electronic part or system.

Standard Guide for Selecting Dosimetry Systems for Application in Pulsed X-Ray Sources

ASTM ISO/ASTM 52701-13 辐射处理用剂量计和剂量测量系统性能特征描述的标准指南

4.1 Ionizing radiation produces physical or chemical changes in many materials that can be measured and related to absorbed dose. Materials with radiation-induced changes that have been thoroughly studied can be used as dosimeters in radiation processing. Note 3—The scientific basis for commonly used dosimetry systems and detailed descriptions of the radiation-induced interactions are given in ICRU Report 80. 4.2 Before a material can be considered for use as a dosimeter, certain characteristics related to manufacture and measurement of its response to ionizing radiation need to be considered, including: 4.2.1 the ability to manufacture batches of the material with evidence demonstrating a reproducible radiation-induced change, 4.2.2  the availability of instrumentation for measuring this change, and 4.2.3 the ability to take into account effects of influence quantities on the dosimeter response and on the measured absorbed-dose values. 4.3 Dosimeter/dosimetry system characterization is conducted to determine the performance characteristics for a dosimeter/dosimetry system related to its capability for measuring absorbed dose. The information obtained from dosimeter/dosimetry system characterization includes the reproducibility of the measured absorbed-dose value, the useful absorbed-dose range, effects of influence quantities, and the conditions under which the dosimeters can be calibrated and used effectively.Note 4—When dosimetry systems are calibrated under the conditions of use, effects of influence quantities may be minimized or eliminated, because the effects can be accounted for or incorporated into the calibration method (see ISO/ASTM Practice 51261). 4.4  The influence quantities of importance might differ for different radiation processing applications and facilities. For references to standards describing different applications and facilities, see ISO/ASTM Practice 52628. 4.5 Classification of a dosimeter as a type I dosimeter or a type II dosimeter (see ISO/ASTM Practice 52628) is based on performance characteristics related to the effects of influence quantities obtained from dosimeter/dosimetry system characterization. 4.6  The dosimeter manufacturer or supplier is responsible for providing a product that meets the performance characteristics defined in product specifications, certificates of conformance, or similar types of documents. Dosimeter specifications should be developed based on dosimeter/dosimetry system characterization. 4.7 The user has the responsibility for ensuring that the dosimetry requirements for the specific applications are met and that dosimeter/dosimetry system characterization information has been considered in: 4.7.1 determining the suitability of the dosimeter or dosimetry system for the specific application (see ISO/ASTM Practice 52628), 4.7.2  selecting the calibration method (see ISO/ASTM Guide 51261), 4.7.3 establishing dosimetry sy......

Standard Guide for Performance Characterization of Dosimeters and Dosimetry Systems for Use in Radiation Processing

ASTM ISO/ASTM 51956-13 使用辐射加工用热致发光剂量测定(TLD)系统的标准实施规程

4.1 In radiation processing, TLDs are mainly used in the irradiation of blood products (see ISO/ASTM Practice 51939) and insects for sterile insect release programs (see ISO/ASTM Guide 51940). TLDs may also be used in other radiation processing applications such as the sterilization of medical products, food irradiation, modification of polymers, irradiation of electronic devices, and curing of inks, coatings and adhesives. (See ISO/ASTM Practices 51608, 51649, and 51702.) 4.2 For radiation processing, the absorbed-dose range of interest is from 1 Gy to 100 kGy. Some TLDs can be used in applications requiring much lower absorbed doses (for example, for personnel dosimetry), but such applications are outside the scope of this practice. Examples of TLDs and applicable dose ranges are given in Table 1. Information on various types of TLDs and their applications can be found in Refs (1-10).7 1.1 This practice covers procedures for the use of thermoluminescence dosimeters (TLDs) to measure the absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water. Thermoluminescence-dosimetry systems (TLD systems) are generally used as routine dosimetry systems. 1.2 The thermoluminescence dosimeter (TLD) is classified as a type II dosimeter on the basis of the complex effect of influence quantities on the dosimeter response. See ISO/ASTM Practice 52628. 1.3 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM 52628 “Practice for Dosimetry in Radiation Processing” for a TLD system. It is intended to be read in conjunction with ISO/ASTM 52628. 1.4 This practice covers the use of TLD systems under the following conditions: 1.4.1 The absorbed-dose range is from 1 Gy to 10 kGy. 1.4.2 The absorbed-dose rate is between 1 × 10-2 and 1 × 1010 Gy s-1. 1.4.3 The radiation-energy range for photons and electrons is from 0.1 to 50 MeV. 1.5 This practice does not cover measurements of absorbed dose in materials subjected to neutron irradiation. 1.6 This practice does not cover procedures for the use of TLDs for determining absorbed dose in radiation-hardness testing of electronic devices. Procedures for the use of TLDs for radiation-hardness testing are given in ASTM Practice E668. 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 Practice for Use of Thermoluminescence-Dosimetry (TLD) Systems for Radiation Processing

