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)

  • 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., $S_4$, and the spatial variable which is divided into fine meshes at the interface between different materials is discretized into 27 mesh points. The calculated $K_{eff}$ value of 0.6145 seems to be far small in comparison with the value obtained by other author for an infinite array of fuel assemblies.

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