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ASTM D3648-04

(Practice)

Standard Practices for the Measurement of Radioactivity

Standard Practices for the Measurement of Radioactivity

SIGNIFICANCE AND USE
This practice was developed for the purpose of summarizing the various generic radiometric techniques, equipment, and practices that are used for the measurement of radioactivity. GENERAL INFORMATION   Top
SCOPE
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 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 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.

General Information

Status
Historical
Publication Date
30-Jun-2004
ICS
17.240 - Radiation measurements
Technical Committee
D19 - Water
Drafting Committee
D19.04 - Methods of Radiochemical Analysis
Current Stage
Ref Project

Relations

Replaces
ASTM D3648-03 - Standard Practices for the Measurement of Radioactivity
Effective Date
01-Jul-2004
Replaced By
ASTM D3648-04(2011) - Standard Practices for the Measurement of Radioactivity
Effective Date
01-Jan-2011
Referred By
ASTM D7283-17 - Standard Test Method for Alpha and Beta Activity in Water By Liquid Scintillation Counting
Effective Date
01-Jul-2004
Referred By
ASTM D1943-20 - Standard Test Method for Alpha Particle Radioactivity of Water 
Effective Date
01-Jul-2004
Referred By
ASTM D5811-20 - Standard Test Method for Strontium-90 in Water
Effective Date
01-Jul-2004
Referred By
ASTM C1473-19 - Standard Test Method for Radiochemical Determination of Uranium Isotopes in Urine by Alpha Spectrometry
Effective Date
01-Jul-2004
Referred By
ASTM D3084-20 - Standard Practice for Alpha-Particle Spectrometry of Water
Effective Date
01-Jul-2004
Referred By
ASTM F3160-21 - Standard Guide for Metallurgical Characterization of Absorbable Metallic Materials for Medical Implants
Effective Date
01-Jul-2004
Referred By
ASTM D3972-09(2015) - Standard Test Method for Isotopic Uranium in Water by Radiochemistry
Effective Date
01-Jul-2004
Referred By
ASTM D6239-09(2015) - Standard Test Method for Uranium in Drinking Water by High-Resolution Alpha-Liquid-Scintillation Spectrometry
Effective Date
01-Jul-2004
Referred By
ASTM C1561-10(2016) - Standard Guide for Determination of Plutonium and Neptunium in Uranium Hexafluoride and U-Rich Matrix by Alpha Spectrometry
Effective Date
01-Jul-2004
Referred By
ASTM D5847-22 - Standard Practice for Writing Quality Control Specifications for Standard Test Methods for Water Analysis
Effective Date
01-Jul-2004
Referred By
ASTM D4107-20 - Standard Test Method for Tritium in Drinking Water
Effective Date
01-Jul-2004
Referred By
ASTM D7727-21 - Standard Practice for Calculation of Dose Equivalent Xenon (DEX) for Radioactive Xenon Fission Products in Reactor Coolant
Effective Date
01-Jul-2004
Referred By
ASTM D3370-18 - Standard Practices for Sampling Water from Flowing Process Streams
Effective Date
01-Jul-2004

