THE EFFECTS OF STORAGE PATTERNS ON THE NEUTRON MULTIPLICATION FACTOR OF SPENT NUCLEAR FUEL CASKS

Mosebetsi Johannes Leotlela

Abstract


The type of an array selected for the storage of fissile material such as fuel assemblies or spent fuel casks has a profound effect on the neutron multiplication factor (keff) of the system. Given a particular initial enrichment, the neutron multiplication factor of the system can either increase or decrease depending on either the type of the array used (which may either be an n x n, or n x m where n m ), the distance among various fissile units or the total number of units. This paper will present the effects of changes in distances between spent fuel casks in various storage arrays using fresh fuel assumptions.


Keywords


burnup credit, actinides, effect of separation gap between cask in criticality, spent fuel casks, neutron importance.

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