ASTM E263-09
(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
SCOPE
DESIG: E 263 09 ^TITLE: Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron ^SIGNUSE:
Refer to Guide E 844 for guidance on the selection, irradiation, and quality control of neutron dosimeters.
Refer to Practice E 261 for a general discussion of the determination of fast-neutron fluence rate with threshold detectors.
Pure iron in the form of foil or wire is readily available and easily handled.
Fig. 1 shows a plot of cross section as a function of neutron energy for the fast-neutron reaction 54Fe(n,p)54Mn (1). This figure is for illustrative purposes only to indicate the range of response of the 54Fe(n,p)54Mn reaction. Refer to Guide E 1018 for descriptions of recommended tabulated dosimetry cross sections.
54Mn has a half-life of 312.13 days (3) (2) and emits a gamma ray with an energy of 834.845 keV (5). (2)
Interfering activities generated by neutron activation arising from thermal or fast neutron interactions are 2.57878 (46)-h 56Mn, 44.95-d (8) 59Fe, and 5.2710-y (8) 60Co (2,3). (Consult 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.
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 the manganese at temperatures up to about 900°C.
Sections 6, 7 and 8 that follow were specifically written to describe the method of chemical separation and subsequent counting of the 54Mn activity. When one elects to count the iron dosimeters directly, those portions of Sections 6, 7 and 8 that pertain to radiochemical separation should be disregarded.
Note 1—The following portions of this test method apply also to direct sample-counting methods: 6.1-6.3, 7.4, 7.9, 7.10, 8.1-8.5, 8.18, 8.19, and 10-13.
FIG. 1 54Fe(n,p)54Mn Cross Section ^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 E 261).
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 E 261.
1.5 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. ^REFERENCE:
ASTM Standards:
D 1193 Specification for Reagent Water
E 170 Terminology Relating to Radiation Measurements and Dosimetry
E 181 Test Methods for Detector Calibration and Analysis of Radionuclides
E 261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
E 844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance,...
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Designation: E263 − 09
StandardTest 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 Department of Defense.
1. Scope E944Guide for Application of Neutron Spectrum Adjust-
ment Methods in Reactor Surveillance, E 706 (IIA)
1.1 This test method describes procedures for measuring
54 54 E1005Test Method for Application and Analysis of Radio-
reaction rates by the activation reaction Fe(n,p) Mn.
metric Monitors for Reactor Vessel Surveillance, E 706
1.2 Thisactivationreactionisusefulformeasuringneutrons
(IIIA)
withenergiesaboveapproximately2.2MeVandforirradiation
E1018Guide for Application of ASTM Evaluated Cross
times up to about 3 years (for longer irradiations, see Practice
Section Data File, Matrix E706 (IIB)
E261).
1.3 With suitable techniques, fission-neutron fluence rates 3. Terminology
8 −2 −1
above 10 cm ·s can be determined. However, in the pres-
3.1 Definitions:
ence of a high thermal-neutron fluence rate (for example, >2 ×
3.1.1 Refer to Terminology E170 for definitions of terms
14 −2 −1 54
10 cm ·s ) Mn depletion should be investigated.
relating to radiation measurements and neutron dosimetry.
1.4 Detailed procedures describing the use of other fast-
neutron detectors are referenced in Practice E261. 4. Summary of Test Method
1.5 This standard does not purport to address all of the
4.1 High-purity iron is irradiated in a neutron field, thereby
54 54 54
safety concerns, if any, associated with its use. It is the
producing radioactive Mn from the Fe(n,p) Mn activation
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
bility of regulatory limitations prior to use.
54
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
2.1 ASTM Standards:
54
4.3 Radioassay of the Mn activity may be accomplished
D1193Specification for Reagent Water
by directly counting the irradiated iron dosimeter, or by first
E170Terminology Relating to Radiation Measurements and
54
chemically separating the Mn activity prior to counting.
Dosimetry
E181Test Methods for Detector Calibration andAnalysis of
4.4 The neutron fluence rate above about 2.2 MeVcan then
Radionuclides
be calculated from the spectral-weighted neutron activation
E261Practice for Determining Neutron Fluence, Fluence
cross section as defined by Practice E261.
