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DOE OSTI · 2345707

Analytic Sensitivity Coefficients for General Multigroup Infinite Medium k-Eigenvalue Problems

Weaver, Colin A.·Rising, Michael E.·Kulesza, Joel A.·Perfetti, Christopher M.·Vaquer, Pablo A.
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Abstract

The general multigroup infinite medium k-eigenvalue neutron transport equation is used to derive analytic expressions for the infinite medium k-eigenvalue, the scalar neutron flux and adjoint, and the sensitivity of $k$ ∞ to perturbations in the multigroup nuclear data of a single species isotropic elastic scattering material. In the appendix, we present the multigroup nuclear data for U-235 and U-238 along with the corresponding k-eigenvalue, flux, adjoint, and sensitivity profiles, which include the sensitivity of $k$ ∞ to the total, fission, capture, and scattering macroscopic cross sections as well as to the group-to-group scattering cross section matrix, group neutron production, and the unconstrained and constrained fission neutron energy distribution.

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73 NUCLEAR PHYSICS AND RADIATION PHYSICSAnalytical MethodsCoefficientInfinite MediumK-EigenvalueMulitgroupNuclear Criticality Safety Program (NCSP)

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Weaver, Colin A., Rising, Michael E., Kulesza, Joel A., Perfetti, Christopher M., Vaquer, Pablo A.. 2024-04-24. Analytic Sensitivity Coefficients for General Multigroup Infinite Medium k-Eigenvalue Problems. https://www.osti.gov/biblio/2345707

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