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ASTM D3648-04 - Standard Practices for the Measurement of Radioactivity
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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation:D3648–04
Standard Practices for the
1
Measurement of Radioactivity
This standard is issued under the fixed designation D3648; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
4
1. Scope 2.2 ANSI/ISO Standards:
ANSI N42.14 Calibration and Use of Germanium Spec-
1.1 Thesepracticescoverareviewoftheacceptedcounting
trometers for the Measurement of Gamma-Ray Emission
practices currently used in radiochemical analyses. The prac-
Rates of Radionuclides
tices are divided into four sections:
ISO Guide to the Expression of Uncertainty in Measure-
Section
ment, 1993
General Information 6 to 11
Alpha Counting 12 to 22
Beta Counting 23 to 33
3. Terminology
Gamma Counting 34 to 41
3.1 Definitions:
1.2 The general information sections contain information
3.1.1 For definitions of terms used in these practices, refer
applicabletoalltypesofradioactivemeasurements,whileeach
to Terminology D1129. For an explanation of the metric
of the other sections is specific for a particular type of
system, including units, symbols, and conversion factors, see
radiation.
Practice E380.
1.3 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the 4. Summary of Practices
responsibility of the user of this standard to establish appro-
4.1 The practices are a compilation of the various counting
priate safety and health practices and determine the applica-
techniques employed in the measurement of radioactivity. The
bility of regulatory limitations prior to use.
important variables that affect the accuracy or precision of
counting data are presented. Because a wide variety of instru-
2. Referenced Documents
ments and techniques are available for radiochemical labora-
2
2.1 ASTM Standards:
tories, the types of instruments and techniques to be selected
D1066 Practice for Sampling Steam
will be determined by the information desired. In a simple
D1129 Terminology Relating to Water
tracer application using a single radioactive isotope having
D1943 Test Method for Alpha Particle Radioactivity of
favorable properties of high purity, energy, and ample activity,
Water
a simple detector will probably be sufficient and techniques
3
D2459 Test Method for Gamma Spectrometry of Water
may offer no problems other than those related to reproduc-
D3084 Practice for Alpha-Particle Spectrometry of Water
ibility. The other extreme would be a laboratory requiring
D3085 Practice for Measurement of Low-LevelActivity in
quantitative identification of a variety of radionuclides, prepa-
3
Water
ration of standards, or studies of the characteristic radiation
D3370 Practices for SamplingWater from Closed Conduits
from radionuclides. For the latter, a variety of specialized
D3649 Practice for High-Resolution Gamma-Ray Spec-
instruments are required. Most radiochemical laboratories
trometry of Water
require a level of information between these two extremes.
E380 Practice for Use of the International System of Units
4.2 A basic requirement for accurate measurements is the
(SI) (the Modernized Metric System)
use of accurate standards for instrument calibration. With the
present availability of good standards, only the highly diverse
1 radiochemistry laboratories require instrumentation suitable
These practices are under the jurisdiction ofASTM Committee D19 on Water
for producing their own radioactive standards. However, it is
and are the direct responsibility of D19.04 on Methods of RadiochemicalAnalysis.
Current edition approved July 1, 2004. Published July 2004. Originally approved
advisable to compare each new standard received against the
in 1978. Last previous edition approved in 2003 as D3648–03. DOI: 10.1520/
previous standard.
D3648-04.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on
4
the ASTM website. Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
3
Withdrawn. 4th Floor, New York, NY 10036.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
D3648–04
4.3 Thus, the typical laboratory may be equipped with 7.1.3 Instrumentation should never be located in a chemical
proportional or Geiger-Mueller counters for beta counting, laboratory where corrosive vapors will cause rapid deteriora-
sodium iodide or germanium detectors, or both, in conjunction tion and failure.
with multic
...

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ASTM D3648-23(Practice)
Standard Practices for the Measurement of Radioactivity

SIGNIFICANCE AND USE
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.
SCOPE
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 – 11  
Alpha Counting  
12 – 22  
Beta Counting  
23 – 33  
Gamma Counting  
34 – 41  
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ASTM D7282-21e1(Practice)
Standard Practice for Setup, Calibration, and Quality Control of Instruments Used for Radioactivity Measurements

