Year: 2017
Type: preprint
Abstract: This work investigates a method for generating medium fidelity reactor model cross sections. The methodology used here couples a neutron transport code with a depletion calculator. Together the two can be used to generate time dependent group cross sections for medium fidelity reactor models in fuel cycle simulation. This work analyzes XSgen, a software that performs the functions mentioned above. Addtionally, it is shown that XSgen is capable of creating datasets for a medium fidelity reactor model known as Bright-lite. The results of this work show that XSgen produces datasets that match NEA benchmarks for both uranium based LWR, and MOX reactors.
Source: arXiv (Cornell University)
Authors: Flanagan, Robert, Scopatz, Anthony
Language: English
Subfield: Aerospace Engineering
Field: Engineering
Domain: Physical Sciences
Open Access status: green
OpenAlex ID: W2772236240