Implementation of Uncertainty Propagation in TRITON/KENO

Authors

Charlotta Sanders, University of Nevada, Las VegasFollow
Denis Beller, University of Nevada, Las VegasFollow

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

pdf

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