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

Conference · Wed Apr 24 04:00:00 EDT 2024

OSTI ID:2345707

Weaver, Colin A. ^[1]; Rising, Michael E. ^[1]; Kulesza, Joel A. ^[1]; Perfetti, Christopher M. ^[2]; Vaquer, Pablo A. ^[1]

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1. Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
2. Univ. of New Mexico, Albuquerque, NM (United States)

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.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States); Univ. of New Mexico, Albuquerque, NM (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: 89233218CNA000001
• OSTI ID: 2345707
• Report Number(s): LA-UR--23-31844
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
Analytical Methods
Coefficient
Infinite Medium
K-Eigenvalue
Mulitgroup
Nuclear Criticality Safety Program (NCSP)