Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237

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 237Np is available as metal foil, wire, or oxide powder. For further information, see Guide E844. It is usually encapsulated in a suitable container to prevent loss of, and contamination by, the  237Np and its fission products.4  
5.3 One or more fission products can be assayed. Pertinent data for relevant fission products are given in Table 15 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) Probability of daughter 140La decay.(D) With 140La (1.67850 d) in transient equilibrium.(E) Primary reference for half-life, gamma energy, and gamma emission probability is Ref (1) when data is available. Note this reference is to the BIPM data that was recommended at the time of the recommended fission yields were set, that is, as of 2009, and not to the latest Vol 8 data that was published in 2016.  (A) The JEFF-3.1/3.1.1 radioactive decay data and fission yields sub-libraries, JEFF Report 20, OECD 2009, Nuclear Energy Agency (2).(B) All yield data given as a %; RC represents a cumulative yield; RI represents an independent yield.(C) The neutron energy represents a generic “fast neutron” spectrum and has been characterized in the JEFF 3.1.1 fission yield library as having an average neutron energy of 0.4 MeV.  
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 0.661657 MeV 137Cs-137mBa gamma ray (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 t...
SCOPE
1.1 This test method covers procedures for measuring reaction rates by assaying a fission product (F.P.) from the fission reaction 237Np(n,f)F.P.  
1.2 The reaction is useful for measuring neutrons with energies from approximately 0.7 to 6 MeV and for irradiation times up to 90 years, provided that the analysis methods described in Practice E261 are followed. If dosimeters are analyzed after irradiation periods longer than 90 years, the information inferred about the fluence during irradiation periods more than 90 years before the end of the irradiation should not be relied upon without supporting data from dosimeters withdrawn earlier.  
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.

General Information

Status
Published
Publication Date
30-Nov-2018
Current Stage
Ref Project

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Standards Content (Sample)

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: E705 − 18
Standard Test Method for
Measuring Reaction Rates by Radioactivation of Neptunium-
1
237
This standard is issued under the fixed designation E705; 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 2. Referenced Documents
2
2.1 ASTM Standards:
1.1 This test method covers procedures for measuring reac-
E170Terminology Relating to Radiation Measurements and
tion rates by assaying a fission product (F.P.) from the fission
237
Dosimetry
reaction Np(n,f)F.P.
E181Test Methods for Detector Calibration andAnalysis of
1.2 The reaction is useful for measuring neutrons with
Radionuclides
energies from approximately 0.7 to 6 MeV and for irradiation
E261Practice for Determining Neutron Fluence, Fluence
times up to 90 years, provided that the analysis methods
Rate, and Spectra by Radioactivation Techniques
described in Practice E261 are followed. If dosimeters are
E262Test Method for Determining Thermal Neutron Reac-
analyzed after irradiation periods longer than 90 years, the tion Rates and Thermal Neutron Fluence Rates by Radio-
information inferred about the fluence during irradiation peri- activation Techniques
E320TestMethodforCesium-137inNuclearFuelSolutions
odsmorethan90yearsbeforetheendoftheirradiationshould
3
by Radiochemical Analysis (Withdrawn 1993)
not be relied upon without supporting data from dosimeters
E393Test Method for Measuring Reaction Rates byAnaly-
withdrawn earlier.
sis of Barium-140 From Fission Dosimeters
1.3 Equivalent fission neutron fluence rates as defined in
E704Test Method for Measuring Reaction Rates by Radio-
Practice E261 can be determined.
activation of Uranium-238
E844Guide for Sensor Set Design and Irradiation for
1.4 Detailed procedures for other fast-neutron detectors are
Reactor Surveillance
referenced in Practice E261.
E944Guide for Application of Neutron Spectrum Adjust-
1.5 The values stated in SI units are to be regarded as ment Methods in Reactor Surveillance
standard. No other units of measurement are included in this E1005Test Method for Application and Analysis of Radio-
metric Monitors for Reactor Vessel Surveillance
standard.
E1018Guide for Application of ASTM Evaluated Cross
1.6 This standard does not purport to address all of the
Section Data File
safety concerns, if any, associated with its use. It is the
responsibility of the user of this standard to establish appro-
3. Terminology
priate safety, health, and environmental practices and deter-
3.1 Definitions:
mine the applicability of regulatory limitations prior to use.
3.1.1 Refer to Terminology E170.
1.7 This international standard was developed in accor-
dance with internationally recognized principles on standard-
4. Summary of Test Method
ization established in the Decision on Principles for the
237
Development of International Standards, Guides and Recom-
4.1 High-purity Np (<40 ppm fissionable impurity) is
mendations issued by the World Trade Organization Technical
irradiatedinafast-neutronfield,therebyproducingradioactive
237
Barriers to Trade (TBT) Committee. fission products from the reaction Np(n,f)F.P.
1 2
ThistestmethodisunderthejurisdictionofASTMCommitteeE10onNuclear For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Technology and Applicationsand is the direct responsibility of Subcommittee contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
E10.05 on Nuclear Radiation Metrology. Standards volume information, refer to the standard’s Document Summary page on
Current edition approved Dec. 1, 2018. Published December 2018. Originally the ASTM website.
3
approved in 1979. Last previous edition approved 2013 as E705–13a. DOI: The last approved version of this historical standard is referenced on
10.1520/E0705-18. www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E705 − 18
137 137m 140
TABLE 2 Recommended Fission Yields for Certain Fission
4.2 Various fission products such as Cs- Ba, Ba-
A
140 95 144 Products
La, Zr,and Cecanbeassayeddependingonthelength
B,A
Fissile Neutron Reaction Type JEFF 3.1.1
of irradiation, purpose of the experiment, etc.
C
Fission Yield (%)
Isotope Energy Product Yield
237 95
4.3 The gamma rays emitted through radioactive decay are
Np(n,f) 0.4 MeV Zr RC 5.6147 ± 2.7 %
99
Mo RC 7.6218 ± 16.304 %
counted and the reaction rate,
...

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: E705 − 13a E705 − 18
Standard Test Method for
Measuring Reaction Rates by Radioactivation of Neptunium-
1
237
This standard is issued under the fixed designation E705; 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
237
Np(n,f)F.P.
1.2 The reaction is useful for measuring neutrons with energies from approximately 0.7 to 6 MeV and for irradiation times up
to 30 to 40 years.90 years, provided that the analysis methods described in Practice E261 are followed. If dosimeters are analyzed
after irradiation periods longer than 90 years, the information inferred about the fluence during irradiation periods more than 90
years before the end of the irradiation should not be relied upon without supporting data from dosimeters withdrawn earlier.
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
E704 Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
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 Aug. 1, 2013Dec. 1, 2018. Published August 2013December 2018. Originally approved in 1979. Last previous edition approved 2013 as
E705 – 13.E705 – 13a. DOI: 10.1520/E0705-13A.10.1520/E0705-18.
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 ----------------------
E705 − 18
4. Summary of Test Method
237
4.1 High-purity Np (<40 ppm fissionable impurity) is irradiated in a fast-neutron field, thereby producing radioactive fission
237
products from the reaction Np(n,f)F.P.
137 137m 1140140 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
...

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