SCALE6 VALIDATION AGAINST VVER-440 EXPERIMENTAL DATA

Nikolay Mihaylov, Maria Manolova, INRNE-BAS, Sofia, Bulgaria

22nd Symposium of AER on VVER Reactor Physics and Reactor Safety (2012, Průhonice, Czech Republic)
CRITICALITY SAFETY

Abstract

The validation of depletion codes is an important task in spent fuel management,
especially for burnup credit application in criticality safety analysis of spent fuel facilities.
The calculations are performed for twelve samples with maximal, average and minimal
burnup from VVER-440 spent fuel assembly, based on #3958 ISTC PIE project. The fuel
assembly has initial enrichment 4.4% of

Presentation / full paper