Standard Practice for Conducting Irradiations at Accelerator-Based Neutron Sources

ABSTRACT
This practice covers procedures for irradiations at accelerator-based neutron sources. The discussion focuses on nearly monoenergetic 14-MeV neutrons from the deuterium-tritium T(d,n) interaction, and broad spectrum neutrons from stopping deuterium beams in thick beryllium or lithium targets. However, most of the recommendations also apply to other types of accelerator-based sources, including spallation neutron sources. The procedures to be considered include methods for characterizing the accelerator beam and target, the irradiated sample, and the neutron flux and spectrum, as well as procedures for recording and reporting irradiation data.
SCOPE
1.1 This practice covers procedures for irradiations at accelerator-based neutron sources. The discussion focuses on two types of sources, namely nearly monoenergetic 14-MeV neutrons from the deuterium-tritium T(d,n) interaction, and broad spectrum neutrons from stopping deuterium beams in thick beryllium or lithium targets. However, most of the recommendations also apply to other types of accelerator-based sources, including spallation neutron sources (1).2 Interest in spallation sources has increased recently due to their development of high-power, high-flux sources for neutron scattering and their proposed use for transmutation of fission reactor waste (2).  
1.2 Many of the experiments conducted using such neutron sources are intended to provide a simulation of irradiation in another neutron spectrum, for example, that from a DT fusion reaction. The word simulation is used here in a broad sense to imply an approximation of the relevant neutron irradiation environment. The degree of conformity can range from poor to nearly exact. In general, the intent of these experiments is to establish the fundamental relationships between irradiation or material parameters and the material response. The extrapolation of data from such experiments requires that the differences in neutron spectra be considered.  
1.3 The procedures to be considered include methods for characterizing the accelerator beam and target, the irradiated sample, and the neutron flux (fluence rate) and spectrum, as well as procedures for recording and reporting irradiation data.  
1.4 Other experimental problems, such as temperature control, are not included.  
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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Publication Date
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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: E798 − 16
Standard Practice for
Conducting Irradiations at Accelerator-Based Neutron
1
Sources
This standard is issued under the fixed designation E798; 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 1.6 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the
1.1 This practice covers procedures for irradiations at
responsibility of the user of this standard to establish appro-
accelerator-based neutron sources. The discussion focuses on
priate safety, health, and environmental practices and deter-
two types of sources, namely nearly monoenergetic 14-MeV
mine the applicability of regulatory limitations prior to use.
neutrons from the deuterium-tritium T(d,n) interaction, and
1.7 This international standard was developed in accor-
broad spectrum neutrons from stopping deuterium beams in
dance with internationally recognized principles on standard-
thick beryllium or lithium targets. However, most of the
ization established in the Decision on Principles for the
recommendations also apply to other types of accelerator-
2 Development of International Standards, Guides and Recom-
based sources, including spallation neutron sources (1). Inter-
mendations issued by the World Trade Organization Technical
est in spallation sources has increased recently due to their
Barriers to Trade (TBT) Committee.
development of high-power, high-flux sources for neutron
scattering and their proposed use for transmutation of fission
2. Referenced Documents
reactor waste (2).
3
2.1 ASTM Standards:
1.2 Many of the experiments conducted using such neutron
C859Terminology Relating to Nuclear Materials
sources are intended to provide a simulation of irradiation in
E170Terminology Relating to Radiation Measurements and
another neutron spectrum, for example, that from a DT fusion
Dosimetry
reaction. The word simulation is used here in a broad sense to
E181Test Methods for Detector Calibration andAnalysis of
imply an approximation of the relevant neutron irradiation
Radionuclides
environment.Thedegreeofconformitycanrangefrompoorto
E261Practice for Determining Neutron Fluence, Fluence
nearly exact. In general, the intent of these experiments is to
Rate, and Spectra by Radioactivation Techniques
establish the fundamental relationships between irradiation or
E263Test Method for Measuring Fast-Neutron Reaction
material parameters and the material response. The extrapola-
Rates by Radioactivation of Iron
tionofdatafromsuchexperimentsrequiresthatthedifferences
E264Test Method for Measuring Fast-Neutron Reaction
in neutron spectra be considered.
Rates by Radioactivation of Nickel
1.3 The procedures to be considered include methods for
E265Test Method for Measuring Reaction Rates and Fast-
characterizing the accelerator beam and target, the irradiated
Neutron Fluences by Radioactivation of Sulfur-32
sample, and the neutron flux (fluence rate) and spectrum, as
E266Test Method for Measuring Fast-Neutron Reaction
wellasproceduresforrecordingandreportingirradiationdata.
Rates by Radioactivation of Aluminum
1.4 Other experimental problems, such as temperature E393Test Method for Measuring Reaction Rates byAnaly-
sis of Barium-140 From Fission Dosimeters
control, are not included.
E854Test Method for Application and Analysis of Solid
1.5 The values stated in SI units are to be regarded as
State Track Recorder (SSTR) Monitors for Reactor Sur-
standard. No other units of measurement are included in this
veillance
standard.
E910Test Method for Application and Analysis of Helium
Accumulation Fluence Monitors for Reactor Vessel Sur-
1
veillance
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applications and is the direct responsibility of Subcommittee
E10.07 on Radiation Dosimetry for Radiation Effects on Materials and Devices.
Current edition approved Oct. 1, 2016. Published December 2016. Originally
3
approved in 1981. Last previous edition approved in 2009 as E798–96(2009). For referenced ASTM standards, visit the ASTM website, www.astm.org, or
DOI: 10.1520/E0798-16. contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
2
The boldface numbers in parentheses refer to a list of references at the end of Standards volume information, refer to the standard’s Document Summary page on
this practice. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Dr
...

