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

Conference · Sun Apr 21 04:00:00 EDT 2024

OSTI ID:2439170

Weaver, Colin Andrew ^[1]; Rising, Michael Evan ^[1]; Kulesza, Joel A. ^[1]; Perfetti, Christopher Michael ^[1]; Vaquer, Pablo Andres ^[1]

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1. Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

This work presents a general set of equations that can be used to rapidly generate new benchmarks to verify nuclear data sensitivity calculations. 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 flux, and the sensitivity of k∞ to perturbations in the multigroup nuclear data of a single species, isotropic and elastic scattering, material. The multigroup nuclear data for U-235 and U-238 is presented along with their corresponding k-eigenvalues, forward flux, adjoint flux, 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-wise fission neutron production, and the unconstrained and constrained fission neutron energy distribution.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: 89233218CNA000001
• OSTI ID: 2439170
• Report Number(s): LA-UR--23-31844
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
Analytic
Infinite Medium
Mulitgroup
Nuclear Criticality Safety Program (NCSP)
Sensitivity Coefficient
k-eigenvalue