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A STUDY FOR DOSE DISTRIBUTION IN SPENT FUEL STORAGE POOL INDUCED BY NEUTRON AND GAMMA-RAY EMITTED IN SPENT FUELS
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  • A STUDY FOR DOSE DISTRIBUTION IN SPENT FUEL STORAGE POOL INDUCED BY NEUTRON AND GAMMA-RAY EMITTED IN SPENT FUELS
  • A STUDY FOR DOSE DISTRIBUTION IN SPENT FUEL STORAGE POOL INDUCED BY NEUTRON AND GAMMA-RAY EMITTED IN SPENT FUELS
저자명
Sohn. Hee-Dong,Kim. Jong-Kyung
간행물명
방사선방어학회지
권/호정보
2011년|36권 4호|pp.174-182 (9 pages)
발행정보
대한방사선방어학회
파일정보
정기간행물|ENG|
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기타
이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
서지반출

기타언어초록

With the reactor operation conditions - 4.3 wt% $^{235}U$ initial enrichment, burn-up 55,000 MWd/MTU, average power 34 MW/MTU for three periods burned time for 539.2 days per period and cooling time for 100 hours after shut down, to set up the condition to determine the minimum height (depth) of spent fuel storage pool to shut off the radiation out of the spent fuel storage pool and to store spent fuels safely, the dose rate on the specific position directed to the surface of spent fuel storage pool induced by the neutron and gamma-ray from spent fuels are evaluated. The length of spent fuel is 381 cm, and as the result of evaluation on each position from the top of spent fuel to the surface of spent fuel storage pool, it is difficult for neutrons from spent fuels to pass through the water layer of maximum 219 cm (600 cm from the floor of spent fuel storage pool) and 419 cm (800 cm from the floor of spent fuel storage pool) for gamma-ray. Therefore, neutron and gamma-ray from spent fuels can pass through below 419 cm (800 cm from the floor) water layer directed to the surface of spent fuel storage pool.