Uncertainty analysis of Lead cross sections on reactor safety for ELECTRA

Author:

Alhassan Erwin,Sjöstrand Henrik,Duan Junfeng,Gustavsson Cecilia,Pomp Stephan,Österlund Michael,Rochman Dimitri,Koning Arjan J.

Abstract

The Total Monte Carlo (TMC) method was used in this study to assess the impact of Pb-206, 207 and 208 nuclear data uncertainties on keff , βeff, coolant temperature coefficient, the coolant void worth for the ELECTRA reactor. Relatively large uncertainties were observed in the keff and the coolant void worth for all the isotopes with significant contribution coming from Pb-208 nuclear data. The large Pb-208 nuclear data uncertainty observed was further investigated by studying the impact of partial channels on the keff and the βeff. Various sections of ENDF file: elastic scattering (n, el), inelastic scattering (n, inl), neutron capture (n, γ), (n, 2n), resonance parameters and the angular distribution were varied randomly and distributions in keff and the βeff obtained. The dominant contributions to the uncertainty in the keff from Pb-208 came from uncertainties in the resonance parameters; however, elastic scattering cross section and the angular distribution also had significant impact. The impact of nuclear data uncertainties on the βeff was observed to be small.

Publisher

EDP Sciences

Cited by 4 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors;Science and Technology of Nuclear Installations;2020-08-12

2. Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo;Annals of Nuclear Energy;2020-05

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4. The Serpent Monte Carlo Code: Status, Development and Applications in 2013;SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo;2014

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