Monte Carlo methods are beginning to be used for three dimensional fuel depletion analyses to compute various quantities of interest, including isotopic compositions of used nuclear fuel. The TRITON control module, available in the SCALE 5.1 code system, can perform three-dimensional (3-D) depletion calculations using either the KENO V.a or KENO-VI Monte Carlo transport codes, as well as the two-dimensional (2-D) NEWT discrete ordinates code. To overcome problems such as spatially nonuniform neutron flux and non-uniform statistical uncertainties in computed reaction rates and to improve the fidelity of calculations using Monte Carlo methods, uncertainty propagation is needed for depletion calculations.
Nuclear reactors; Monte Carlo method; Spent reactor fuels; Stochastic processes
Nuclear | Nuclear Engineering | Oil, Gas, and Energy | Statistical Methodology | Statistical Models
Implementation of Uncertainty Propagation in TRITON/KENO.
Available at: https://digitalscholarship.unlv.edu/hrc_trp_reactor/23