ASTM E2450-11

Standard Practice for Application of CaF₂(Mn) Thermoluminescence Dosimeters in Mixed Neutron-Photon Environments

SCOPE
1.1 This practice describes a procedure for measuring gamma-ray absorbed dose in CaF2(Mn) thermoluminescence dosimeters (TLDs) exposed to mixed neutron-photon environments during irradiation of materials and devices. The practice has broad application, but is primarily intended for use in the radiation-hardness testing of electronics. The practice is applicable to the measurement of absorbed dose from gamma radiation present in fields used for neutron testing.
1.2 This practice describes a procedure for correcting for the neutron response of a CaF2(Mn) TLD. The neutron response may be subtracted from the total response to give the gamma-ray response. In fields with a large neutron contribution to the total response, this procedure may result in large uncertainties.
1.3 More precise experimental techniques may be applied if the uncertainty derived from this practice is larger than the user can accept. These techniques are not discussed here. The references in Section 8 describe some of these techniques.
1.4 This practice does not discuss effects on the TLD reading of neutron interactions with material surrounding the TLD to ensure charged particle equilibrium. These effects depend on the surrounding material and its thickness, and on the neutron spectrum (1).

General Information

• Status: Historical
• Publication Date: 31-Oct-2011
• ICS: 17.240 - Radiation measurements
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.07 - Radiation Dosimetry for Radiation Effects on Materials and Devices

Relations

• Replaces: ASTM E2450-06 - Standard Practice for Application of CaF<inf>2</inf>(Mn) Thermoluminescence Dosimeters in Mixed Neutron-Photon Environments
• Effective Date: 01-Nov-2011
• Referred By: ASTM E1855-20 - Standard Test Method for Use of 2N2222A Silicon Bipolar Transistors as Neutron Spectrum Sensors and Displacement Damage Monitors
• Effective Date: 01-Nov-2011
• Referred By: ASTM F1190-18 - Standard Guide for Neutron Irradiation of Unbiased Electronic Components
• Effective Date: 01-Nov-2011
• Referred By: ASTM E668-20 - Standard Practice for Application of Thermoluminescence-Dosimetry (TLD) Systems for Determining Absorbed Dose in Radiation-Hardness Testing of Electronic Devices
• Effective Date: 01-Nov-2011
• Referred By: ASTM E1854-19 - Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
• Effective Date: 01-Nov-2011

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: E2450 − 11
StandardPractice for
Application of CaF (Mn) Thermoluminescence Dosimeters in
2
1
Mixed Neutron-Photon Environments
This standard is issued under the fixed designation E2450; 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 Dose in Radiation-HardnessTesting of Electronic Devices
E720 Guide for Selection and Use of Neutron Sensors for
1.1 This practice describes a procedure for correcting a
Determining Neutron Spectra Employed in Radiation-
CaF (Mn) thermoluminescence dosimeter (TLD) reading for
2
Hardness Testing of Electronics
its response to neutrons during the irradiation. The neutron
E721 Guide for Determining Neutron Energy Spectra from
response may be subtracted from the total TLD response to
Neutron Sensors for Radiation-Hardness Testing of Elec-
give the gamma-ray response. In fields with a large neutron
tronics
contribution to the total response, this procedure may result in
E722 PracticeforCharacterizingNeutronFluenceSpectrain
large uncertainties.
Terms of an Equivalent Monoenergetic Neutron Fluence
1.2 More precise experimental techniques may be applied if
for Radiation-Hardness Testing of Electronics
the uncertainty derived from this practice is larger than the
E1854 Practice for Ensuring Test Consistency in Neutron-
level that the user can accept. These more precise techniques
Induced Displacement Damage of Electronic Parts
are not discussed here. The references in Section 8 describe
F1190 Guide for Neutron Irradiation of Unbiased Electronic
some of these techniques.
Components
1.3 This practice does not discuss effects on the TLD
3. Terminology
reading from neutron interactions with the material surround-
3.1 Definitions:
ing the TLD and used to ensure a charged particle equilibrium.
3.1.1 absorbed dose—see Terminology E170.
These effects will depend on the isotopic composition of the
surrounding material and its thickness, and on the incident
3.1.2 exposure—see Terminology E170.
2
neutron spectrum (1).
3.1.3 kerma—see Terminology E170.
1.4 The values stated in SI units are to be regarded as
3.1.4 linear energy transfer (LET)—the energy loss per unit
standard.
distance as a charged particle passes through a material.
Electrons resulting from gamma-ray interactions in a material
2. Referenced Documents
generally have a low LET. Heavy charged particles resulting
3
2.1 ASTM Standards:
from neutron interactions with a material generally have a high
E170 Terminology Relating to Radiation Measurements and
LET.
Dosimetry
3.1.5 neutron sensitivity m(E)—the ratio of the detector
E666 Practice for CalculatingAbsorbed Dose From Gamma
reading, that is, the effective neutron dose, to the neutron
or X Radiation
fluence. Thus,
E668 Practice for Application of Thermoluminescence-
M E
~ !
Dosimetry (TLD) Systems for Determining Absorbed
m~E! 5 (1)
Φ~E!
where:
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
Φ(E) = the neutron fluence, and
Technology and Applications and is the direct responsibility of Subcommittee
E10.07 on Radiation Dosimetry for Radiation Effects on Materials and Devices.
M(E) = the apparent dose (light output) in the TLD caused
Current edition approved Nov. 1, 2011. Published November 2011. Originally
by neutrons of energy E.
approved in 2005. Last previous edition approved in 2006 as E2450-06. DOI:
10.1520/E2450-11.
4. Significance and Use
2
The boldface numbers in parentheses refer to the list of references at the end of
this standard.
4.1 Electronic devices are typically tested for survivability
3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
to gamma radiation in pure gamma-ray fields. Testing elec-
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
tronic device response against neutrons is more complex since
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. there is invariably a gamma-ray component in addition to the
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E2450 − 11
neutron field.The gamma-ray response of the electronic device 5.3 The neutron spectrum must be known (see Guides E720
is typically subtracted from the overall response to find the and E721). This may be determined in a separate exposure. A
device response to neutrons. This approach to the testing neutron monitor should be used on the irradiation along with
requires a determination of the gamma-ray exposure in the the device under test
...

