1109.5379 (C. L. Jones et al.)

Reactor Simulation for Antineutrino Experiments using DRAGON and MURE    [PDF]

C. L. Jones, A. Bernstein, J. M. Conrad, Z. Djurcic, M. Fallot, L. Giot, G. Keefer, A. Onillon, L. Winslow

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.

View original: http://arxiv.org/abs/1109.5379