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: E798 − 96 (Reapproved 2009) E798 − 16
Standard Practice for
Conducting Irradiations at Accelerator-Based Neutron
1
Sources
This standard is issued under the fixed designation E798; 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 practice covers procedures for irradiations at accelerator-based neutron sources. The discussion focuses on two types
of sources, namely nearly monoenergetic 14-MeV neutrons from the deuterium-tritium T(d,n) interaction, and broad spectrum
neutrons from stopping deuterium beams in thick beryllium or lithium targets. However, most of the recommendations also apply
2
to other types of accelerator-based sources, including spallation neutron sources (1). Interest in spallation sources has increased
recently due to their development of high-power, high-flux sources for neutron scattering and their proposed use for transmutation
of fission reactor waste (2).
1.2 Many of the experiments conducted using such neutron sources are intended to simulate provide a simulation of irradiation
in another neutron spectrum, for example, that from a DT fusion reaction. The word simulation is used here in a broad sense to
imply an approximation of the relevant neutron irradiation environment. The degree of conformity can range from poor to nearly
exact. In general, the intent of these simulationsexperiments is to establish the fundamental relationships between irradiation or
material parameters and the material response. The extrapolation of data from such experiments requires that the differences in
neutron spectra be considered.
1.3 The procedures to be considered include methods for characterizing the accelerator beam and target, the irradiated sample,
and the neutron flux (fluence rate) and spectrum, as well as procedures for recording and reporting irradiation data.
1.4 Other experimental problems, such as temperature control, are not included.
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
3
2.1 ASTM Standards:
C859 Terminology Relating to Nuclear Materials
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
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
E393 Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters
E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance,
E706(IIIB)
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applicationsand is the direct responsibility of Subcommittee E10.08 on
Procedures for Neutron Radiation Damage Simulation.
Current edition approved Aug. 1, 2009Oct. 1, 2016. Published September 2009December 2016. Originally approved in 1981. Last previous edition approved in 20032009
as E798 – 96 (2003).(2009). DOI: 10.1520/E0798-96R09.10.1520/E0798-16.
2
The boldface numbers in parentheses refer to a list of references at the end of this practice.
3
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

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E798 − 16
E910 Test Method for Application and Analysis of Helium Accumulation Fluence
...

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