ASTM ISO/ASTM 51818-13 能量在80至300 keV的辐射加工用电子束设备的剂量测定的标准实施规程

A variety of irradiation processes uses low energy electron beam facilities to modify product characteristics. Dosimetry requirements, the number and frequency of measurements, and record keeping requirements will vary depending on the type and end use of the products being processed. Dosimetry is often used in conjunction with physical, chemical, or biological testing of the product, to help verify specific treatment parameters. Note 18212;In many cases dosimetry results can be related to other quantitative product properties; for example, gel fraction, melt flow, modulus, molecular weight distribution, or cure analysis tests. Radiation processing specifications usually include a minimum or maximum absorbed dose limit, or both. For a given application these limits may be set by government regulation or by limits inherent to the product itself. Critical process parameters must be controlled to obtain reproducible dose distribution in processed materials. The electron beam energy, beam current, beam width and process line speed (conveying speed) affect absorbed dose. Before any electron beam facility can be routinely utilized, it must be validated to determine its effectiveness. This involves testing of the process equipment, calibrating the measuring instruments and the dosimetry system, and demonstrating the ability to consistently deliver the required dose within predetermined specifications. In order for a dosimetry system to be effective in low-energy electron irradiation applications and to measure doses with an acceptable level of uncertainty, it is necessary to calibrate the dosimetry system under irradiation conditions that are consistent with those encountered in routine use. For example, a dosimetry system calibration conducted using penetrating gamma radiation or high energy electrons may result in significantly inaccurate dose measurement when the dosimetry system is used at low energy electron beam facilities. Details of calibration are discussed in Section 5.1.1 This practice covers dosimetric procedures to be followed in installation qualification, operational qualification and performance qualification (IQ, OQ, PQ), and routine processing at electron beam facilities to ensure that the product has been treated with an acceptable range of absorbed doses. Other procedures related to IQ, OQ, PQ, and routine product processing that may influence absorbed dose in the product are also discussed. 1.2 The electron beam energy range covered in this practice is between 80 and 300 keV, generally referred to as low energy. 1.3 Dosimetry is only one component of a total quality assurance program for an irradiation facility. Other measures may be required for specific applications such as medical device sterilization and food preservation. 1.4 Other specific ISO and ASTM standards exist for the irradiation of food and the radiation sterilization of health care products. For the radiation sterilization of health care products, see ISO 11137. In those areas covered by ISO 11137, that standard takes precedence. For food irradiation, see ISO 14470:2011. Information about effective or regulatory dose limits for food products is not within the scope of this practice (see ASTM F1355 and F1356). 1.5 This document is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with ASTM E2232, “Practice for Dosimetry in Radiati......

