Abstract
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 a 137Cs source. The results show that the simulated efficiencies are fairly consistent with the measured ones for 137Cs, 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.
Original language | English |
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Pages (from-to) | 59-63 |
Number of pages | 5 |
Journal | Radioprotection |
Volume | 51 |
Issue number | 1 |
DOIs | |
Publication status | Published - Jan 2016 |
Externally published | Yes |
Keywords
- whole-body counter
- Monte Carlo simulation
- lung counting
- counting efficiency