Title :
FREYA—A New Monte Carlo Code for Improved Modeling of Fission Chains
Author :
Hagmann, C. ; Randrup, J. ; Vogt, Ryszard
Author_Institution :
Lawrence Livermore Nat. Lab., Livermore, CA, USA
Abstract :
A new simulation capability for modeling individual fission events and chains and the transport of fission products in materials is presented. The fission yield event yield algorithm (FREYA) is a Monte Carlo code for generating fission events providing correlated kinematic information for prompt neutrons, gammas, and fragments. For each fission event, FREYA generates multiplicity, energy, and the direction of neutrons and gammas while conserving energy and momentum at each step. To study materials with multiplication, shielding effects, and detectors, we have integrated FREYA into the general-purpose Monte Carlo code MCNP. This new tool will allow more accurate modeling of detector responses including correlations and the development of SNM detectors with increased sensitivity.
Keywords :
Monte Carlo methods; fission products; neutron transport theory; nuclear engineering computing; nuclear materials transportation; shielding; FREYA; MCNP general-purpose Monte Carlo code; Monte Carlo code; SNM detectors; fission chains; fission product transport; fission yield event yield algorithm; individual fission events; shielding effect; Correlation; Detectors; Iron; Laboratories; Materials; Monte Carlo methods; Neutrons; Fission; Monte Carlo; neutrons; nuclear physics;
Journal_Title :
Nuclear Science, IEEE Transactions on
DOI :
10.1109/TNS.2013.2251425