Standard Practice for Dosimetry in an Electron Beam Facility for Radiation Processing at Energies Between 80 and 300 keV

ASTM ISO/ASTM 51261-13 辐射处理用常规剂量测定系统校准的标准实施规程

4.1 Ionizing radiation is used to produce various desired effects in products. Examples of applications include the sterilization of medical products, microbial reduction, modification of polymers and electronic devices, and curing of inks, coatings, and adhesives.4.2 Absorbed-dose measurements, with statistical controls and documentation, are necessary to ensure that products receive the desired absorbed dose. These controls include a program that addresses requirements for calibration of routine dosimetry system.4.3 A routine dosimetry system calibration procedure as described in this document provides the user with a dosimetry system whose dose measurements are traceable to national or international standards for the conditions of use (see Annex A4). The dosimetry system calibration is part of the user抯 measurement management system.1.1 This practice specifies the requirements for calibrating routine dosimetry systems for use in radiation processing, including establishing measurement traceability and estimating uncertainty in the measured dose using the calibrated dosimetry system.NOTE 1桼egulations or other directives exist in many countries that govern certain radiation processing applications such as sterilization of healthcare products and radiation processing of food requiring that absorbed-dose measurements be traceable to national or international standards (ISO 11137-1, Refs (1-3)2).1.2 The absorbed-dose range covered is up to 1 MGy.1.3 The radiation types covered are photons and electrons with energies from 80 keV to 25 MeV.1.4 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ASTM E2628 揚ractice for Dosimetry in Radiation Processing?for the calibration of routine dosimetry systems. It is intended to be read in conjunction with ASTM E2628 and the relevant ASTM or ISO/ASTM standard practice for the dosimetry system being calibrated referenced in Section 2.1.5 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 Calibration of Routine Dosimetry Systems for Radiation Processing

ASTM E1026-13 使用弗里克剂量测定系统的标准实施规范

4.1 The Fricke dosimetry system provides a reliable means for measurement of absorbed dose to water, based on a process of oxidation of ferrous ions to ferric ions in acidic aqueous solution by ionizing radiation (4). In situations not requiring traceability to national standards, this system can be used for absolute determination of absorbed dose without calibration, as the radiation chemical yield of ferric ions is well characterized (see Appendix X3). 4.2 The dosimeter is an air-saturated solution of ferrous sulfate or ferrous ammonium sulfate that indicates absorbed dose by an increase in optical absorbance at a specified wavelength. A temperature-controlled calibrated spectrophotometer is used to measure the absorbance (ICRU 80). 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 dosimetry system. The Fricke dosimetry system may be used as either a reference standard dosimetry system or a routine dosimetry system. 1.2 This practice is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of Practice E2628 for the Fricke dosimetry system. It is intended to be read in conjunction with Practice E2628. 1.3 The practice describes the spectrophotometric analysis procedures for the Fricke dosimetry system. 1.4 This practice applies only to gamma radiation, X-radiation (bremsstrahlung), and high-energy electrons. 1.5 This practice applies provided the following are satisfied: 1.5.1 The absorbed dose range shall be from 20 to 400 Gy (1).2 1.5.2 The absorbed-dose rate does not exceed 106 Gy·s−1 (2). 1.5.3 For radioisotope gamma sources, the initial photon energy is greater than 0.6 MeV. For X-radiation (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. Note 1—The lower ......