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:E2450–06 Designation:E2450–11
Standard Practice for
Application of CaF (Mn) Thermoluminescence Dosimeters in
2
1
Mixed Neutron-Photon Environments
This standard is issued under the fixed designation E2450; 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
1.1This practice describes a procedure for measuring gamma-ray absorbed dose in CaF
1.1 This practice describes a procedure for correcting a CaF (Mn) thermoluminescence dosimeters (TLDs) exposed to mixed
2
neutron-photon environments during irradiation of materials and devices. The practice has broad application, but is primarily
intended for use in the radiation-hardness testing of electronics. The practice is applicable to the measurement of absorbed dose
from gamma radiation present in fields used for neutron testing.
1.2This practice describes a procedure for correcting for the neutron response of a CaF (Mn) TLD. The neutron response may
2
be subtracted from the total response to give the gamma-ray response. In fields with a large neutron contribution to the total
response, this procedure may result in large uncertainties.
1.3More precise experimental techniques may be applied if the uncertainty derived from this practice is larger than the user can
accept. These techniques are not discussed here. The references in Section 8 describe some of these techniques.
1.4ThispracticedoesnotdiscusseffectsontheTLDreadingofneutroninteractionswithmaterialsurroundingtheTLDtoensure
chargedparticleequilibrium.Theseeffectsdependonthesurroundingmaterialanditsthickness,andontheneutronspectrum(Mn)
thermoluminescence dosimeter (TLD) reading for its response to neutrons during the irradiation. The neutron response
maybesubtractedfromthetotalTLDresponsetogivethegamma-rayresponse.Infieldswithalargeneutroncontribution
to the total response, this procedure may result in large uncertainties.
1.2 More precise experimental techniques may be applied if the uncertainty derived from this practice is larger than the level
that the user can accept. These more precise techniques are not discussed here. The references in Section 8 describe some of these
techniques.
1.3 This practice does not discuss effects on the TLD reading from neutron interactions with the material surrounding the TLD
and used to ensure a charged particle equilibrium. These effects will depend on the isotopic composition of the surrounding
2
material and its thickness, and on the incident neutron spectrum (1).
1.4 The values stated in SI units are to be regarded as standard.
2. Referenced Documents
3
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and Dosimetry
E666 Practice for Calculating Absorbed Dose From Gamma or X Radiation
E668 Practice for Application of Thermoluminescence-Dosimetry (TLD) Systems for Determining Absorbed Dose in
Radiation-Hardness Testing of Electronic Devices
E720 Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness
Testing of Electronics
E721 Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics
E722 Practice for Characterizing Neutron Fluence Spectra in Terms of an Equivalent Monoenergetic Neutron Fluence for
Radiation-Hardness Testing of Electronics
E1854 Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
F1190 Guide for Neutron Irradiation of Unbiased Electronic Components
1
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 MayNov. 1, 2006.2011. Published May 2006.November 2011. Originally approved in 2005. Last previous edition approved in 20052006 as
E2450-05.E2450-06. DOI: 10.1520/E2450-06.10.1520/E2450-11.
2
The boldface numbers in parentheses refer to the list of references at the end of this standard.
3
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at [e-mail]. 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 C70
...