Source Intensity Analysis of DUPIC Fuel

DUPIC 핵연료의 조사선량률 분석

  • Kim, Yun-Goo (Department of Nuclear Engineering, Kyunghee University) ;
  • Lim, Jae-Yong (Department of Nuclear Engineering, Kyunghee University) ;
  • Park, Bhum-Lak (Department of Nuclear Engineering, Kyunghee University) ;
  • Park, Kwang-Heon (Department of Nuclear Engineering, Kyunghee University) ;
  • Whang, Ju-Ho (Department of Nuclear Engineering, Kyunghee University)
  • 김윤구 (경희대학교 원자력공학과) ;
  • 임재용 (경희대학교 원자력공학과) ;
  • 박범락 (경희대학교 원자력공학과) ;
  • 박광헌 (경희대학교 원자력공학과) ;
  • 황주호 (경희대학교 원자력공학과)
  • Published : 1996.06.30

Abstract

Source intensities in terms of the exposure rates at 1m from the fresh and spent DUPIC fuels, made from standard and extended turnup PWR fuels, were analyzed. Two cases were studied based on the degree of elimination of removable elements. Homogeneous mixture model was applied to get the exposure rate. The exposure rate turned out to be very high and sensitive to Cs elimination during the dry process. About 90% of exposure can be reduced in the case of fresh DUPIC fuel made from 10-year cooled spent PWR fuels if Cs is fully removed during the dry process. The main radiation source in spent fuels is Cs-137. The dry storage of spent DUPIC fuel may need a longer wet storage period and require a further review.