ASTM E2450-23

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Designation: E2450 − 16 E2450 − 23
Standard Practice for
Application of CaF (Mn) Thermoluminescence Dosimeters in
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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
1.1 This practice describes a procedure for correcting a CaF (Mn) thermoluminescence dosimeter (TLD) reading for its response
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to neutrons during the irradiation. The neutron response may be subtracted from the total TLD 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.
1.2 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 88 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
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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.
1.5 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.
2. Referenced Documents
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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
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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 June 1, 2016Jan. 1, 2023. Published July 2016January 2023. Originally approved in 2005. Last previous edition approved in 20112016 as
E2450 – 11.E2450 – 16. DOI: 10.1520/E2450-16.10.1520/E2450-23.
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The boldface numbers in parentheses refer to the list of references at the end of this standard.
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volume information, refer to the standard’s Document Summary page on the ASTM website.
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E2450 − 23
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
3. Terminology
3.1 Definitions:
3.1.1 absorbed dose—see Terminology E170.
3.1.2 exposure—see Terminology E170.
3.1.3 kerma—see Terminology E170.
3.1.4 linear energy transfer (LET)—the energy loss per unit distance as a charged particle passes through a material.
3.1.4.1 Discussion—
Electrons resulting from gamma-ray interactions in a material generally have a low LET. Heavy charged particles resulting from
neutron interactions with a material generally have a high LET.
3.1.5 neutron sensitivity m(E)—the ratio of the detector reading, that is, the effective neutron dose, to the neutron fluence. Thus,
M~E!
m~E! 5 (1)
Φ~E!
where:
Φ(E) = the neutron fluence, and
M(E) = the apparent dose (light output) in the TLD caused by neutrons of energy E.
4. Significance a
...