Document Type
Annual Report
Publication Date
2008
First page number:
86
Last page number:
86
Abstract
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.
Keywords
Nuclear reactors; Monte Carlo method; Spent reactor fuels; Stochastic processes
Controlled Subject
Monte Carlo method; Nuclear reactors; Spent reactor fuels; Stochastic processes
Disciplines
Nuclear | Nuclear Engineering | Oil, Gas, and Energy | Statistical Methodology | Statistical Models
File Format
File Size
119 KB
Language
English
Repository Citation
Sanders, C.,
Beller, D.
(2008).
Implementation of Uncertainty Propagation in TRITON/KENO.
86-86.
Available at:
https://digitalscholarship.unlv.edu/hrc_trp_reactor/23
Included in
Nuclear Commons, Nuclear Engineering Commons, Oil, Gas, and Energy Commons, Statistical Methodology Commons, Statistical Models Commons