Reactor Simulation for Antineutrino Experiments using DRAGON and MURE
  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. 
C. L. Jones, A. Bernstein, J. M. Conrad, Z. Djurcic, M. Fallot, L.   Giot, G. Keefer, A. Onillon, L. Winslow
nucl-ex hep-ex