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Development of Bounding Burnup Axial Profiles for WWER-440 Spent Fuel Pool Burnup Credit Analysis

S. Bznuni, N. Baghdasaryan, A. Amirjanyan, G. Nazaryan, P. Kohut, J. Ramsey

Nuclear Science and Engineering / Volume 186 / Number 1 / April 2017 / Pages 98-102

Technical Paper /

First Online Publication:April 21, 2017

Bounding axial profiles for WWER-440 spent fuel pool burnup credit analysis were developed. A database of axial burnup profiles of WWER-440 type fuel assemblies and fuel followers was developed and studied to determine the burnup axial profile that results in the maximal neutron multiplication factor. Bounding axial profiles were determined based on the statistical analysis of keff of the analyzed profiles from the statistical outliers of the axial profile database. The influence of the identified bounding profiles on keff is quantified for the WWER-440 spent fuel pool. Criticality calculations using the database axial profiles were conducted by the MCNP6.1 program. The isotopic compositions of the spent WWER-440 fuels were quantified by the ORIGEN program of the SCALE 6.1 package.

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