Monte Carlo Study of MOSFET Dosimeter Dose Correction Factors Considering Energy Spectrum of Radiation Field in a Steam Generator Channel Head

원전 증기발생기 수실 내 에너지 스펙트럼을 고려한 MOSFET 방사선검출기 선량보정인자 결정에 관한 몬테칼로 전산모사 연구

  • 조성구 (한양대학교 원자력공학과) ;
  • 최상현 (한양대학교 원자력공학과) ;
  • 김찬형 (한양대학교 원자력공학과)
  • Published : 2006.12.30

Abstract

In Korea, a real-time effective dose measurement system is in development. The system uses 32 high-sensitivity MOSFET dosimeters to measure radiation doses at various organ locations in an anthropomorphic physical phantom. The MOSFET dosimeters are, however, mainly made of silicon and shows some degree of energy and angular dependence especially for low energy photons. This study determines the correction factors to correct for these dependences of the MOSFET dosimeters for accurate measurement of radiation doses at organ locations in the phantom. For this, first, the dose correction factors of MOSFET dosimeters were determined for the energy spectrum in the steam generator channel of the Kori Nuclear Power Plant Unit #1 by Monte Carlo simulations. Then, the results were compared with the dose correction factors from 0.652 MeV and 1.25 MeV mono-energetic photons. The difference of the dose correction factors were found very negligible $(\leq1.5%)$, which in general shows that the dose corrections factors determined from 0.662 MeV and 1.25 MeV can be in a steam general channel head of a nuclear power plant. The measured effective dose was generally found to decrease bit $\sim7%$ when we apply the dose correction factors.

국내에서는 현재 물리적 인형 모의피폭체와 수십 개의 소형 MOSFET 선량계를 이용하여 유효선량(Effective Dose)을 실시간으로 정확하게 측정할 수 있는 시스템을 개발 중에 있다. 이때 사용되는 MOSFET 선량계는 그 크기가 매우 작으며, 상대적으로 높은 민감도를 가지고 선량을 실시간으로 측정할 수 있다는 장점이 있는 반면, 검출부위가 조직등가 물질이 아닌 실리콘으로 이루어져 있어 저에너지 광자에 대하여 적절한 보정이 필요하다. 본 연구에서는 몬테칼로 전산모사 방법을 사용하여 증기발생기 수실 내부의 에너지 스펙트럼에 대한 MOSFET 선량계의 선량보정인자 값들을 계산하였으며, 이렇게 계산된 보정인자 값들을 선행 연구에서 구한 값, 즉 0.662 MeV와 1.25 MeV의 광자만을 이용하여 구한 선량보정인자 값들과 비교하여 보았다. 비교 결과, 두 서로 다른 조건에서의 선량보정인자들은 큰 차이를 보이지 않았으며$(\leq1.5%)$, 따라서 선행 연구에서 구한 선량보정인자들을 원자력발전소의 증기발생기 수실에 그대로 적용하여도 큰 문제가 없음을 알 수 있었다. 또한, 증기발생기 수실에 대하여 결정된 선량보정인자들을 실측된 MOSFET 선량계의 선량값들에 적용하여 선량보정에 따라 유효선량이 어느 정도 변화하는 가를 확인한 결과, 유효선량은 선량보정인자를 적용할 경우가 적용하지 않을 경우에 비해 약 7% 정도 낮게 평가됨을 알 수 있었다.

