ASTM E704-19
(Test Method)Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
SIGNIFICANCE AND USE
5.1 Refer to Practice E261 for a general discussion of the determination of fast-neutron fluence rate with fission detectors.
5.2 238U is available as metal foil, wire, or oxide powder (see Guide E844). It is usually encapsulated in a suitable container to prevent loss of, and contamination by, the 238U and its fission products.
5.3 One or more fission products can be assayed. Pertinent data for relevant fission products are given in Table 1 and Table 2. (A) The lightface numbers in parentheses are the magnitude of plus or minus uncertainties in the last digit(s) listed.(B) With 137mBa (2.552 min) in equilibrium.(C) The recommended half-life and gamma emission probabilities have been taken from the Reference (3) data that was recommended at the time that the recommended fission yields were set.(D) Probability of daughter 140La decay.(E) This is the activity ratio of 140La/140Ba after reached transient equilibrium (t ≥ 19 days). (A) The JEFF-3.1/3.1.1 radioactive decay data and fission yields sub-libraries, JEFF Report 20, OECD 2009, Nuclear Energy Agency (5).(B) All yield data given as a %; RC represents a cumulative yield; RI represents an independent yield.
5.3.1 137Cs-137mBa is chosen frequently for long irradiations. Radioactive products 134Cs and 136Cs may be present, which can interfere with the counting of the 0.662 MeV 137Cs-137mBa gamma rays (see Test Method E320).
5.3.2 140Ba-140La is chosen frequently for short irradiations (see Test Method E393).
5.3.3 95Zr can be counted directly, following chemical separation, or with its daughter 95Nb using a high-resolution gamma detector system.
5.3.4 144Ce is a high-yield fission product applicable to 2- to 3-year irradiations.
5.4 It is necessary to surround the 238U monitor with a thermal neutron absorber to minimize fission product production from a quantity of 235U in the 238U target and from 239Pu from (n,γ) reactions in the 238U material. Assay of the 239Pu concentration when a signif...
SCOPE
1.1 This test method covers procedures for measuring reaction rates by assaying a fission product (F.P.) from the fission reaction 238U(n,f)F.P.
1.2 The reaction is useful for measuring neutrons with energies from approximately 1.5 to 7 MeV and for irradiation times up to 30 to 40 years, provided that the analysis methods described in Practice E261 are followed.
1.3 Equivalent fission neutron fluence rates as defined in Practice E261 can be determined.
1.4 Detailed procedures for other fast-neutron detectors are referenced in Practice E261.
1.5 The values stated in SI units are to be regarded as 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.
1.7 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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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.
Designation: E704 − 19
Standard Test Method for
Measuring Reaction Rates by Radioactivation of Uranium-
1
238
This standard is issued under the fixed designation E704; 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.
1. Scope E181Test Methods for Detector Calibration andAnalysis of
Radionuclides
1.1 This test method covers procedures for measuring reac-
E261Practice for Determining Neutron Fluence, Fluence
tion rates by assaying a fission product (F.P.) from the fission
238
Rate, and Spectra by Radioactivation Techniques
reaction U(n,f)F.P.
E262Test Method for Determining Thermal Neutron Reac-
1.2 The reaction is useful for measuring neutrons with
tion Rates and Thermal Neutron Fluence Rates by Radio-
energies from approximately 1.5 to 7 MeV and for irradiation
activation Techniques
times up to 30 to 40 years, provided that the analysis methods
E320TestMethodforCesium-137inNuclearFuelSolutions
described in Practice E261 are followed.
3
by Radiochemical Analysis (Withdrawn 1993)
1.3 Equivalent fission neutron fluence rates as defined in
E393Test Method for Measuring Reaction Rates byAnaly-
Practice E261 can be determined.
sis of Barium-140 From Fission Dosimeters
E705Test Method for Measuring Reaction Rates by Radio-
1.4 Detailed procedures for other fast-neutron detectors are
activation of Neptunium-237
referenced in Practice E261.
E844Guide for Sensor Set Design and Irradiation for
1.5 The values stated in SI units are to be regarded as
Reactor Surveillance
standard. No other units of measurement are included in this
E944Guide for Application of Neutron Spectrum Adjust-
standard.
ment Methods in Reactor Surveillance
1.6 This standard does not purport to address all of the
E1005Test Method for Application and Analysis of Radio-
safety concerns, if any, associated with its use. It is the
metric Monitors for Reactor Vessel Surveillance
responsibility of the user of this standard to establish appro-
E1018Guide for Application of ASTM Evaluated Cross
priate safety, health, and environmental practices and deter-
Section Data File
mine the applicability of regulatory limitations prior to use.
