Journal of Radiation Protection and Research
- Volume 4 Issue 1
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- Pages.1-4
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- 1979
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- 2508-1888(pISSN)
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- 2466-2461(eISSN)
Criticality Safety Determination of Spent Fuel Storage Vault
기사용(旣使用) 핵연료저장시(核燃料貯藏時) 핵임계(核臨界) 안전성(安全性) 결정(決定)
- Yook, Chong-Chul (Dept. of Nuclear Engineering, Hanyang University)
- 육종철 (한양대학교 공과대학 원자력공학과)
- Published : 1979.07.30
Abstract
Effective multiplication factor has been calculated for one PWR fresh fuel assembly immersed in a spent fuel storage vault on the basis of the neutron transport theory. A numerical calculation has been carried out by means of Sn approximation. The method employed in this study is that the energy domain is broken into 16 groups, the angular variable is divided into four discrete direction, i.e.,
중성자(中性子) 수송이론(輸送理論)을 써서 기사용(旣使用) 핵연료(核燃料) 저장조(貯藏槽)에 있는 한 개(個)의 PWR용(用) 핵연료집합체(核燃料集合體)에 대(對)한 유효증배계수(有效增倍係數)(
Keywords