Standard Practice for Using the Fricke Dosimetry System

ASTM E393-13 通过分析由裂变剂量计产生的钡-140来测定反应速率的标准试验方法

5.1 Refer to Guide E844 for the selection, irradiation, and quality control of neutron dosimeters. 5.2 Refer to Practice E261 for a general discussion of the measurement of neutron fluence rate and fluence. The neutron spectrum must be known in order to measure neutron fluence rates with a single detector. Also it is noted that cross sections are continuously being reevaluated. The latest recommended cross sections and details on how they can be obtained are discussed in Guide E1018. 5.3 The reaction rate of a detector nuclide of known cross section, when combined with information about the neutron spectrum, permits the determination of the magnitude of the fluence rate impinging on the detector. Furthermore, if results from other detectors are available, the neutron spectrum can be defined more accurately. The techniques for fluence rate and fluence determinations are explained in Practice E261. 5.4 140Ba is a radioactive nuclide formed as a result of uranium fission. Although it is formed in fission of any heavy atom, the relative yield will differ. Recommended fission yields for 140Ba production are given in Table 1. The direct (independent) fission yield of the daughter product 140La, which is counted, is given in Table 2. These independent fission yields are relatively low compared to the 140Ba cumulative fission yield and will not significantly affect the accuracy of the nondestructive procedure and need not be considered. 5.5 The half-life of 140Ba is 12.752 days. Its daughter 140La has a half-life of 1.6781 days.3 The comparatively long half-life of 140Ba allows the counting to be delayed several weeks after irradiation in a high-neutron field. However, to achieve maximum sensitivity the daughter product 140La should be counted five to six days after the irradiation during nondestructive analysis or five to six days after chemical separation if the latter technique is used. An alternative method after chemical separation is to count the 140Ba directly. 5.6 Because of its 12.752 day half-life and substantial fission yield, 140Ba is useful for irradiation times up to about six weeks in moderate intensity fields. The number of fissions produced should be approximately 109 or greater for good counting statistics. Also, if the irradiation time is substantially longer than six weeks, the neutron fluence rate determined will apply mainly to the neutron field existing during the latter part of the irradiation.......

Standard Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters

ASTM ISO/ASTM 52116-13 自给式干贮存伽玛辐照器剂量测定的标准实施规程

4.1 The design and operation of a self-contained irradiator should ensure that reproducible absorbed doses are obtained when the same irradiation parameters are used. Dosimetry is performed to determine the relationship between the irradiation parameters and the absorbed dose.4.1.1 For most applications, the absorbed dose is expressed as absorbed dose to water (see ISO/ASTM Practice 51261). For conversion of absorbed dose to water to that to other materials, for example, silicon, see Annex A1 of ISO/ASTM Practice 51261.4.2 Self-contained dry-storage gamma irradiators contain properly shielded radioactive sources, namely 137Cs or 60Co, that emit ionizing electromagnetic radiation (gamma radiation). These irradiators have an enclosed, accessible irradiator sample chamber connected with a sample positioning system, for example, irradiator drawer, rotor, or irradiator turntable, as part of the irradiation device.4.3 Self-contained dry-storage gamma irradiators can be used for many radiation processing applications, including the calibration irradiation of dosimeters; studies of dosimeter influence quantities; radiation effects studies, and irradiation of materials or biological samples for process compatibility studies; batch irradiations of microbiological, botanical, or in-vitro samples; irradiation of small animals; radiation 8220;hardness8221; testing of electronics components and other materials; and batch radiation processing of containers of samples.NOTE 18212;Self-contained dry-storage gamma irradiators contain a sealed radiation source, or an array of sealed radiation sources securely held in a dry container constructed of solid materials. The sealed radiation sources are shielded at all times, and human access to the chamber undergoing irradiation is not physically possible due to the irradiator8217;s design configuration (see ANSI/HPS N43.7).NOTE 28212;For reference8211;standard dosimetry, the absorbed dose and absorbed-dose rate can be expressed in water or other material which has similar radiation absorption properties to that of the samples or dosimeters being irradiated. In some cases, the reference-standard dosimetry may be performed using ionization chambers, and may be calibrated in terms of exposure (C kg8211;1), or absorbed dose to air, water or tissue (Gy). Measurements performed in terms of exposure apply to ionization in air, and care should be taken to apply that measurement to the sample being irradiated.1.1 This practice outlines dosimetric procedures to be followed with self-contained dry-storage gamma irradiators. For irradiators used for routine processing, procedures are given to ensure that product processed will receive absorbed doses within prescribed limits.1.2 This practice covers dosimetry in the use of dry-storage gamma irradiators, namely self-contained dry-storage 137Cs or 60Co irradiators (shielded freestanding irradiators). It does not cover underwater pool sources, panoramic gamma sources, nor does it cover self-contained bremsstrahlung X-ray units.1.3 The absorbed-dose range for the use of the dry-storage self-contained gamma irradiators covered by this practice is typically 1 to 105 Gy, depending on the application. The absorbed-dose rate range typically is from 108211;2 to 103 Gy/min.1.4 For irradiators supplied for specific applications, specific ISO/ASTM or ASTM practices and guides provide dosimetric procedures for the application. For procedures specific to dosimetry in blood irradiation, see ISO/ASTM Practice 51939. For procedures specific to dosimetry in radiation research on food and agricultural products, see ISO/ASTM Practice 51900. For procedures specific to radiation hardness testing, see ASTM Practice E1249. For procedures specific to the dosimetry in the irradiation of insects for sterile release programs, see I......

