Calculation of Spectrum to Dose Conversion Factors for a NaI(TI) Scintillation Detector Using the Response Matrix

Jun, Jae-Shik;Yi, Chul-Young;Chai, Ha-Seok;Cho, Hyuck

  • Published : 1995.11.01

Abstract

A method for converting a ${\gamma}$-ray spectrum measured by a NaI(TI) scintillation detector to a dose, namely, conversion of a spectrum to an exposure, a spectrum to an air kerma, and a spectrum to a dose equivalent, is presented. A Monte Carlo simulation code was developed to calculate the response functions of the NaI(TI) scintillation detector for arbitrary ${\gamma}$-ray energies. The effect of the detector cap, the nonlinear light output of the NaI(TI) crystal in the low-energy region, and all possible processes involved in photon and electron transport, such as the photoelectric effect, compton scattering, pair production, and bremsstrahlung, were taken into account in the course of the simulation procedure. Response matrices of three different sizes($30\;{\times}\;30,\;40\;{\times}\;40,\;and\;50{\times}\;50$) were constructed by combining the response functions of a $3"{\phi}\;{\times}3"$ NaI(TI) spectrometer for ${\gamma}$-ray energies up to 3 MeV. Conversion factors for the measured spectrum to dose were evaluated by weighting the diagonal components of the inverse matrices so that the deviation deduced from the theoretical values might be the least. In order to confirm the applicability of the calculated conversion factors, the factors were used in the conversion of a measured spectrum to a dose, and the result was compared with those obtained by the G(E) operator and the energy-band methods.

Keywords

References

  1. J. Nucl. Sic. Tech. v.7 S. Minato;M. Kawano
  2. In-situ Ge(Li) and NaI(Tl) Gamma-Ray Spectrometry, HASL-258 H. L. Beck;J. DeCampo;C. Gogolak
  3. A New Method of Dose Evaluation by Spectrum - Dose conversion Operator and Determination of the Operator S. Moriuchi
  4. Photon Cross Sections, Attenuation Coefficients and Energy Absorption Coefficients from 10 keV to 100 GeV, NSRDS-NBS 29 J. H. Hubbell
  5. Alphs-, Beta- and Gamma-Ray Spectroscopy K. Siegbahn
  6. Photon Cross Sections, Attenuation Coefficients and Energy Absorption Coefficients from 10 keV to 100 GeV, NSRDS-NBS 29 J. H. Hubbell
  7. Photon Cross Sections from 0.001 to 100 MeV for Elements 1 through 100, LA-3753 E. Storm;H. I. Israel
  8. Rev. Mod. Phys. v.24 F. Sauter;C. M. Davisson;R. D. Evans
  9. Nucl. Instr. Meth. v.116 B. Grosswendt
  10. Meth. Comp. Phys. v.1 M. J. Berger
  11. Nucl. Instr. Meth. v.103 T. Tabata;R. Ito;S. Okabe
  12. Nucl. Instr. Meth. v.12 C. D. Zerby;A. Meyer;R. B. Murray
  13. EML Procedure Manual, HASL-300 K. M. Miller;G. de Planque(ed.);P. W. Krey(ed.)
  14. Nucl. Instr. Meth. v.104 M. J. Berger;S. M. Seltzer
  15. Phys. Med. Biol. v.32 M. Boutillon;A. M. Perroche-Roux
  16. Recommendations of the International Commission on Radiological Protection, ICRP Publication 26 ICRP(International Commission on Radiological Protection)
  17. Determination of Dose Equivalents Resulting from External Radiation Sources, ICRU Report 39 ICRU(Internation Commission on Radiation Units and Measurements)
  18. Determination of Dose Equivalents from External Radiation Sources - Part 2, ICRU Report 43 ICRU
  19. Measutement of Dose Equivalents from External Photon and Electron Radiations, ICRU Report 47 ICRU
  20. A Dosimetric Instrument Based on the Spectrum Weighting Function Method for Environmental Radiation Measurements, JAERI-M 7066 S. Moriuchi
  21. New Phys. v.30 J. S. Jun;H. S. Chai;B. Y. Lee;H. C. Kim;D. J. Lee;D. S. Kim;D. H. Um