ASTM E263-18
(Test Method)Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron
Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron
SIGNIFICANCE AND USE
5.1 Refer to Guide E844 for guidance on 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 iron in the form of foil or wire is readily available and easily handled.
5.4 Fig. 1 shows a plot of cross section as a function of neutron energy for the fast-neutron reaction 54Fe(n,p)54Mn (1).3 This figure is for illustrative purposes only to indicate the range of response of the 54Fe(n,p)54Mn reaction. Refer to Guide E1018 for recommended tabulated dosimetry cross sections.
FIG. 1 54Fe(n,p)54Mn Cross Section
5.5 54Mn has a half-life of 312.19 (3) days4 (2) and emits a gamma ray with an energy of 834.855 (3) keV (2).
5.6 Interfering activities generated by neutron activation arising from thermal or fast neutron interactions are 2.57878 (46)-h 56Mn, 44.494 (12) days 59Fe, and 5.2711 (8) years 60Co (2,3). (Consult the latest version of Ref (2) for more precise values currently accepted for the half-lives.) Interference from 56Mn can be eliminated by waiting 48 h before counting. Although chemical separation of 54Mn from the irradiated iron is the most effective method for eliminating 59Fe and 60Co, direct counting of iron for 54Mn is possible using high-resolution detector systems or unfolding or stripping techniques, especially if the dosimeter was covered with cadmium or boron during irradiation. Altering the isotopic composition of the iron dosimeter is another useful technique for eliminating interference from extraneous activities when direct sample counting is to be employed.
5.7 The vapor pressures of manganese and iron are such that manganese diffusion losses from iron can become significant at temperatures above about 700°C. Therefore, precautions must be taken to avoid the diffusion loss of 54Mn from iron dosimeters at high temperature. Encapsulating the iron dosimeter in quartz o...
SCOPE
1.1 This test method describes procedures for measuring reaction rates by the activation reaction 54Fe(n,p)54Mn.
1.2 This activation reaction is useful for measuring neutrons with energies above approximately 2.2 MeV and for irradiation times up to about three years, provided that the analysis methods described in Practice E261 are followed. If dosimeters are analyzed after irradiation periods longer than three years, the information inferred about the fluence during irradiation periods more than three years before the end of the irradiation should not be relied upon without supporting data from dosimeters withdrawn earlier.
1.3 With suitable techniques, fission-neutron fluence rates above 108 cm−2·s−1 can be determined. However, in the presence of a high thermal-neutron fluence rate (for example, >2 × 1014 cm−2·s −1) 54Mn depletion should be investigated.
1.4 Detailed procedures describing the use of 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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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: E263 − 18
Standard Test Method for
Measuring Fast-Neutron Reaction Rates by Radioactivation
1
of Iron
This standard is issued under the fixed designation E263; 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.
This standard has been approved for use by agencies of the U.S. Department of Defense.
1. Scope 2. Referenced Documents
2
1.1 This test method describes procedures for measuring 2.1 ASTM Standards:
54 54
reaction rates by the activation reaction Fe(n,p) Mn. D1193Specification for Reagent Water
E170Terminology Relating to Radiation Measurements and
1.2 Thisactivationreactionisusefulformeasuringneutrons
Dosimetry
withenergiesaboveapproximately2.2MeVandforirradiation
E181Test Methods for Detector Calibration andAnalysis of
times up to about three years, provided that the analysis
Radionuclides
methodsdescribedinPracticeE261arefollowed.Ifdosimeters
E261Practice for Determining Neutron Fluence, Fluence
are analyzed after irradiation periods longer than three years,
Rate, and Spectra by Radioactivation Techniques
the information inferred about the fluence during irradiation
E844Guide for Sensor Set Design and Irradiation for
periods more than three years before the end of the irradiation
Reactor Surveillance
should not be relied upon without supporting data from
E944Guide for Application of Neutron Spectrum Adjust-
dosimeters withdrawn earlier.
ment Methods in Reactor Surveillance
1.3 With suitable techniques, fission-neutron fluence rates
E1005Test Method for Application and Analysis of Radio-
8 −2 −1
above 10 cm ·s can be determined. However, in the pres-
metric Monitors for Reactor Vessel Surveillance
ence of a high thermal-neutron fluence rate (for example, >2 ×
E1018Guide for Application of ASTM Evaluated Cross
14 −2 −1 54
10 cm ·s ) Mn depletion should be investigated.
