Monte Carlo simulation of lung counting efficiency using a whole-body counter at a nuclear power plant
Radioprotection, ISSN: 1769-700X, Vol: 51, Issue: 1, Page: 59-63
2016
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Article Description
In order to routinely evaluate workers’ internal exposure due to intake of radionuclides, a whole-body counter (WBC) at the Third Qinshan Nuclear Power Co. Ltd. (TQNPC) is used. Counting would typically occur immediately after a confirmed or suspected inhalation exposure. The counting geometry would differ as a result of the height of the individual being counted, which would result in over- or underestimated intake(s). In this study, Monte Carlo simulation was applied to evaluate the counting efficiency when performing a lung count using the WBC at the TQNPC. In order to validate the simulated efficiencies for lung counting, the WBC was benchmarked for various lung positions using aCs source. The results show that the simulated efficiencies are fairly consistent with the measured ones forCs, with a relative error of 0.289%. For a lung organ simulation, the discrepancy between the calibration phantom and the Chinese reference adult person (170 cm) was within 6% for peak energies ranging from 59.5 keV to 2000 keV. The relative errors vary from 4.63% to 8.41% depending on the person’s height and photon energy. Therefore, the simulation technique is effective and practical for lung counting, which is difficult to calibrate using a physical phantom.
Bibliographic Details
http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=85047831878&origin=inward; http://dx.doi.org/10.1051/radiopro/2015030; http://www.radioprotection.org/10.1051/radiopro/2015030; https://dx.doi.org/10.1051/radiopro/2015030; https://www.radioprotection.org/articles/radiopro/abs/2016/01/radiopro150030/radiopro150030.html
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