Standard Practice for Dosimetry for a Self-Contained Dry-Storage Gamma Irradiator

ASTM ISO/ASTM 52628-13 辐射加工过程中计量测定的标准实施规程

4.1 Radiation processing of articles in both commercial and research applications may be carried out for a number of purposes. These include, for example, sterilization of health care products, reduction of the microbial populations in foods and modification of polymers. The radiations used may be accelerated electrons, gamma-radiation from radionuclide sources such as cobalt-60, or X-radiation. 4.2 To demonstrate control of the radiation process, the absorbed dose must be measured using a dosimetry system, the calibration of which, is traceable to appropriate national or international standards. The radiation-induced change in the dosimeter is evaluated and related to absorbed dose through calibration. Dose measurements required for particular processes are described in other standards referenced in this practice. 1.1 This practice describes the basic requirements that apply when making absorbed dose measurements in accordance with the ASTM E61 series of dosimetry standards. In addition, it provides guidance on the selection of dosimetry systems and directs the user to other standards that provide specific information on individual dosimetry systems, calibration methods, uncertainty estimation and radiation processing applications. 1.2 This practice applies to dosimetry for radiation processing applications using electrons or photons (gamma- or X-radiation). 1.3 This practice addresses the minimum requirements of a measurement management system, but does not include general quality system requirements. 1.4 This practice does not address personnel dosimetry or medical dosimetry. 1.5 This practice does not apply to primary standard dosimetry systems. 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 Dosimetry in Radiation Processing

ASTM E1894-13 选择脉冲X射线源用的剂量测定系统的标准指南

4.1 Flash X-ray facilities provide intense bremsstrahlung radiation environments, usually in a single sub-microsecond pulse, which often fluctuates in amplitude, shape, and spectrum from shot to shot. Therefore, appropriate dosimetry must be fielded on every exposure to characterize the environment, see ICRU Report 34. These intense bremsstrahlung sources have a variety of applications which include the following: 4.1.1 Generation of X-ray and gamma-ray environments similar to that from a nuclear weapon burst. 4.1.2 Studies of the effects of X-rays and gamma rays on materials. 4.1.3 Studies of the effects of radiation on electronic devices such as transistors, diodes, and capacitors. 4.1.4 Vulnerability and survivability testing of military systems and components. 4.1.5 Computer code validation studies. 4.2 This guide is written to assist the experimenter in selecting the needed dosimetry systems (not all radiation parameters must be measured in a given experiment) for use at pulsed X-ray facilities. This guide also provides a brief summary of the information on how to use each of the dosimetry systems. Other guides (see Section 2) provide more detailed information on selected dosimetry systems in radiation environments and should be consulted after an initial decision is made on the appropriate dosimetry system to use. There are many key parameters which describe a flash X-ray source, such as dose, dose rate, spectrum, pulse width, etc., such that typically no single dosimetry system can measure all the parameters simultaneously. 1.1 This guide provides assistance in selecting and using dosimetry systems in flash X-ray experiments. Both dose and dose-rate techniques are described. 1.2 Operating characteristics of flash X-ray sources are given, with emphasis on the spectrum of the photon output. 1.3 Assistance is provided to relate the measured dose to the response of a device under test (DUT). The device is assumed to be a semiconductor electronic part or system.

