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ASTM D7362-14

(Guide)

Standard Guide for Rapid Screening of Vegetation for Radioactive Strontium Aerial Deposition (Withdrawn 2023)

Standard Guide for Rapid Screening of Vegetation for Radioactive Strontium Aerial Deposition (Withdrawn 2023)

SIGNIFICANCE AND USE
5.1 Strontium-90 is a major component of nuclear waste and is also a potential radioisotope for use as a weapon of mass destruction in a radiological dispersal device. It is a beta-emitting radioisotope with moderate half-life (~30 years). Strontium-89 is also a beta emitting radionuclide, but with a half-life of only ~50 days it is not usually present in significant quantities. If ingested the radiostrontium may deposit in the bone of an individual and thus can contribute a significant radiological dose to an affected person.  
5.2 Following an explosion in which radioactive material was present, the potential exists for the material to become airborne. It will quickly attach to atmospheric particles and be deposited on surfaces as the plume passes. This guide provides a rapid procedure by which vegetation can be screened to determine if radiostrontium is present and to provide a conservative estimate of its deposition on vegetation.  
5.3 This guide is intended to be used in a field portable lab, or if needed, can be performed completely in the field; therefore no hazardous chemicals are required to complete the analysis. However, an option for the use of acid in certain steps is documented in this guide.  
5.4 This guide is not intended to be used for screening food products or animal feed following an accident or incident.
SCOPE
1.1 This guide provides a rapid procedure by which vegetation samples may be screened for surface contamination of radioactive strontium (89Sr and 90Sr, collectively referred to as radiostrontium) following an airborne radioactive dispersal event. It provides a conservative estimate of radiostrontium deposition that can be used by decision makers for immediate actions prior to obtaining definitive results from a fixed laboratory asset.  
1.2 Insoluble forms of radiostrontium, such as the strontium (90Sr) titanate (SrTiO3) used in radio-isotope thermal-electric generators (RTGs), will not be measured by this method.  
1.3 Non-SI units are used in the calculations of this guide for ease of use during the emergency phase of an event. The instrumentation used typically provides count rates in counts per minute (cpm) rather than per second (s–1, the SI unit), thus activity is expressed in dpm (decays per minute) rather than Bq. Additionally, US EPA protective guidelines for surface contamination are expressed in dpm/100 cm2.  
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 prior to use.
WITHDRAWN RATIONALE
This guide provides a rapid procedure by which vegetation samples may be screened for surface contamination of radioactive strontium (89Sr and 90Sr, collectively referred to as radiostrontium) following an airborne radioactive dispersal event. It provides a conservative estimate of radiostrontium deposition that can be used by decision makers for immediate actions prior to obtaining definitive results from a fixed laboratory asset.
Formerly under the jurisdiction of Committee D19 on Water, this guide was withdrawn in January 2023 in accordance with section 10.6.3 of the Regulations Governing ASTM Technical Committees, which requires that standards shall be updated by the end of the eighth year since the last approval date.

General Information

Status
Withdrawn
Publication Date
31-Oct-2014
Withdrawal Date
11-Jan-2023
ICS
17.240 - Radiation measurements
Technical Committee
D19 - Water
Drafting Committee
D19.04 - Methods of Radiochemical Analysis
Current Stage
Ref Project