Rate, and Spectra by Radioactivation Techniques
E844Guide for Sensor Set Design and Irradiation for
5. Significance and Use
Reactor Surveillance, E 706 (IIC)
5.1 Refer to Guide E844 for guidance on the selection,
irradiation, and quality control of neutron dosimeters.
1
ThistestmethodisunderthejurisdictionofASTMCommitteeE10onNuclear
5.2 Refer to Practice E261 for a general discussion of the
Technology and Applicationsand is the direct responsibility of Subcommittee
determination of fast-neutron fluence rate with threshold de-
E10.05 on Nuclear Radiation Metrology.
tectors.
Current edition approved June 1, 2009. Published June 2009. Originally
approved in 1965 as E263–65T. Last previous edition approved in 2005 as
5.3 Pure iron in the form of foil or wire is readily available
E263–05. DOI: 10.1520/E0263-09.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or and easily handled.
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
5.4 Fig. 1 shows a plot of cross section as a function of
Standards volume information, refer to the standard’s Document Summary page on
54 54
the ASTM website. neutron energy for the fast-neutron reaction Fe(n,p) Mn
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E263 − 09
6. Apparatus (Note 1)
6.1 High–Resolution Gamma-Ray Spectrometer, because of
its high resolution, the germanium detector is useful when
contaminant activities are present. SeeTest Methods E181 and
E1005.
6.2 Precision Balance, able to achieve the required accu-
racy.
6.3 Digital Computer, useful for data analysis (optional).
6.4 Chemical Separation Cylinder, borosilicate glass, about
25-mL capacity, equipped with stopcock and funnel. This
apparatus is illustrated in Fig. 2.
54 54
FIG. 1 Fe(n,p)
...
This document is not anASTM standard and is intended only to provide the user of anASTM 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:E 263–93 Designation: E263 – 09
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 (ϵ) 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 E 261E261).
8 −2 −1
1.3 With suitable techniques, fission-neutron fluence rates above 10 cm ·s can be determined. However, in the presence of
54
14 −2 −1 )
a high thermal-neutron fluence rate (for example, >2 3 10 cm ·s , Mn depletion should be investigated.
1.4Detailed procedures for other fast-neutron detectors are referenced in Practice E 261E 261
1.4 Detailed procedures describing the use of other fast-neutron detectors are referenced in Practice E261.
1.5 This standard does not purport to address all of the safety problems,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, Fluence, and Spectra by Radioactivation Techniques
3
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(IIC) E 706 (IIC)
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
3
E1005 Test Method forApplication andAnalysis of Radiometric Monitors for ReactorVessel Surveillance, E 706(IIIA) E 706
(IIIA)
E1018 Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706E 706E706 (IIB)
3. Terminology
3.1 Definitions:
3.1.1Refer to Terminology E 170E 170.
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
MnarecountedinaccordancewithMethodsE181E181andthereactionrate,asdefinedbyPracticeE261E261Mnarecounted
in accordance with Test Methods E181. The reaction rate, as defined by Practice E261, is calculated from the decay rate and
irradiation conditions.
1
ThistestmethodisunderthejurisdictionofASTMCommitteeE-10E10onNuclearTechnologyandApplicationsandisthedirectresponsibilityofSubcommitteeE10.05
on Nuclear Radiation Metrology.
Current edition approved Sept. 15, 1993. Published November 1993. Originally published as E 263–65T. Last previous edition E 263–88.
Current edition approved June 1, 2009. Published June 2009. Originally approved in 1965 as E263–65T. Last previous edition approved in 2005 as E263–05. DOI:
10.1520/E0263-09.
2
Annual Book of ASTM Standards, Vol 11.01.
2
ForreferencedASTMstandards,visittheASTMwebsite,www.astm.org,orcontactASTMCustomerServiceatservice@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 – 09
4.3The neutron fluence rate above about 2.2 MeV can then be calculated from the spectral-weighted neutron activation cross
section as defined by Practice E 261E 261
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 E 844E844 for
...
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