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Dose Deposition Profiles in Untreated Brick Material

O’Mara, Ryan; Hayes, Robert*

doi: 10.1097/HP.0000000000000843

In nuclear forensics or accident dosimetry, building materials such as bricks can be used to retrospectively determine radiation fields using thermoluminescence and/or optically stimulated 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 treatment. This method was tested by estimating the gamma-ray energies 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 reconstructions in the wake of nuclear accidents or for any related application where doses of interest are large compared to overall process system noise.

*North Carolina State University, Nuclear Engineering Department, Raleigh, NC.

The authors declare no conflicts of interest.

For correspondence contact: Ryan O’Mara, North Carolina State University, Nuclear Engineering Department, 1009 Capability Dr., Raleigh NC 27606 or emai at:

(Manuscript accepted 15 December 2017)

© 2018 by the Health Physics Society