Standard Guide for Selecting Dosimetry Systems for Application in Pulsed X-Ray Sources

ASTM ISO/ASTM 51702-13 辐射处理用伽马设施中剂量测定的标准实施规程

4.1 Various products and materials routinely are irradiated at predetermined doses in gamma irradiation facilities to reduce their microbial population or to modify their characteristics. Dosimetry requirements may vary depending upon the irradiation application and end use of the product. Some examples of irradiation applications where dosimetry may be used are:4.1.1 Sterilization of medical devices,4.1.2 Treatment of food for the purpose of parasite and pathogen control, insect disinfestation, and shelf life extension,4.1.3 Disinfection of consumer products,4.1.4 Cross-linking or degradation of polymers and elastomers,4.1.5 Polymerization of monomers and grafting of monomers onto polymers,4.1.6 Enhancement of color in gemstones and other materials,4.1.7 Modification of characteristics of semiconductor devices, and4.1.8 Research on materials effects.NOTE 38212;Dosimetry is required for regulated irradiation processes such as sterilization of medical devices and the treatment of food. It may be less important for other industrial processes, for example, polymer modification, which can be evaluated by changes in the physical and chemical properties of the irradiated materials.4.2 An irradiation process usually requires a minimum absorbed dose to achieve the intended effect. There also may be a maximum absorbed dose that the product can tolerate and still meet its functional or regulatory specifications. Dosimetry is essential to the irradiation process since it is used to determine both of these limits and to confirm that the product is routinely irradiated within these limits.4.3 The absorbed-dose distribution within the product depends on the overall product dimensions and mass, irradiation geometry, and source activity distribution.4.4 Before an irradiation facility can be used, it must be qualified to determine its effectiveness in reproducibly delivering known, controllable absorbed doses. This involves testing the process equipment, calibrating the equipment and dosimetry system, and characterizing the magnitude, distribution and reproducibility of the absorbed dose delivered by the irradiator for a range of product densities.4.5 To ensure consistent and reproducible dose delivery in a qualified process, routine process control requires documented product handling procedures before and after irradiation, consistent product loading configuration, control and monitoring of critical process parameters, routine product dosimetry and documentation of the required activities.1.1 This practice outlines the installation qualification program for an irradiator and the dosimetric procedures to be followed during operational qualification, performance qualification, and routine processing in facilities that process products with ionizing radiation from radionuclide gamma sources to ensure that product has been treated within a predetermined range of absorbed dose. Other procedures related to operational qualification, performance qualification, and routine processing that may influence absorbed dose in the product are also discussed.NOTE 18212;Dosimetry is only one component of a total quality assurance program for adherence to good manufacturing practices used in radiation processing applications.NOTE 28212;ISO/ASTM Practices 51818 and 51649 describe dosimetric procedures for low and high enery electron beam facilities for radiation processing and ISO/ASTM Practice 51608 describes procedures for X-ray (bremsstrahlung) facilities for radiation processing.1.2 For the radiation sterilization of health care products, see ISO 11137-1. In those areas covered by ISO 11137-1, that standard takes precedence.1.3 This document is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with AS......

Standard Practice for Dosimetry in a Gamma Facility for Radiation Processing

ASTM E1006-13 试验反应堆试验物理学计量测定结果的分析和说明的标准实施规程

3.1 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. 3.2 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 E693), 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. 3.3 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 Annex A1 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 E185, E853, and E1035, Guides E900, E2005, E2006 and Test Method E646. 1.5 This standard may involve hazardous mate......

Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments

ASTM ISO/ASTM 51631-13 电子束中剂量测量和常规剂量测定系统校准用量热剂量测定系统的使用标准实施规程

4.1 This practice is applicable to the use of calorimetric dosimetry systems 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 dosimetry systems in electron beams. Calorimetric dosimetry systems are most suitable for dose measurement at electron accelerators utilizing conveyor systems for transport of product during irradiation.NOTE 18212;For additional information on calorimetric dosimetry system operation and use, see ICRU Report 80. For additional information on 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).4.2 The calorimetric dosimetry systems described in this practice are not primary standard dosimetry systems. The calorimeters are classified as Type II dosimeters (ASTM E2628). They may be used as internal standards at an electron beam irradiation facility, including being used as transfer standard dosimetry systems for calibration of other dosimetry systems, or they may be used as routine dosimeters. The calorimetric dosimetry systems 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.NOTE 28212;The calorimetric bodies of the calorimeters described in this practice are made from low atomic number materials. The electron fluences within these calorimetric bodies are almost independent of energy when irradiated with electron beams of 1.5 MeV or higher, and the mass collision stopping powers are approximately the same for these materials.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 E666 and E668, and Ref (1).4.4.1 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.4.4.2 Polymeric materials other than polystyrene may also be used for calorimetric measurements. Polystyrene is used because it is known to be resistant to radiation (11) and because almost no exo- or endothermic reactions take place (12).1.1 This practice covers the preparation and use of semiadiabatic calorimetric dosimetry systems for measurement of absorbed dose and for calibration of routine dosimetry systems 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 document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements ofASTM Practice E2628 for a calorimetric dosimetry system. It is intended to be read in conjunction with ASTM Practice E2628.1.3 The calorimeters described in this practice are classified as Type II dosimeters on the basis of the complex effect of influence quantities. See ASTM Practice E2628.1.4 This practice applies to electron beams in the energy range from 1.5 to 12 MeV.1.5 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.1.6 The average absorbed-dose rate range shall generally be greater than 10 Gy183;s-1.1.7 The temperature range for use of these calorimetric dosimetry systems d......

Standard Practice for Use of Calorimetric Dosimetry Systems for Electron Beam Dose Measurements and Routine Dosimeter Calibration

ASTM ISO/ASTM 51607-13 丙胺酸-电子顺磁共振剂量测量系统使用的标准实施规程

The alanine-EPR dosimetry system provides a means for measuring absorbed dose. It is based on the measurement of specific stable free radicals in crystalline alanine generated by ionizing radiation. Alanine-EPR dosimetry systems are used in reference- or transfer-standard or routine dosimetry systems in radiation applications that include: sterilization of medical devices and pharmaceuticals, food irradiation, polymer modifications, medical therapy and radiation damage studies in materials (1, 13-15).1.1 This practice covers dosimeter materials, instrumentation, and procedures for using the alanine-EPR dosimetry system for measuring the absorbed dose in the photon and electron radiation processing of materials. The system is based on electron paramagnetic resonance (EPR) spectroscopy of free radicals derived from the amino acid alanine. 1.2 The alanine dosimeter is classified as a type I dosimeter as it is affected by individual influence quantities in a well-defined way that can be expressed in terms of independent correction factors (see ASTM Practice E2628). The alanine dosimeter may be used in either a reference standard dosimetry system or in a routine dosimetry system. 1.3 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ASTM E2628 “Practice for Dosimetry in Radiation Processing” for alanine dosimetry system. It should be read in conjunction with ASTM E2628. 1.4 This practice covers alanine-EPR dosimetry systems for dose measurements under the following conditions: 1.4.1 The absorbed dose range is between 1 and 1.5 × 105Gy. 1.4.2 The absorbed dose rate is up to 102Gy s-1 for continuous radiation fields and up to 3 × 1010Gy s-1 for pulsed radiation fields (1-4). 1.4.3 The radiation energy for photons and electrons is between 0.1 and 30 MeV (1, 2, 5-8). 1.4.4 The irradiation temperature is between –78 °C and + 70 °C (2, 9-12). 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 Use of the Alanine-EPR Dosimetry System

