Sensitivity Coefficients for Fast Reactor Core Analysis

TL;DRAbstract

Sensitivity coefficients of nuclear reactors with respect to cross section changes are very useful for the evaluation of neutronic characteristics with respect to nuclear data change, cross section adjustment, and uncertainty analysis. In the analysis of fast reactors, cell calculations are usually carried out using fine energy groups to accurately take into account the cross section behaviour in the fast and resonance energy ranges. Sensitivity coefficients should thus be calculated using fine groups, although in practice core calculations are done with broad energy groups. Also, in fast reactors the transport effect is large because of the long neutron mean free path and because leakage is larger than in thermal reactors. However, sensitivity coefficients are usually calculated based on diffusion theory. This paper present two topics. The first is a “sensitivity reconstruction”, an attempt to estimate fine group sensitivities from broad group calculations. A “flux reconstruction” met

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