Propagation of nuclear data uncertainties for ELECTRA burn-up calculations
H. Sj\"ostrand, E. Alhassan, J. Duan, C. Gustavsson, A. Koning, S., Pomp, D. Rochman, M. \"Osterlund

TL;DR
This study propagates nuclear data uncertainties for the ELECTRA reactor's fuel inventory during burn-up using the Total Monte Carlo method, highlighting the impact of data uncertainties on reactor parameters and the potential for benchmark data to reduce these uncertainties.
Contribution
It introduces a fast TMC methodology for efficient uncertainty propagation in nuclear reactor burn-up calculations, focusing on the ELECTRA reactor and Pu-239 data.
Findings
Uncertainty in long-term radiotoxicity and decay heat is insignificant.
Uncertainty in minor actinides can be large, affecting recycling.
Criticality benchmarks can reduce inventory uncertainties.
Abstract
The European Lead-Cooled Training Reactor (ELECTRA) has been proposed as a training reactor for fast systems within the Swedish nuclear program. It is a low-power fast reactor cooled by pure liquid lead. In this work, we propagate the uncertainties in Pu-239 transport data to uncertainties in the fuel inventory of ELECTRA during the reactor life using the Total Monte Carlo approach (TMC). Within the TENDL project the nuclear models input parameters were randomized within their uncertainties and 740 Pu-239 nuclear data libraries were generated. These libraries are used as inputs to reactor codes, in our case SERPENT, to perform uncertainty analysis of nuclear reactor inventory during burn-up. The uncertainty in the inventory determines uncertainties in: the long-term radio-toxicity, the decay heat, the evolution of reactivity parameters, gas pressure and volatile fission product content.…
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Taxonomy
TopicsNuclear reactor physics and engineering · Nuclear Materials and Properties · Nuclear and radioactivity studies