SIGNIFICANCE AND USE
5.1 This practice is consistent with a performance-based approach wherein the frequency of recalibration and instrument testing is linked to the results from continuing instrument quality control. Under the premise of this practice, a laboratory demonstrates that its instrument performance is acceptable for analyzing sample test sources.  
5.2 When a laboratory demonstrates acceptable performance based on continuing instrument quality control data (that is, control charts and tolerance charts), batch QC samples (that is, blanks, laboratory control samples, replicates, matrix spikes, and other batch QC samples as may be applicable) and independent reference materials, traditional schedule-driven instrument recalibration is permissible but unnecessary.  
5.3 When continuing instrument QC, batch QC, or independent reference material sample results indicate that instrument response has exceeded established control or tolerance limits, instrument calibration is required. Other actions related to sample analyses on the affected instruments may be required by the laboratory QM.  
5.4 The data obtained while following this practice will likely be stored electronically. The data remain in electronic storage, where they are readily available to produce plots, graphs, spreadsheets, and other types of displays and reports. The laboratory QM should specify the frequency and performance of data storage backup.
SCOPE
1.1 This practice covers consensus criteria for the setup, calibration, and quality control of nuclear instruments. Setup establishes the operating parameters of the instrument—for example, voltage or discriminator settings. Calibrations determine the instrument’s response characteristics—for example, its counting efficiency or gain. Quality control ensures that the performance of the instrument remains acceptable for its intended use and consistent with the performance at the time of calibration.  
1.2 This practice addresses four of the most commonly used types of nuclear counting instruments: alpha-particle spectrometer, gamma-ray spectrometer, gas proportional counter, and liquid scintillation counter.  
1.3 The values stated in SI units are to be regarded as standard. The values given in parentheses are mathematical conversions that are provided for information only and are not considered 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM D7784-20(Practice)
Standard Practice for the Rapid Assessment of Gamma-ray Emitting Radionuclides in Environmental Media by Gamma Spectrometry

SIGNIFICANCE AND USE
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 (for example, 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 (for example, 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 practice establishes an empirical gamma-ray spectrometer calibration using standards traceable to the SI via a national metrology institute (NMI) such as the National Institute of Standards and Technology (NIST) in the United States and the National Physical Laboratory (NPL) in the United Kingdom 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...
SCOPE
1.1 This practice covers the quantification of radionuclides in environmental media (for example, water, soil, vegetation, food) by means of simple preparation and counting with a high-resolution gamma ray detector. Because the practice is designed for rapid analysis, extensive efforts to ensure homogeneity or ideal sample counting conditions are not taken.  
1.2 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard.  
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
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ASTM D8027-17(Practice)
Standard Practice for Concentration of Select Radionuclides Using MnO2 for Measurement Purposes

SIGNIFICANCE AND USE
5.1 This practice is applicable to the separation of specific radionuclides of interest as part of overall radiochemical analytical methods. Radionuclides of interest may need to be quantified at activity levels of less than 1 Bq. This may require measurement of less than 1 fg of analyte in a sample which has a mass of a gram to more than several kilograms. This requires concentration of radionuclides into a smaller volume counting geometry or exclusion of species which would impede subsequent chemical separations, or both. MnO2 has shown good selectivity in being able to concentrate the following elements: actinium (Ac), bismuth (Bi), lead (Pb), polonium (Po), plutonium (Pu), radium (Ra), thorium (Th), and uranium (U) as noted in the referenced literature (see Sections 4 and 8). The MnO2 can be loaded onto a variety of substrates in preparation for use or generated in-situ in an aqueous solution. The presented processes are not meant to be all encompassing of what is possible or meant to address all limitations of using MnO2. Some limitations are noted in Section 6, Interferences.
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1.1 This practice is intended to provide a variety of approaches in which manganese oxide (MnO2) can be used to concentrate radionuclides of interest into a smaller volume counting geometry or exclude other species that would otherwise impede subsequent chemical separation steps in an overall radiochemical method, or both.  
1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
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1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM D7283-17(Test Method)
Standard Test Method for Alpha and Beta Activity in Water By Liquid Scintillation Counting