Section Data File
1.4 Detailed procedures describing the use of other fast-
3. Terminology
neutron detectors are referenced in Practice E261.
3.1 Definitions:
1.5 The values stated in SI units are to be regarded as
3.1.1 Refer to Terminology E170 for definitions of terms
standard. No other units of measurement are included in this
relating to radiation measurements and neutron dosimetry.
standard.
1.6 This standard does not purport to address all of the
4. Summary of Test Method
safety concerns, if any, associated with its use. It is the
4.1 High-purity iron is irradiated in a neutron field, thereby
responsibility of the user of this standard to establish appro-
54 54 54
producing radioactive Mn from the Fe(n,p) Mn activation
priate safety, health, and environmental practices and deter-
reaction.
mine the applicability of regulatory limitations prior to use.
1.7 This international standard was developed in accor-
4.2 The gamma rays emitted by the radioactive decay of
54
dance with internationally recognized principles on standard-
Mn are counted in accordance with Test Methods E181. The
ization established in the Decision on Principles for the
reaction rate, as defined by Practice E261, is calculated from
Development of International Standards, Guides and Recom-
the decay rate and irradiation conditions.
mendations issued by the World Trade Organization Technical
54
4.3 Radioassay of the Mn activity may be accomplished
Barriers to Trade (TBT) Committee.
by directly counting the irradiated iron dosimeter, or by first
54
chemically separating the Mn activity prior to counting.
1
ThistestmethodisunderthejurisdictionofASTMCommitteeE10onNuclear
Technology and Applications and is the direct responsibility of Subcommittee
2
E10.05 on Nuclear Radiation Metrology. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved Dec. 1, 2018. Published January 2019. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 1965 as E263–65T. Last previous edition approved in 2013 as Standards volume information, refer to the standard’s Document Summary page on
E263–13. DOI: 10.1520/E0263-18. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E263 − 18
59 60
4.4 The neutron fluence rate above about 2.2 MeVcan then is the most effective method for eliminating Fe and Co,
54
be calculated from the spectral-weighted neutron activation direct counting of iron for Mn is possible usin
...
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: E263 − 13 E263 − 18
Standard Test Method for
Measuring Fast-Neutron Reaction Rates by Radioactivation
1
of Iron
This standard is issued under the fixed designation E263; 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.
This standard has been approved for use by agencies of the U.S. Department of Defense.
1. Scope
54 54
1.1 This test method describes procedures for measuring reaction rates by the activation reaction Fe(n,p) Mn.
1.2 This activation reaction is useful for measuring neutrons with energies above approximately 2.2 MeV and for irradiation
times up to about 3 years (for longer irradiations, see three years, provided that the analysis methods described in Practice E261).
are followed. If dosimeters are analyzed after irradiation periods longer than three years, the information inferred about the fluence
during irradiation periods more than three years before the end of the irradiation should not be relied upon without supporting data
from dosimeters withdrawn earlier.
8 −2 −1
1.3 With suitable techniques, fission-neutron fluence rates above 10 cm ·s can be determined. However, in the presence of
14 −2 −1 54
a high thermal-neutron fluence rate (for example, >2 × 10 cm ·s ) Mn depletion should be investigated.
1.4 Detailed procedures describing the use of 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:
D1193 Specification for Reagent Water
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
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 for definitions of terms relating to radiation measurements and neutron dosimetry.
1
This test method is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.05
on Nuclear Radiation Metrology.
Current edition approved June 1, 2013Dec. 1, 2018. Published July 2013January 2019. Originally approved in 1965 as E263 – 65 T. Last previous edition approved in
20092013 as E263 – 09.E263 – 13. DOI: 10.1520/E0263-13.10.1520/E0263-18.
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.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E263 − 18
4. Summary of Test Method
54 54 54
4.1 High-purity iron is irradiated in a neutron field, thereby producing radioactive Mn from the Fe(n,p) Mn activation
reaction.
4.2 The gamma rays emitted by the radioactive decay of
54
Mn are counted in accordance with Test Methods E181. The reaction rate, as defined by Practice E261, is calculated from the
decay rate and irradiation conditions.
54
4.3 Radioassay of the Mn activity may be accomplished by directly counting the irradiated iron dosimeter, or by first
54
chemically se
...
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