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arXiv · 1712.02241

XSgen: A Cross Section Generation Methodology for Fuel Cycle Simulation

Robert Flanagan·Anthony Scopatz
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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.

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Robert Flanagan, Anthony Scopatz. 2017-12-05. XSgen: A Cross Section Generation Methodology for Fuel Cycle Simulation. https://arxiv.org/abs/1712.02241

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