SIGNIFICANCE AND USE
5.1 This test method is intended for the measurement of gross alpha- and beta-activity concentrations in the analyses of environmental and drinking waters. For samples submitted to satisfy regulatory or permit requirements, the submitter should assure that this or any other method used is acceptable to the regulator or permit issuer.  
5.2 This test method is also applicable to the direct analysis of gross alpha- and beta-activity concentrations in water when low detection limits are not required. Direct analysis provides a rapid method for determination of gross alpha- and beta-activity concentrations when low detection limits are not required.  
5.3 This test method is not capable of discriminating among alpha emitting radionuclides or among beta emitting radionuclides. Those intending to identify and quantify specific radionuclides should use test methods specific to the radionuclides of interest.  
5.4 This test method may not be cited as a method for the determination of gross alpha- or beta-activity concentrations in a solid/soil matrix or the acid digestate of the same. The use of this test method for such applications brings the potential for serious bias and incomparability of results dependent on the matrix constituents, manner of sample preparation or treatment, or both.
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1.1 This test method covers the measurement of gross alpha- and beta- activity concentrations in a homogeneous water sample. It is applicable to alpha emitters with activity concentration levels above 0.11 Bq/L (3 pCi/L) and beta emitters with activity concentration levels above 0.15 Bq/L (4 pCi/L). This test method is not applicable to samples containing radionuclides that are volatile under conditions of the analysis.  
1.2 This test method may also be used for the direct measurement of gross alpha- and beta- activity concentrations in homogeneous water samples with alpha emitter activity concentration levels above 1.8 Bq/L (50 pCi/L) and beta emitter activity concentration levels above 3.7 Bq/L (100 pCi/L).  
1.3 This test method was tested using single-operator tests.2,3 A collaborative study following the U.S. EPA “Protocol for the Evaluation of Alternate Test Procedures for Analyzing Radioactive Contaminants in Drinking Water” was performed. The results of this study are on file at ASTM Headquarters.4  
1.4 The values stated in SI units are to be regarded as standard. The values given in parentheses are mathematical conversions to pCi/L that are provided for information only and are not considered standard. An exception is noted in Section 14.  
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ASTM D7939-15(Test Method)
Standard Test Method for Rapid Radiochemical Determination of Americium-241 in Water

SIGNIFICANCE AND USE
5.1 This test method is considered a rapid method when compared to other classical methods for the determination of 241Am in aqueous solutions. During the method validation of this method, a test batch of fourteen test samples plus quality control samples was chemically processed in ~7.5 hours. Additional time for counting the samples depends on the measurement quality objectives.  
5.2 This test method is specific for Americium-241 (241Am) in drinking water and other aqueous samples. However, if any isotopes of curium are present in the sample, they will be carried with americium during the analytical separation process and will be observed in the final alpha spectrum.  
5.3 This test method is capable of achieving a required method uncertainty for 241Am of 0.070 Bq/L at an analytical action level of 0.555 Bq/L. This test method is capable of achieving a required relative method uncertainty, φMR, 13 % above 0.555 Bq/L. This test method is capable of achieving a “required” minimum detectable concentration (MDC) of 0.055 Bq/L.  
5.4 To attain these stated measurement quality objectives (MQOs), a sample volume of approximately 200 mL and count time of at least 1 to 3 hours are recommended. The sample turnaround time and throughput may vary based on additional project MQOs, the time for analysis of the final counting form, and initial sample volume. This test method should be validated before use following the protocols provided in Method Validation Guide for Qualifying Methods Used by Radiological Laboratories Participating in Incident Response Activities.4  
5.5 This test method is intended to be used for water samples that are similar in composition to drinking water. This method was evaluated following the guidance presented for “Level E Method Validation: Adapted or Newly Developed Methods, Including Rapid Methods” in Method Validation Guide for Qualifying Methods Used by Radiological Laboratories Participating in Incident Response Activities and Chapter 6 of ...
SCOPE
1.1 This test method is specifically for Americium-241 (241Am) in drinking water and other aqueous samples. However, if any isotopes of curium are present in the sample, they will be carried with americium during the analytical separation process and will be observed in the final alpha spectrum. The presence of 243Am in the water sample will bias the results obtained by this test method.  
1.2 This test method is applicable to samples in which radioactive contamination is from either known or unknown origins. If any filtration of the sample is performed before starting the analysis, those solids should be analyzed separately. The results from the analysis of these solids should be reported separately (as a suspended activity concentration for the water volume filtered) but identified with the filtrate results.  
1.3 This test method is applicable to the determination of soluble 241Am. This test method is not applicable to the determination of 241Am in highly insoluble particulate matter possibly present in water samples contaminated as a result of a radiological dispersal device (RDD) event.  
1.4 This test method uses rapid radiochemical separation techniques for determining americium in water samples following a radiological or nuclear incident. Although, with this test method, concentrations of 241Am on the same order of magnitude as methods used for the Safe Drinking Water Act (SDWA) can be detected, this test method is not a substitute for SDWA-approved methods for 241Am.  
1.5 Units—The values stated in SI units are to be regarded as the standard. No other units of measurement are included in this standard.  
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.

