Reactor simulation for antineutrino experiments using DRAGON and MURE
Author(s)
Jones, Christopher LaDon; Bernstein, Aron M.; Conrad, Janet; Djurcic, Z.; Fallot, M.; Giot, L.; Keefer, G.; Onillon, A.; Winslow, Lindley; ... Show more Show less
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Rising interest in nuclear reactors as a source of antineutrinos for experiments motivates validated, fast, and accessible simulations to predict reactor fission rates. Here we present results from the DRAGON and MURE simulation codes and compare them to other industry standards for reactor core modeling. We use published data from the Takahama-3 reactor to evaluate the quality of these simulations against the independently measured fuel isotopic composition. The propagation of the uncertainty in the reactor operating parameters to the resulting antineutrino flux predictions is also discussed.
Date issued
2012-07Department
Massachusetts Institute of Technology. Department of PhysicsJournal
Physical Review D
Publisher
American Physical Society
Citation
Jones, C. et al. “Reactor simulation for antineutrino experiments using DRAGON and MURE.” Physical Review D 86.1 (2012). © 2012 American Physical Society
Version: Final published version
ISSN
1550-7998
1089-4918