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A Heat Transfer Approach to the Calculation of Residual Power of Used Nuclear Fuel

Peter Schreiber, Pavol Tanuska, Robert Vrabel, and Pavel Vazan

Nuclear Technology / Volume 185 / Number 2 / February 2014 / Pages 208-215

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-138

In this paper, we develop a new method for determining the residual power of used nuclear fuel (UNF). The method is based on the heat transfer analysis of UNF in a C-30 transport container with a KZ-48 compact storage cask. We compare the results achieved by the currently used SCALE 6 software packages based on nuclear physics calculations and the results from our method.

 
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