Nuclear Engineering and Technology
- 제14권2호
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- Pages.86-91
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- 1982
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- 1738-5733(pISSN)
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- 2234-358X(eISSN)
핵연료 저장시설의 임계 안전성 분석
Criticality Safety Analysis of Spent Fuel Storage Facility for Bo-Ri Unit 1
- Dong Ha Kim (Seoul National University) ;
- Un Chul Lee (Seoul National University)
- 발행 : 1982.06.01
초록
1977년 집합체 cell 중심간의 간격을 53.34cm(162 연료 집합체 저장)에서 36cm(562 연료 집합체저장)로 줄임으로 고리 1호기 부속 기사용 연료 저장 용량을 화장하였다. 확장된 저장 시설에 대하여 Monte Carlo방법을 이용한 KENO-IV코드로 Core Performance Branch에서 제시한 비정상적인 냉각수 밀도 조건에 따라 유효증배계수를 구하였다. KENO-IV결과 밀도 0.1143g/cm에서 최대유효 증배계수 0.9958
In 1977, spent fuel storage capacity of Ko-Ri Unit 1 was raised to contain 4-2/3 core, by reducing the center-to-center spacing between fuel assemblies from 53.34cm to 36cm. In this paper the adequacy is discussed in detail by examining the previous design analysis report. According to the analytic method presented by Core Performance Branch, study on credible abnormal moderator density condition is performed by using KENO-IV for the redesigned spent fuel storage facility. Result shows that 36cm for the center-to-center spacing between fuel assemblies is not enough to keep the storage safe at water density of 0.1143g/㎤, which gives the maximum
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