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ASTM D7362-14 - Standard Guide for Rapid Screening of Vegetation for Radioactive Strontium Aerial Deposition (Withdrawn 2023)ASTM D7362-14 - Standard Guide for Rapid Screening of Vegetation for Radioactive Strontium Aerial Deposition (Withdrawn 2023)
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ASTM D7362-14 - Standard Guide for Rapid Screening of Vegetation for Radioactive Strontium Aerial Deposition (Withdrawn 2023)
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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: D7362 − 14
Standard Guide for
Rapid Screening of Vegetation for Radioactive Strontium
1
Aerial Deposition
This standard is issued under the fixed designation D7362; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope 2.2 Other Documents:
3
EPA Protective Action Guidelines
1.1 This guide provides a rapid procedure by which vegeta-
tion samples may be screened for surface contamination of
3. Terminology
89 90
radioactive strontium ( Sr and Sr, collectively referred to as
3.1 Definitions—See Terminology D1129 for terms related
radiostrontium) following an airborne radioactive dispersal
to water.
event. It provides a conservative estimate of radiostrontium
deposition that can be used by decision makers for immediate 3.2 Definitions of Terms Specific to This Standard:
actions prior to obtaining definitive results from a fixed
3.2.1 ROI, n—region of interest; the span of channels, or
laboratory asset. region, in the spectrum in which the counts due to a specific
radioisotope appear on a functioning, calibrated liquid scintil-
1.2 Insoluble forms of radiostrontium, such as the strontium
lation spectrometry system.
90
( Sr) titanate (SrTiO ) used in radio-isotope thermal-electric
3
3.3 Acronyms:
generators (RTGs), will not be measured by this method.
3.3.1 RLS, n—rapid liquid sampler
1.3 Non-SI units are used in the calculations of this guide
3.3.2 SPE, n—solid phase extraction
for ease of use during the emergency phase of an event. The
instrumentation used typically provides count rates in counts
4. Summary of Guide
–1
per minute (cpm) rather than per second (s , the SI unit), thus
4.1 Vegetation is collected from an area equivalent to 100
activity is expressed in dpm (decays per minute) rather than
2
cm . The leafy material is shaken with pH = 2 water to
Bq. Additionally, US EPA protective guidelines for surface
2
solubilize radiostrontium deposited on the vegetation. The
contamination are expressed in dpm/100 cm .
radiostrontium is then extracted onto a solid phase extraction
1.4 This standard does not purport to address all of the
(SPE) disk for counting and quantification.
safety concerns, if any, associated with its use. It is the
90
4.2 Testing has shown that chemical recoveries for Sr
responsibility of the user of this standard to establish appro-
under these extraction conditions average 30–50 %, with
priate safety and health practices and determine the applica-
89
similar recoveries expected for Sr.
bility of regulatory limitations prior to use.
4.3 Acounting efficiency of 80–85 % can be achieved using
2. Referenced Documents liquid scintillation spectrometry.
2
4.4 Quantification may also be accomplished using a simple
2.1 ASTM Standards:
gas-filled count rate meter (a “pancake probe”); however the
D1129 Terminology Relating to Water
presence of other beta-emitting radionuclides can not be
D1193 Specification for Reagent Water
discerned when using such a non-discriminatory detector.
D3648 Practices for the Measurement of Radioactivity
5. Significance and Use
5.1 Strontium-90isamajorcomponentofnuclearwasteand
1
This guide is under the jurisdiction ofASTM Committee D19 on Water and is
is also a potential radioisotope for use as a weapon of mass
the direct responsibility of Subcommittee D19.04 on Methods of Radiochemical
Analysis.
destruction in a radiological dispersal device. It is a beta-
Current edition approved Nov. 1, 2014. Published November 2014. Originally
emitting radioisotope with moderate half-life (~30 years).
approved in 2007. Last previous edition approved in 2007 as D7362 –07. DOI:
10.1520/D7362-14.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
3
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Available from United States Environmental Protection Agency (EPA), Ariel
Standards volume information, refer to the standard’s Document Summary page on Rios Bldg., 1200 Pennsylvania Ave., NW, Washington, DC 20460, http://
the ASTM website. www.epa.gov.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
D7362 − 14
Strontium-89 is also a beta emitting radionuclide, but with a should allow the option of looking at the entire counting
half-life of only ~50 days it is not usually present in significant spectrum so that evaluation of other interferences may be
quantities. If ingested the radiostrontium may deposit in the completed. Automatic discrimination of alpha and beta par-
bone of an individual and thus can co
...

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ASTM D3648-23(Practice)
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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.
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ASTM D7282-21e1(Practice)
Standard Practice for Setup, Calibration, and Quality Control of Instruments Used for Radioactivity Measurements

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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.  
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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.  
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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.  
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ASTM D8027-17(Practice)
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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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ASTM D7283-17(Test Method)
Standard Test Method for Alpha and Beta Activity in Water By Liquid Scintillation Counting

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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.  
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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
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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.  
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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.  
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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.
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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.  
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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.  
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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
ASTM G183-15(2023)(Practice)
Standard Practice for Field Use of Pyranometers, Pyrheliometers and UV Radiometers

SCOPE
1.1 This practice describes deployment conditions, maintenance requirements, verification procedures and calibration frequencies for use of pyranometers, pyrheliometers and UV radiometers in outdoor testing environments. This practice also discusses the conditions that dictate the level of accuracy required for instruments of different types.  
1.2 While both pyranometers and UV radiometers may be employed indoors to measure light radiation sources, the measurement of ultraviolet and light radiation in accelerated weathering enclosures using manufactured light sources generally requires specialized radiometric instruments. Use of radiometric instrumentation to measure laboratory light sources is covered in ISO 9370.
Note 1: An ASTM standard that is similar to ISO 9370 is under development and deals with the instrumental determination of irradiance and radiant exposure in weathering tests.  
1.3 The characterization of radiometers is outside the scope of the activities required of users of radiometers, as contemplated by this standard.  
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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