ASTM E2852-13 有害物质检测仪表收购, 维修, 存储和使用的标准指南

5.1 This guide provides information that could be used to: 5.1.1 Establish a hazardous material instrument program; 5.1.2 Help ensure that consistently reliable instruments are available for the detection of hazardous materials; and 5.1.3 Provide the safety professional with the means to evaluate the risk and facilitate the mitigation of the threat from hazardous materials. 5.2 This guide provides information to help perform the following: 5.2.1 Select detection equipment. 5.2.2 Maintain the equipment in a manner that supports its immediate use when required. 5.2.3 Store equipment using proper methods and conditions between uses. 5.2.4 Calibrate equipment in accordance with manufacturer’s recommendations and regulatory requirements: 5.2.4.1 At appropriate intervals; 5.2.4.2 Using appropriate standards; and 5.2.4.3 While maintaining proper documentation of calibration and repair. 5.2.5 Use and verify equipment performance: 5.2.5.1 As recommended by the manufacturer for its intended application; 5.2.5.2 By performing functional checks; and 5.2.5.3 By knowing any limitations of use. 5.3 This guide also provides information regarding the types of materials to be included in training programs for the use and maintenance of the equipment. 1.1 This guide provides techniques that can be used to ensure the proper operation and use of Hazardous Material detection equipment. This document cannot replace education or experience and should be used in conjunction with professional judgment. Not all aspects of this guide may be applicable in all circumstances. 1.2 This guide is not intended to represent or replace any accreditation or certification documents by which the adequacy of a given professional service must be judged. 1.3 This guide 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 guide to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. 1.4 When using HAZMAT equipment follow the manufacturer’s guidance and appropriate safety practices for the expected or suspected threat. 1.5 Th......

Standard Guide for Acquisition, Maintenance, Storage, and Use of Hazardous Material Detection Instrumentation

ASTM D7784-12 使用伽马能谱测量快速评估在环境介质中释放放射性核素的伽马射线的标准实施规程

5.1 This practice was developed for the rapid determination of gamma-emitting radionuclides in environmental media. The results of the test may be used to determine if the activity of these radionuclides in the sample exceeds the action level for the relevant incident or emergency response. The detection limits will be dependent on sample size, counting configuration, and the detector system in use. 5.2 In most cases, a sample container which is large in diameter and short in height relative to the detector will provide the best gamma-ray detection efficiency. For samples of water or other low-Z materials (e.g., vegetation), the re-entrant or Marinelli-style beaker may yield the best gamma-ray detection efficiency. 5.3 The density of the sample material and physical parameters of the sample container (e.g., diameter, height, material) may have significant consequences for the accuracy of the sample analysis as compared to the calibration. For this reason, the ideal calibration material and container (often referred to as ‘geometry’) will be exactly the same as the samples to be analyzed. Differences in sample container or sample matrix may introduce significant errors in detector response, especially at low gamma-ray energies. Every effort should be made to account for these differences if the exact calibration geometry is not available. 5.4 This method establishes an empirical gamma-ray spectrometer calibration using standards traceable to a national standardizing body in a specific geometry selected to ensure that the container, density, and composition of the standard matches that of the samples as closely as possible. However, in some cases it may be beneficial to modify such initial calibrations using mathematical modeling or extrapolations to an alternate geometry. Use of such a model may be acceptable, depending on the measurement quality objectives of the analysis process, and provided that appropriate compensation to uncertainty estimates are included. The use of such calibration models is best supported by the successful analysis of a method validation reference material (MVRM). 5.5 This practice addresses the analysis of numerous gamma-emitting radionuclides in environmental media. This practice should be applicable to non-environmental media (for example, urine, debris, or rubble) that have similar physical properties. The key determination of “similar physical properties” is the ability to demonstrate that the gamma spectrometry system response to the sample configuration is suitably similar to that for which the system is calibrated. 5.6 For the analysis of radionuclides with low gamma-ray emission energies (lt;100 keV), self-absorption of the gamma-rays in the sample matrix can have a significant adverse effect on detection and quantification. The user should verify that instrument calibrations appropriately account for any self-absorption that may result from the sample matrix. 5.7 Commonly available energy and efficiency calibration standards cover the energy range of approximately 60 keV to 1836 keV. Results obtained using gamma-ray peaks outside the efficiency calibrated energy range will have greater uncertainty not accounted for in the uncertainty calculations of this practice. Great care should be taken to review the efficiency calibration values and the shape of the efficiency curve outside this range. ......

Standard Practice for the Rapid Assessment of Gamma-ray Emitting Radionuclides in Environmental Media by Gamma Spectrometry