1.7 This international standard was developed in accor-
3. Terminology
dance with internationally recognized principles on standard-
3.1 Definitions:
ization established in the Decision on Principles for the
Development of International Standards, Guides and Recom- 3.1.1 Refer to Terminology E170.
mendations issued by the World Trade Organization Technical
Barriers to Trade (TBT) Committee. 4. Summary of Test Method
238 235
4.1 High-purity U (<40 ppm U) is irradiated in a
2. Referenced Documents
fast-neutron field, thereby producing radioactive fission prod-
2
2.1 ASTM Standards:
238
ucts from the reaction U(n,f)F.P.
E170Terminology Relating to Radiation Measurements and
137 137m 140
Dosimetry 4.2 Various fission products such as Cs- Ba, Ba-
140 95 144
La, Zr, and Ce can be assayed depending on the length
of irradiation, purpose of the experiment, etc.
1
ThistestmethodisunderthejurisdictionofASTMCommitteeE10onNuclear
Technology and Applicationsand is the direct responsibility of Subcommittee
4.3 The gamma rays emitted through radioactive decay are
E10.05 on Nuclear Radiation Metrology.
counted, and the reaction rate, as defined in Practice E261,is
Current edition approved Oct. 1, 2019. Published October 2019. Originally
calculated from the decay rate and the irradiation conditions.
approved in 1984. Last previous edition approved in 2013 as E704–13. DOI:
10.1520/E0704-19.
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
3
Standards volume information, refer to the standard’s Document Summary page on The last approved version of this historical standard is referenced on
the ASTM website. www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E704 − 19
TABLE 2 Recommended Fission Yields for Certain Fission
4.4 Theneutronfluencerateforneutronswithenergiesfrom
A
Products
approximately 1.5 to 7 MeV can then be calculated from the
A,B
Fissile Neutron Reaction Type JEFF-3.1.1
spectral-weightedneutronactivationcrosssectionasdefinedin
Fission Yield %
Isotope Energy Product Yield
Practice E261.
238 95
U(n,f) 0.5 MeV Zr RC 5.19 ± 1.714 %
237 238 99
Mo RC 6.1
...
This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation: E704 − 13 E704 − 19
Standard Test Method for
Measuring Reaction Rates by Radioactivation of Uranium-
1
238
This standard is issued under the fixed designation E704; 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
1.1 This test method covers procedures for measuring reaction rates by assaying a fission product (F.P.) from the fission
238
reaction U(n,f)F.P.
1.2 The reaction is useful for measuring neutrons with energies from approximately 1.5 to 7 MeV and for irradiation times up
to 30 to 40 years.years, provided that the analysis methods described in Practice E261 are followed.
1.3 Equivalent fission neutron fluence rates as defined in Practice E261 can be determined.
1.4 Detailed procedures for other fast-neutron detectors are referenced in Practice E261.
1.5 The values stated in SI units are to be regarded as 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 safety, health, and healthenvironmental practices and determine the
applicability of regulatory limitations prior to use.
1.7 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.
2. Referenced Documents
2
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and Dosimetry
E181 Test Methods for Detector Calibration and Analysis of Radionuclides
E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
E262 Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation
Techniques
3
E320 Test Method for Cesium-137 in Nuclear Fuel Solutions by Radiochemical Analysis (Withdrawn 1993)
E393 Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters
E705 Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
E1018 Guide for Application of ASTM Evaluated Cross Section Data File
3. Terminology
3.1 Definitions:
3.1.1 Refer to Terminology E170.
1
This test method is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applicationsand is the direct responsibility of Subcommittee E10.05 on
Nuclear Radiation Metrology.
Current edition approved June 1, 2013Oct. 1, 2019. Published July 2013October 2019. Originally approved in 1984. Last previous edition approved in 20082013 as
E704 – 08.E704 – 13. DOI: 10.1520/E0704-13.10.1520/E0704-19.
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 the ASTM website.
3
The last approved version of this historical standard is referenced on www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E704 − 19
4. Summary of Test Method
238 235
4.1 High-purity U (<40 ppm U) is irradiated in a fast-neutron field, thereby producing radioactive fission products from
238
the reaction U(n,f)F.P.
137 137m 140 140 95 144
4.2 Various fission products such as Cs- Ba, Ba- La, Zr, and Ce can be assayed depending on the length of
irradiation, purpose of the experiment, etc.
4.3 The gamma rays emitted through radioactive decay are counted, and the reaction rate, as defined in Practice E261, is
calculated from the decay rate and the irradiation conditions.
4.4 The neutron fluence rate for neutrons with energies from approximately 1.5 to 7 MeV can then be calculated from the
spectral-weighted neutron activation cross section as defined in Prac
...
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