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ASTM D5928-23(Practice)
Standard Practice for Screening of Waste for Radioactivity

SIGNIFICANCE AND USE
5.1 Most facilities disposing or using waste materials are prohibited from handling wastes that contain radioactive materials. This practice provides the user a rapid method for screening waste material for the presence or absence of radioactivity at user-established levels that consider background radiation and the intended use of the screening method. It is important to these facilities to be able to verify generator-supplied information in regard to radiation and to meet worker health and safety needs.
SCOPE
1.1 This practice covers the screening for α–, β–, and γ radiation above ambient background levels or user-defined criteria, or both, in liquid, sludge, or solid waste materials.  
1.2 This practice is intended to be a gross screening method for determining the presence or absence of radioactive materials in liquid, sludge, or solid waste materials. It is not intended to replace more sophisticated quantitative analytical techniques, but to provide a method for rapidly screening samples for radioactivity above ambient background levels or user-defined criteria, or both, for facilities prohibited from handling radioactive waste.  
1.3 This practice may or may not be suitable for applications such as site assessments and remediation activities, depending on the data quality objectives or intended use.  
1.4 The values stated in SI units are to be regarded as the standard.  
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM E481-23(Practice)
Standard Practice for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver

SIGNIFICANCE AND USE
3.1 This practice uses one monitor (cobalt) with a nearly 1/v absorption cross-section curve and a second monitor (silver) with a large resonance peak so that its resonance integral is large compared to its thermal cross section. The pertinent data for these two reactions are given in Table 1. The equations are based on the Westcott formalism ((2, 3) and Practice E261) and determine a Westcott 2200 m/s neutron fluence rate nv0 and the Westcott epithermal index parameter  . References (4-6) contain a general discussion of the two-reaction test method. In this practice, the absolute activities of both cobalt and silver monitors are determined. This differs from the test method in the references wherein only one absolute activity is determined.  (A) The numbers in parentheses following given values are the uncertainty in the last digit(s) of the value; 0.729 (8) means 0.729 ± 0.008, 70.8(1) means 70.8 ± 0.1.(B) The decay constant, λ, is defined as ln(2) / t1/2 with units of sec–1, where t1/2 is the nuclide half-life in seconds.(C) Calculated using Eq 10.(D) In Fig. 1, Θ = 4ErkT/AΓ2 = 0.2 corresponds to the value for 109Ag for T = 293 K, ∑r = N0σr,max,T=0Kσr,max,T=0K = 31138.03 barn at 5.19 eV (13). The value of σr,max,T=0K = 31138.03 barns is calculated using the Breit-Wigner single-level resonance formula  where the 109Ag atomic mass is A = 108.9047558 amu (14), the ENDF/B-VIII.0 (MAT = 4731) (13) resonance parameters are: resonance total width Γ = 0.1427333 eV, formation neutron width Γn = 0.0127333 eV, and radiative/decay width Γγ = 0.13 eV, with a resonance spin J=1, and the statistical spin factor  where s1 = 1/2 and s2 = 1/2 are the spins of the two particles (neutron and 109Ag ground state (15)) forming resonance.  
3.2 The advantages of this approach are the elimination of four difficulties associated with the use of cadmium: (1) the perturbation of the field by the cadmium; (2) the inexact cadmium cut-off energy; (3) the low melting temperature of cadmium; a...
SCOPE
1.1 This practice covers a suitable means of obtaining the thermal neutron fluence rate, or fluence, in nuclear reactor environments where the use of cadmium, as a thermal neutron shield as described in Test Method E262, is undesirable for reasons such as potential spectrum perturbations or due to temperatures above the melting point of cadmium.  
1.2 The reaction 59Co(n,γ )60Co results in a well-defined gamma emitter having a half-life of 5.2711 years2 (8)3 (1).4 The reaction 109Ag(n,γ)110mAg results in a nuclide with a well-known, complex decay scheme with a half-life of 249.78 (2) days (1). Both cobalt and silver are available either in very pure form or alloyed with other metals such as aluminum. A reference source of cobalt in aluminum alloy to serve as a neutron fluence rate monitor wire standard is available from the National Institute of Standards and Technology (NIST) as Standard Reference Material (SRM) 953.5 The competing activities from neutron activation of other isotopes are eliminated, for the most part, by waiting for the short-lived products to die out before counting. With suitable techniques, thermal neutron fluence rate in the range from 108 cm−2·s−1 to 3 × 1015 cm−2·s−1 can be measured. Two calculational practices are described in Section 9 for the determination of neutron fluence rates. The practice described in 9.3 may be used in all cases. This practice describes a means of measuring a Westcott neutron fluence rate in 9.2 (Note 1) by activation of cobalt- and silver-foil monitors (see Terminology E170). For the Wescott Neutron Fluence Convention method to be applicable, the measurement location must be well moderated and be well represented by a Maxwellian low-energy distribution and an (1/E) epithermal distribution. These conditions are usually only met in positions surrounded by hydrogenous moderator without nearby strongly multiplying or absorbing materials.
Note 1: Westcott fluence rate    ...

