  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.
