• Title/Summary/Keyword: expanded MDR

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The Criticality Analysis of Spent Fuel Pool with Consolidated Fuel in KNU 9 & 10 (조밀화 집합체로 중간저장하는 경우 원자력 발전소 9, 10호기의 사용 후 핵연료 저장조의 임계분석)

  • Jae, Moo-Sung;Park, Goon-Cherl;Chung, Chang-Hyun;Jang, Jong-Hwa
    • Nuclear Engineering and Technology
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    • v.20 no.1
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    • pp.27-34
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    • 1988
  • Since the lack of the spent fuel storage capcity has been expected for all Korean nuclear power plants in the mid-1990s, the maximum density rack (MDR) with consolidated fuels can be proposed to overcome the shortage of the storage capacity in KNU 9 & 10 which have most limited capacities. To ensure the safety when the alternatives are applied in the KNU 9 & 10, the multiplication factor are calculated with varying the rack pitch and the thickness of consolidated storage box by the AMPX-KENO IV codes. The computing system is verified by the benchmark calculation with criticality experiments for arrays of consolidated fuel modules, which was reported by B & W in 1981. Also an abnormal condition, i.e. malposition accident, is simulated. The results indicate that the KNU 9 & 10 storage pools with consolidated fuel are safe in the view of the criticality. Thus the storage capacity can be expanded from 9/3 cores into 27/3 cores even with considering equipments and cooling spaces.

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