ASTM E263-13
(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 descriptions of recommended tabulated dosimetry cross sections.
5.5 54Mn has a half-life of 312.13 (3) days4 (2) and emits a gamma ray with an energy of 834.838 (5) keV (2).
5.6 Interfering activities generated by neutron activation arising from thermal or fast neutron interactions are 2.5789 (1)-h 56Mn, 44.495 (9) day 59Fe, and 1925.28 (1) day 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 or vanadium will contain t...
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 3 years (for longer irradiations, see Practice E261).
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 and health practices and determine the applicability of regulatory limitations prior to use.
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Designation: E263 − 13
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 E261Practice for Determining Neutron Fluence, Fluence
Rate, and Spectra by Radioactivation Techniques
1.1 This test method describes procedures for measuring
54 54 E844Guide for Sensor Set Design and Irradiation for
reaction rates by the activation reaction Fe(n,p) Mn.
Reactor Surveillance, E 706 (IIC)
1.2 Thisactivationreactionisusefulformeasuringneutrons
E944Guide for Application of Neutron Spectrum Adjust-
withenergiesaboveapproximately2.2MeVandforirradiation
ment Methods in Reactor Surveillance, E 706 (IIA)
times up to about 3 years (for longer irradiations, see Practice
E1005Test Method for Application and Analysis of Radio-
E261).
metric Monitors for Reactor Vessel Surveillance, E 706
1.3 With suitable techniques, fission-neutron fluence rates (IIIA)
8 −2 −1
E1018Guide for Application of ASTM Evaluated Cross
above 10 cm ·s can be determined. However, in the pres-
ence of a high thermal-neutron fluence rate (for example, >2 × Section Data File, Matrix E706 (IIB)
14 −2 −1 54
10 cm ·s ) Mn depletion should be investigated.
3. Terminology
1.4 Detailed procedures describing the use of other fast-
3.1 Definitions:
neutron detectors are referenced in Practice E261.
3.1.1 Refer to Terminology E170 for definitions of terms
1.5 The values stated in SI units are to be regarded as
relating to radiation measurements and neutron dosimetry.
standard. No other units of measurement are included in this
4. Summary of Test Method
standard.
4.1 High-purity iron is irradiated in a neutron field, thereby
1.6 This standard does not purport to address all of the
54 54 54
producing radioactive Mn from the Fe(n,p) Mn activation
safety concerns, if any, associated with its use. It is the
responsibility of the user of this standard to establish appro- reaction.
priate safety and health practices and determine the applica-
4.2 The gamma rays emitted by the radioactive decay of
54
bility of regulatory limitations prior to use.
Mn are counted in accordance with Test Methods E181. The
reaction rate, as defined by Practice E261, is calculated from
2. Referenced Documents
the decay rate and irradiation conditions.
2
54
2.1 ASTM Standards:
4.3 Radioassay of the Mn activity may be accomplished
D1193Specification for Reagent Water
by directly counting the irradiated iron dosimeter, or by first
54
E170Terminology Relating to Radiation Measurements and
chemically separating the Mn activity prior to counting.
Dosimetry
4.4 The neutron fluence rate above about 2.2 MeVcan then
E181Test Methods for Detector Calibration andAnalysis of
be calculated from the spectral-weighted neutron activation
Radionuclides
cross section as defined by Practice E261.
5. Significance and Use
1
ThistestmethodisunderthejurisdictionofASTMCommitteeE10onNuclear
5.1 Refer to Guide E844 for guidance on the selection,
Technology and Applications and is the direct responsibility of Subcommittee
irradiation, and quality control of neutron dosimeters.
E10.05 on Nuclear Radiation Metrology.
CurrenteditionapprovedJune1,2013.PublishedJuly2013.Originallyapproved
5.2 Refer to Practice E261 for a general discussion of the
in 1965 as E263–65T. Last previous edition approved in 2009 as E263–09. DOI:
determination of fast-neutron fluence rate with threshold de-
10.1520/E0263-13.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or tectors.
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
5.3 Pure iron in the form of foil or wire is readily available
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. and easily handled.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E263 − 13
5.4 Fig. 1 shows a plot of cross section as a function of iron dosimeters directly, those portions of Sections 6, 7 and 8
54 54
neutron energy for the fast-neutron reaction Fe(n,p) Mn that pertain to radiochemical separation should be disregarded.
3
(1). This figure is for illustrative purposes only to indicate the
NOTE1—Thefollowingportionsofthistestmethodapplyalsotodirect
54 54
range of response of the Fe(n,p) Mn reaction. Refer to
sample-counting methods: 6.1 – 6.3, 7.4, 7.9, 7.10, 8.1 –
...
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: E263 − 09 E263 − 13
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 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 Practice E261).
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 and health practices and determine the applicability of regulatory
limitations prior to use.
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, 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 for definitions of terms relating to radiation measurements and neutron dosimetry.
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.
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, 2009June 1, 2013. Published June 2009July 2013. Originally approved in 1965 as E263 – 65 T. Last previous edition approved in
20052009 as E263 – 05.E263 – 09. DOI: 10.1520/E0263-09.10.1520/E0263-13.
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.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E263 − 13
54
4.3 Radioassay of the Mn activity may be accomplished by directly counting the irradiated iron dosimeter, or by first
54
chemically separating the Mn activity prior to counting.
4.4 The neutron fluence rate above about 2.2 MeV can then be calculated from the spectral-weighted neutron activation cross
section as defined by Practice E261.
5. 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.
54 54 3
5.4 Fig. 1 shows a plot of cross section as a function of neutron energy for the fast-neutron reaction Fe(n,p
...
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