ASTM E704-13
(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.
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 Methods 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 significant contribution is expected.
5.4.1 Fission product production in a light-water reactor by neutron activation product 239Pu has been calculated to be insignificant (238U(n,f), for an irradiation period of 12 years at a fast-neutron (E > 1 MeV) fluence rate of 1 × 1011 cm−2 · s−1 provided the 238U is shielded from thermal neutrons (see Fig. 2 of Guide E844).
5.4.2 Fission product production from photonuclear reactions, that is, (γ,f) reactions, while negligible near-power and research-reactor cores, can be large for deep-water penetrations (1).4
5.5 Good agreement between neutron fluence measured by 238U fission and the 54Fe(n,p)54Mn reaction has been demonstrated (2). The reaction 238U(n,f) F.P. is u...
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.
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 and health practices and determine the applicability of regulatory limitations prior to use.
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Designation: E704 − 13
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 E320TestMethodforCesium-137inNuclearFuelSolutions
3
by Radiochemical Analysis (Withdrawn 1993)
1.1 This test method covers procedures for measuring reac-
E393Test Method for Measuring Reaction Rates byAnaly-
tion rates by assaying a fission product (F.P.) from the fission
238 sis of Barium-140 From Fission Dosimeters
reaction U(n,f)F.P.
E705Test Method for Measuring Reaction Rates by Radio-
1.2 The reaction is useful for measuring neutrons with
activation of Neptunium-237
energies from approximately 1.5 to 7 MeV and for irradiation
E844Guide for Sensor Set Design and Irradiation for
times up to 30 to 40 years.
Reactor Surveillance, E 706 (IIC)
1.3 Equivalent fission neutron fluence rates as defined in E944Guide for Application of Neutron Spectrum Adjust-
ment Methods in Reactor Surveillance, E 706 (IIA)
Practice E261 can be determined.
E1005Test Method for Application and Analysis of Radio-
1.4 Detailed procedures for other fast-neutron detectors are
metric Monitors for Reactor Vessel Surveillance, E 706
referenced in Practice E261.
(IIIA)
1.5 The values stated in SI units are to be regarded as
E1018Guide for Application of ASTM Evaluated Cross
standard. No other units of measurement are included in this
Section Data File, Matrix E706 (IIB)
standard.
1.6 This standard does not purport to address all of the 3. Terminology
safety concerns, if any, associated with its use. It is the
3.1 Definitions:
responsibility of the user of this standard to establish appro-
3.1.1 Refer to Terminology E170.
priate safety and health practices and determine the applica-
bility of regulatory limitations prior to use.
4. Summary of Test Method
238 235
2. Referenced Documents
4.1 High-purity U (<40 ppm U) is irradiated in a
2
fast-neutron field, thereby producing radioactive fission prod-
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
E181Test Methods for Detector Calibration andAnalysis of
La, Zr, and Ce can be assayed depending on the length
Radionuclides
of irradiation, purpose of the experiment, etc.
E261Practice for Determining Neutron Fluence, Fluence
4.3 The gamma rays emitted through radioactive decay are
Rate, and Spectra by Radioactivation Techniques
counted, and the reaction rate, as defined in Practice E261,is
E262Test Method for Determining Thermal Neutron Reac-
calculated from the decay rate and the irradiation conditions.
tion Rates and Thermal Neutron Fluence Rates by Radio-
activation Techniques
4.4 Theneutronfluencerateforneutronswithenergiesfrom
approximately 1.5 to 7 MeV can then be calculated from the
spectral-weightedneutronactivationcrosssectionasdefinedin
1
ThistestmethodisunderthejurisdictionofASTMCommitteeE10onNuclear
Practice E261.
Technology and Applicationsand is the direct responsibility of Subcommittee
E10.05 on Nuclear Radiation Metrology. 237 238
4.5 A parallel procedure that uses Np instead of Uis
CurrenteditionapprovedJune1,2013.PublishedJuly2013.Originallyapproved
given in Test Method E705.
in 1984. Last previous edition approved in 2008 as E704–08. DOI: 10.1520/
E0704-13.
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 − 13
TABLE 2 Recommended Fission Yields for Certain Fission
5. Significance and Use
A
Products
5.1 Refer to Practice E261 for a general discussion of the
A,B
Fissile Neutron Reaction Type JEFF-3.1.1
determination of fast-neutron fluence rate with fission detec- Fission Yield %
Isotope Energy Product Yield
238 95
tors.
U(n,f) 0.5 MeV Zr RC 5.19 ± 1.714 %
99
Mo RC 6.18 ± 1.6 %
238
5.2 U is available as metal foil, wire, or oxide powder 103
Ru RC 6.03 ± 1.6 %
137
(see Guide E844). It is usually encapsulated in a suitable Cs RC 6.02 ± 2.52 %
137m
238
Ba RI 1.0169e-2 ± 36.5 %
container to prevent loss of, and contamination by, the U
140
Ba RC 5.68 ± 2.67 %
140
and it
...
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 − 08 E704 − 13
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 reaction
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.
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 unitesunits 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.
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, E 706 (IIC)
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706 (IIIA)
E1018 Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)
3. Terminology
3.1 Definitions:
3.1.1 Refer to Terminology E170.
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.
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 July 1, 2008June 1, 2013. Published September 2008July 2013. Originally approved in 1984. Last previous edition approved in 20022008 as
E704 – 96 (2002).E704 – 08. DOI: 10.1520/E0704-08.10.1520/E0704-13.
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 − 13
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 Practice E261.
237 238
4.5 A parallel procedure that uses Np instead of U is given in Test Method E705.
5. Significance and Use
5.1 Refer to Practice E261 for a general discussion of the determination of fast-neutron fluence rate with fission detectors.
238
5.2 U is available as metal foil, wire, or oxide powder (see Guide E844). It is usually encapsulated
...
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