Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques

SIGNIFICANCE AND USE
Transmutation Processes—The effect on materials of bombardment by neutrons depends on the energy of the neutrons; therefore, it is important that the energy distribution of the neutron fluence, as well as the total fluence, be determined.
SCOPE
1.1 This practice describes procedures for the determination of neutron fluence rate, fluence, and energy spectra from the radioactivity that is induced in a detector specimen.
1.2 The practice is directed toward the determination of these quantities in connection with radiation effects on materials.
1.3 For application of these techniques to reactor vessel surveillance, see also Test Methods E1005.
1.4 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.
Note 1—Detailed methods for individual detectors are given in the following ASTM test methods: E262, E263, E264, E265, E266, E343, E393, E481, E523, E526, E704, E705, and E854.

General Information

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Historical
Publication Date
31-Dec-2009
Current Stage
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Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation: E261 − 10
StandardPractice for
Determining Neutron Fluence, Fluence Rate, and Spectra by
1
Radioactivation Techniques
This standard is issued under the fixed designation E261; 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 E265Test Method for Measuring Reaction Rates and Fast-
Neutron Fluences by Radioactivation of Sulfur-32
1.1 Thispracticedescribesproceduresforthedetermination
E266Test Method for Measuring Fast-Neutron Reaction
of neutron fluence rate, fluence, and energy spectra from the
Rates by Radioactivation of Aluminum
radioactivity that is induced in a detector specimen.
E343Test Method for Measuring Reaction Rates by Analy-
1.2 The practice is directed toward the determination of
sis of Molybdenum-99 Radioactivity From Fission Do-
these quantities in connection with radiation effects on mate- 3
simeters (Withdrawn 2002)
rials.
E393Test Method for Measuring Reaction Rates by Analy-
1.3 For application of these techniques to reactor vessel sis of Barium-140 From Fission Dosimeters
E481Test Method for Measuring Neutron Fluence Rates by
surveillance, see also Test Methods E1005.
Radioactivation of Cobalt and Silver
1.4 This standard does not purport to address all of the
E523Test Method for Measuring Fast-Neutron Reaction
safety concerns, if any, associated with its use. It is the
Rates by Radioactivation of Copper
responsibility of the user of this standard to establish appro-
E526Test Method for Measuring Fast-Neutron Reaction
priate safety and health practices and determine the applica-
Rates by Radioactivation of Titanium
bility of regulatory limitations prior to use.
E693Practice for Characterizing Neutron Exposures in Iron
NOTE 1—Detailed methods for individual detectors are given in the
and Low Alloy Steels in Terms of Displacements Per
following ASTM test methods: E262, E263, E264, E265, E266, E343,
Atom (DPA), E 706(ID)
E393, E481, E523, E526, E704, E705, and E854.
E704Test Method for Measuring Reaction Rates by Radio-
activation of Uranium-238
2. Referenced Documents
E705Test Method for Measuring Reaction Rates by Radio-
2
2.1 ASTM Standards:
activation of Neptunium-237
E170Terminology Relating to Radiation Measurements and
E722PracticeforCharacterizingNeutronFluenceSpectrain
Dosimetry
Terms of an Equivalent Monoenergetic Neutron Fluence
E181Test Methods for Detector Calibration andAnalysis of
for Radiation-Hardness Testing of Electronics
Radionuclides
E844Guide for Sensor Set Design and Irradiation for
E262Test Method for Determining Thermal Neutron Reac-
Reactor Surveillance, E 706 (IIC)
tion Rates and Thermal Neutron Fluence Rates by Radio-
E854Test Method for Application and Analysis of Solid
activation Techniques
State Track Recorder (SSTR) Monitors for Reactor
E263Test Method for Measuring Fast-Neutron Reaction
Surveillance, E706(IIIB)
Rates by Radioactivation of Iron
E944Guide for Application of Neutron Spectrum Adjust-
E264Test Method for Measuring Fast-Neutron Reaction
ment Methods in Reactor Surveillance, E 706 (IIA)
Rates by Radioactivation of Nickel
E1005Test Method for Application and Analysis of Radio-
metric Monitors for Reactor Vessel Surveillance, E 706
(IIIA)
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
E1018Guide for Application of ASTM Evaluated Cross
Technology and Applicationsand is the direct responsibility of Subcommittee
Section Data File, Matrix E706 (IIB)
E10.05 on Nuclear Radiation Metrology.
E2005Guide for Benchmark Testing of Reactor Dosimetry
CurrenteditionapprovedJan.1,2010.PublishedMay2010.Originallyapproved
in 1965 as E261–65T. Last previous edition approved in 2003 as E261–03. DOI: in Standard and Reference Neutron Fields
10.1520/E0261-10.
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 ----------------------
E261 − 10
2.2 ISO Standard: position of interest. When feasible, place the detectors in the
Guide in the Expression of Uncertainty in Measurement experiment capsule. In this case, long-term irradiations are
often required.
3. Terminology
8.3 Itisdesirable,butnotrequired,thattheneutrondetector
3.1 Descriptions of terms relating to dosimetry are found in
be irradiated
...