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ASTM D3648-23(Practice)
Standard Practices for the Measurement of Radioactivity

SIGNIFICANCE AND USE
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.
SCOPE
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 – 11  
Alpha Counting  
12 – 22  
Beta Counting  
23 – 33  
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM
ASTM E266-23(Test Method)
Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum

SIGNIFICANCE AND USE
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 determination of fast-neutron fluence rate with threshold detectors.  
5.3 Pure aluminum in the form of foil or wire is readily available and easily handled. 27Al has an abundance of 100 % (1).3  
5.4 24Na has a half-life of 14.958 (2)4 h (2) and emits gamma rays with energies of 1.368630 (5) and 2.754049 (13) MeV (2).  
5.5 Fig. 1 shows a plot of the International Reactor Dosimetry and Fusion File (IRDFF-II) cross section (3, 4) versus neutron energy for the fast-neutron reaction  27Al(n,α) 24Na (3) along with a comparison to the current experimental database (5, 6). While the RRDF-2008 and IRDFF-1.05 cross sections extend from threshold up to 60 MeV, due to considerations of the available validation data, the energy region over which this standard recommends use of this cross section for reactor dosimetry applications only extends from threshold at ~4.25 MeV up to 20 MeV. This figure is for illustrative purposes and is used to indicate the range of response of the  27Al(n,α) reaction. Refer to Guide E1018 for recommended sources for the tabulated dosimetry cross sections.
FIG. 1 27Al(n,α)24Na Cross Section, from IRDFF-II Library, with EXFOR Experimental Data  
5.6 Two competing activities, 28Al (2.25 (2) minute half-life) and 27Mg (9.458 (12) minute half-life), are formed in the reactions 27Al(n,γ)28Al and 27Al(n,p)27Mg, respectively, but these can be eliminated by waiting 2 h before counting.
SCOPE
1.1 This test method covers procedures measuring reaction rates by the activation reaction  27Al(n,α)24Na.  
1.2 This activation reaction is useful for measuring neutrons with energies above approximately 6.5 MeV and for irradiation times up to about two days (for longer irradiations, or when there are significant variations in reactor power during the irradiation, see Practice E261).  
1.3 With suitable techniques, fission-neutron fluence rates above 106 cm−2·s−1 can be determined.  
1.4 Detailed procedures for other fast neutron detectors are referenced in Practice E261.  
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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