Reactor simulation for antineutrino experiments using DRAGON and MURE
Name
Conrad_Reactor simulation.pdf
Size
361.18 KB
Format
Adobe PDF
Checksum (MD5)
ca25e1081f9ec636cc4ee0847fd1512f
Author(s)
Jones, Christopher LaDon
Bernstein, Aron M.
Conrad, Janet
Djurcic, Z.
Fallot, M.
Giot, L.
Keefer, G.
Onillon, A.
Winslow, Lindley
Date Issued
July 2012
Journal
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
Abstract
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.
MIT Department
Massachusetts Institute of Technology. Department of Physics
Terms of Use
Article is made available in accordance with the publisher's policy and may be subject to US copyright law. Please refer to the publisher's site for terms of use.
Persistent DSpace Link
DOI of Published Version
https://doi.org/10.1103/PhysRevD.86.012001