Keywords

References

  1. ICRP ; Recommendations of the International Commission on Radiological Protection. Publication 60, Annals of the ICRP. 1991 April;2l(1-3):1-89 https://doi.org/10.1016/0146-6453(91)90065-O
  2. Hudsom CG. The need for dosimetry multibadging at nuclear power plants. Radiat. Protect. Mgt. 1984 Jan;43-49
  3. Nuclear Regulatory Commission. Code of Federal Regulations 10CFR20.1003 Definitions. U.S. Government Printing Office. 1992:362-367
  4. Ontario Power Generation. Ontario Hydro Radiation Protection Dosimetry Programme, IR-11 (Revision 2). 1992
  5. Michio Y, Seiichi M. On the Technical Guideline of Radiation Council to Assessment of External and Internal Exposure. 1999 Sep;34(3):319-322 https://doi.org/10.5453/jhps.34.319
  6. 김희근, 박규준. 원전 불균일 방사선장하에서 유효선량 평가를 위한 복수선량계 알고리즘 적용방안(Rev.2). 한국전력공사 전력연구원. 2005
  7. NCRP. Use of personal monitors to estimate effective dose equivalent and effective dose to workers for external exposure to low-let radiation. NCRP REPORT No. 122. 1995:7-16
  8. NRC. NRC regulatory issue summary 2004-01 method for estimating effective dose equivalent from external radiation sources using two dosimeters. U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation. 2004
  9. Lakshmanan AR, Kher RK, Supe SJ. Estimation of effective dose equivalent using individual dosimeters. Radiat. Port. Dosim. 1991;35(4) :247-252
  10. Xu X. The Assessment of effective dose equivalent using personnel dosimeters. Ph.D Dissertation, Texas A&M University. 1994
  11. Claycamp HG. Optimisation of monitor weighting factors for the estimation of effective dose equivalent from external photon exposures. Radiat. Prot. Dosim. 1999;81(2):105-111
  12. Kim CH, Reece WD, Poston JW. Development of a two-dosimeter alforithm for better estimation of effective dose equivalent and effective dose. Radiat. Prot. Dosim. 1999;81(2):101-112 https://doi.org/10.1093/oxfordjournals.rpd.a032573
  13. Kim CH, Reece WD. Overestimation of the two-dosimeter approach and movement of radiation workers during exposure. Rad. Prot. Mgt. 2000 Dec;17(6):17-25
  14. Kim CH, Reece WD. Effect of angular response properties of personal dosemeters on the estimation of effective dose using two dosemeters. Rad. Prot. Dos. 2001;93(3):215-221 https://doi.org/10.1093/oxfordjournals.rpd.a006432
  15. Kim CH, Reece WD. Monte Carlo simulation of single and two-dosimeter approaches in a steam generator channel head. Health Phys. 2002;83(2):243-254 https://doi.org/10.1097/00004032-200208000-00009
  16. Perisinakis K, Damilakis J, Anezinis P, Tzagaraki I, Varveris H, Cranidis A, Gourtsoyiannis N. Assessment of patient effective radiation dose and associated radiogenic risk from extracorporeal shock-wave lithotripsy. Health Phys. 2004 Dec;83(6):847-853
  17. Calzado A, Ruiz Sanz S, Melochor M, Vano E. A comparison of measured and calculated organ doses from CT examinations. Radiat. Prot. Dosim. 1995;57(1-4):381-385
  18. Wang B, Xu XG, Kim CH. Monte carlo study of MOSFET dosimeter characteristics: dose dependence on photon energy, direction and dosimeter composition. Rad. Prot. Dosi. 2005 May;113(1):40-46 https://doi.org/10.1093/rpd/nch426
  19. Cho S, Choi SH, Na SH, Kim CH. Determination of Dose Correction Factor for Energy and Directional Dependence of the MOSFET Dosimeter in an Anthropomorphic Phantom. J. Korean Asso. Radiat. Prot. 2006 Jun;31(2):97-104
  20. Vanbrabant R, Regge P. Characterization of the corrosion products in primary reactor water of PWR during normal operation and transient phases. Water Chemistry II. 1980;paper 41:279-284
  21. Polley MV, Garbett K, Pick ME. A Survey of the Effect of Primary Coolant pH on Westinghouse PWR Plant Radiation Fields. Electric Power Research Institute. 1994 Nov;TR-104180
  22. Lee CS, Lee JK. Characterization of Radiation Field in the Steam Generator Water Chambers and Effective Doses to the Workers. J. Korean Asso. Radiat. Prot. 1999 Dec;24(4):209-217
  23. Rogers B, Montoya P, Olguin B, Lopez A, Jarlow J. MCNPX user's manual, version 2.4.0. New Mexico; RSICC. 2002:99-100
  24. Cristy M, Eckerman KF. Specific absorbed fractions of energy at various ages from internal photon sources. TM-8381. Oak Ridge. Oak Ridge National Laboratory. 1987;1:77-102
  25. Rogers B, Montoya P, Olguin B, Lopez A, Jarlow J. MCNPX user's manual, version 2.4.0. New Mexico; RSICC. 2002:111-116