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Title: Dose Deposition Profiles in Untreated Brick Material

In nuclear forensics or accident dosimetry, building materials such as bricks can be used to retrospectively determine radiation fields using thermoluminescence and/or optically stimu-lated luminescence. A major problem with brick material is that significant chemical processing is generally necessary to isolate the quartz from the brick. In this study, a simplified treatment process has been tested in an effort to lessen the processing burden for retrospective dosimetry studies. It was found that by using thermoluminescence responses, the dose deposition profile of a brick sample could be reconstructed without any chemical treat-ment. This method was tested by estimating the gamma-ray ener-gies of an 241Am source from the dose deposition in a brick. The results demonstrated the ability to retrospectively measure the source energy with an overall energy resolution of approximately 6 keV. This technique has the potential to greatly expedite dose re-constructions in the wake of nuclear accidents or for any related application where doses of interest are large compared to overall process system noise.
Authors:
 [1] ;  [1]
  1. North Carolina State Univ., Raleigh, NC (United States)
Publication Date:
Grant/Contract Number:
NA0002576
Type:
Accepted Manuscript
Journal Name:
Health Physics
Additional Journal Information:
Journal Volume: 114; Journal Issue: 4; Journal ID: ISSN 0017-9078
Publisher:
Health Physics Society
Research Org:
North Carolina State Univ., Raleigh, NC (United States)
Sponsoring Org:
USDOE National Nuclear Security Administration (NNSA), Office of Nonproliferation and Verification Research and Development (NA-22)
Country of Publication:
United States
Language:
English
Subject:
61 RADIATION PROTECTION AND DOSIMETRY
OSTI Identifier:
1438010

O'Mara, Ryan, and Hayes, Robert. Dose Deposition Profiles in Untreated Brick Material. United States: N. p., Web. doi:10.1097/HP.0000000000000843.
O'Mara, Ryan, & Hayes, Robert. Dose Deposition Profiles in Untreated Brick Material. United States. doi:10.1097/HP.0000000000000843.
O'Mara, Ryan, and Hayes, Robert. 2018. "Dose Deposition Profiles in Untreated Brick Material". United States. doi:10.1097/HP.0000000000000843.
@article{osti_1438010,
title = {Dose Deposition Profiles in Untreated Brick Material},
author = {O'Mara, Ryan and Hayes, Robert},
abstractNote = {In nuclear forensics or accident dosimetry, building materials such as bricks can be used to retrospectively determine radiation fields using thermoluminescence and/or optically stimu-lated luminescence. A major problem with brick material is that significant chemical processing is generally necessary to isolate the quartz from the brick. In this study, a simplified treatment process has been tested in an effort to lessen the processing burden for retrospective dosimetry studies. It was found that by using thermoluminescence responses, the dose deposition profile of a brick sample could be reconstructed without any chemical treat-ment. This method was tested by estimating the gamma-ray ener-gies of an 241Am source from the dose deposition in a brick. The results demonstrated the ability to retrospectively measure the source energy with an overall energy resolution of approximately 6 keV. This technique has the potential to greatly expedite dose re-constructions in the wake of nuclear accidents or for any related application where doses of interest are large compared to overall process system noise.},
doi = {10.1097/HP.0000000000000843},
journal = {Health Physics},
number = 4,
volume = 114,
place = {United States},
year = {2018},
month = {4}
}