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A simplified perturbation model for calculation of few-group cross sections and reaction rates

Journal Article · · Nucl. Sci. Eng.; (United States)
OSTI ID:6280303
A fast efficient perturbation model is developed for generating four-group cross sections and flux spectrum and performing fuel depletion in a light water reactor unit cell configuration. In the thermal energy region, an approximate solution of the neutron spectrum is determined based on the Wigner-Wilkins free-gas hydrogen scattering model. In the fast energy region, a combination of analytical and empirical techniques is used to determine resonance cross sections. These models are combined in a perturbation scheme and incorporated as the SIFAS code. Reaction rates of important nuclides in reactor cores can be estimated by the code to within 0.5% for fuel depletion studies with fuel burnup of up to 30,000 MWd/tonne.
Research Organization:
The University of Michigan, Department of Nuclear Engineering Ann Arbor, Michigan
OSTI ID:
6280303
Journal Information:
Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 85:2; ISSN NSENA
Country of Publication:
United States
Language:
English