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 261–98 Designation:E261–10
Standard Practice for
Determining Neutron Fluence, Fluence Rate, and Spectra by
1
Radioactivation Techniques
This standard is issued under the fixed designation E261; 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.
1. Scope
1.1 Thispracticedescribesthegeneralproceduresforthedeterminationofneutronfluencerate,fluence,andenergyspectrafrom
the radioactivity that is induced in a detector specimen.
1.2 The practice is directed toward the determination of these quantities in connection with radiation effects on materials.
1.3 For application of these techniques to reactor vessel surveillance, see also Test Methods E 1005E1005.
1.4 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.
NOTE1—Detailed methods for individual detectors are given in the followingASTM test methods: E 262E 262, E 263E 263, E 264E 264, E 265E 265,
E 266E 266, E 343E 343, E 393E 393, E 418E 418, E 481E 481, E 523E 523, E 526E 526, E 704E 704, E 705E 705, and E 854E 844 1—Detailed
methods for individual detectors are given in the followingASTM test methods: E262, E263, E264, E265, E266, E343, E393, E481, E523, E526, E704,
E705, and E854.
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
E262 Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation
Techniques
E263 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron
E264 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
E265 Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
E266 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum
E343 Test Method for Measuring Reaction Rates byAnalysis of Molybdenum-99 Radioactivity fromFrom Fission Dosimeters
2
E393 Test Method for Measuring Reaction Rates by Analysis of Barium-140 from Fission Dosimeters
E418MethodforMeasuringFast-NeutronFluxbyTrack-EtchTechniqueTestMethodforMeasuringReactionRatesbyAnalysis
of Barium-140 From Fission Dosimeters
E481 Test Method for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver
E523 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
2
E526 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Titanium Test Method for Measuring
Fast-Neutron Reaction Rates by Radioactivation of Titanium
E693 PracticeforCharacterizingNeutronExposuresinIronandLowAlloySteelsinTermsofDisplacementsPerAtom(DPA),
E 706(ID)
E704 Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
2
E705 Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237 Test Method for Measuring Reaction
Rates by Radioactivation of Neptunium-237
E722 Practice for Characterizing Neutron Fluence Spectra in Terms of an Equivalent Monoenergetic Neutron Fluence for
Radiation-Hardness Testing of Electronics
1
This practice is under the jurisdiction ofASTM Committee E-10 E10 on Nuclear Technology andApplications and is the direct responsibility of Subcommittee E10.05
on Nuclear Radiation Metrology.
Current edition approved Dec. 10, 1996. Published February 1997. Originally published as E 261–65T. Last previous edition E 261–96.
Current edition approved Jan. 1, 2010. Published May 2010. Originally approved in 1965 as E261–65T. Last previous edition approved in 2003 as E261–03. DOI:
10.1520/E0261-10.
2
ForreferencedASTMstandards,visittheASTMwebsite,www.astm.org,orcontactASTMCustomerServiceatservice@astm.org.For Annual Book of ASTM Standards
, Vol 12.02.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 ----------------------
E261–10
2
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(
...

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