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Ambient dose equivalent measurement with a CsI(Tl) based electronic personal dosimeter

  • Park, Kyeongjin (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Kim, Jinhwan (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Lim, Kyung Taek (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Kim, Junhyeok (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Chang, Hojong (Institute for Information Technology Convergence, Korea Advanced Institute of Science and Technology) ;
  • Kim, Hyunduk (IRIS Co., Ltd.) ;
  • Sharma, Manish (Department of Nuclear Engineering, Khalifa University) ;
  • Cho, Gyuseong (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology)
  • Received : 2019.02.14
  • Accepted : 2019.06.17
  • Published : 2019.12.25

Abstract

In this manuscript, we present a method for the direct calculation of an ambient dose equivalent (H* (10)) for the external gamma-ray exposure with an energy range of 40 keV to 2 MeV in an electronic personal dosimeter (EPD). The designed EPD consists of a 3 × 3 ㎟ PIN diode coupled to a 3 × 3 × 3 ㎣ CsI (Tl) scintillator block. The spectrum-to-dose conversion function (G(E)) for estimating H* (10) was calculated by applying the gradient-descent method based on the Monte-Carlo simulation. The optimal parameters for the G(E) were found and this conversion of the H* (10) from the gamma spectra was verified by using 241Am, 137Cs, 22Na, 54Mn, and 60Co radioisotopes. Furthermore, gamma spectra and H* (10) were obtained for an arbitrarily mixed multiple isotope case through Monte-Carlo simulation in order to expand the verification to more general cases. The H* (10) based on the G(E) function for the gamma spectra was then compared with H* (10) calculated by simulation. The relative difference of H* (10) from various single-source spectra was in the range of ±2.89%, and the relative difference of H* (10) for a multiple isotope case was in the range of ±5.56%.

Keywords

References

  1. International Comission on Radiation Units and Measurements, Quantities and Units in Radiaiton Protectrion Dosimetry, 1996.
  2. P. Buzhan, A. Karakash, Teverovskiy Yu, Silicon photomultiplier and Csi(Tl) scintillator in application to portable H*(10) dosimeter, Nucl. Instrum. Methods Phys. Res. Sect. A Accel. Spectrom. Detect. Assoc. Equip. 912 (2018) 245-247. https://doi.org/10.1016/j.nima.2017.11.067
  3. R. Casanovas, E. Prieto, M. Salvado, Calculation of the ambient dose equivalent H*(10) from gamma-ray spectra obtained with scintillation detectors, Appl. Radiat. Isot. 118 (2016) 154-159. https://doi.org/10.1016/j.apradiso.2016.09.001
  4. A. Camp, A. Vargas, Ambient dose estimation H*(10) from Labr3(Ce) spectra, Radiat. Protect. Dosim. 160 (4) (2014) 264-268. https://doi.org/10.1093/rpd/nct342
  5. C.Y. Yi, et al., Measurement of ambient dose equivalent using a Nai(Tl) scintillation detector, Radiat. Protect. Dosim. 74 (4) (1997) 273-278. https://doi.org/10.1093/oxfordjournals.rpd.a032207
  6. P. Kessler, et al., Novel spectrometers for environmental dose rate monitoring, J. Environ. Radioact. 187 (2018) 115-121. https://doi.org/10.1016/j.jenvrad.2018.01.020
  7. International Commission on Radiological Protection, Conversion Coefficients for Use in Radiological Protection against External Radiation, vol. 74, ICRP Publication, 1996.
  8. S. Tsuda, et al., Characteristics and verification of a Car-borne survey system for dose rates in air: kurama-ii, J. Environ. Radioact. 139 (2015) 260-265. https://doi.org/10.1016/j.jenvrad.2014.02.028
  9. S. Tsuda, K. Saito, Spectrum-dose conversion operator of Nai(Tl) and Csi(Tl) scintillation detectors for air dose rate measurement in contaminated environments, J. Environ. Radioact. 166 (Pt 3) (2017) 419-426. https://doi.org/10.1016/j.jenvrad.2016.02.008
  10. P. Huang, Measurement of air kerma rate and ambient dose equivalent rate using the G(E) function with hemispherical cdznte detector, Nucl. Sci. Tech. 29 (3) (2018) 35. https://doi.org/10.1007/s41365-018-0375-3
  11. S. Moriuchi, I. Miyanaga, A spectrometric method for measurement of lowlevel gamma exposure dose, Health Phys. 12 (1966) 541-551. https://doi.org/10.1097/00004032-196604000-00009
  12. H. Terada, et al., Spectrum-to-Exposure rate conversion function of a Ge(Li) insitu environmental gamma-ray spectrometer, IEEE Trans. Nucl. Sci. 24 (1) (1977) 647-651. https://doi.org/10.1109/TNS.1977.4328758
  13. Masahiro Tsutsumi, Yoshihiko Tanimura, $LaCl_3(Ce)$ scintillation detector applications for environmental gamma-ray measurements of low to high dose rates, Nucl. Instrum. Methods Phys. Res. Sect. A Accel. Spectrom. Detect. Assoc. Equip. 557 (2) (2006) 554-560. https://doi.org/10.1016/j.nima.2005.11.117
  14. D.B. Pelowitz, et al., MCNP6 User's Manual, version 1.0, Report No. LA-CP-13-00634, Rev. 0, Los Alamos National Laboratory, 2013.
  15. P. Buzhan, et al., Silicon photomultiplier and its possible applications, Nucl. Instrum. Methods Phys. Res. Sect. A Accel. Spectrom. Detect. Assoc. Equip. 504 (1-3) (2003) 48-52. https://doi.org/10.1016/S0168-9002(03)00749-6
  16. B. Dolgoshein, et al., Status report on silicon photomultiplier development and its applications, Nucl. Instrum. Methods Phys. Res. Sect. A Accel. Spectrom. Detect. Assoc. Equip. 563 (2) (2006) 368-376. https://doi.org/10.1016/j.nima.2006.02.193
  17. P. Buzhan, et al., An advanced study of silicon photomultiplier, in: Proceedings of the Seventh International Conference on Advance Technology & Particle Physics, 2002, pp. 717-728.
  18. Daisuke Totsuka, et al., Performance test of Si pin photodiode line scanner for thermal neutron detection, Nucl. Instrum. Methods Phys. Res. Sect. A Accel. Spectrom. Detect. Assoc. Equip. 659 (1) (2011) 399-402. https://doi.org/10.1016/j.nima.2011.08.014
  19. B.E. Patt, et al., High resolution CsI(Tl)/Si-PIN detector development for breast imaging, IEEE Trans. Nucl. Sci. 45 (1998) 2126-2131. https://doi.org/10.1109/23.708319
  20. D. Clement, et al., Development of a 3D position sensitive scintillation detector using neural networks, IEEE Nucl. Sci. Symp. Conf. Rec. (1998) 1448-1452.
  21. F. Knoll, Glenn, Radiation Detection and Measurement, John wiley & Sons, 2010.

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