A New Method for the Solution of Group Diffusion Equations

Journal Article · Fri May 12 00:00:00 EDT 2017 · Nuclear Science and Engineering

DOI:https://doi.org/10.13182/nse8-1-44· OSTI ID:4180785

Foderaro, A. ^[1]; Garabedian, H. L. ^[1]

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1. General Motors LLC, Detroit, MI (United States)

Here, the diffusion equations associated with the multigroup, multiregion problem are solved by expansions in eigenfunctions which are solutions of the Helmholtz equation. A determinantal criticality equation is exhibited in which the order of the determinant is independent of the number of groups and which can be solved without recourse to complicated computational procedures. Moreover, the need to fulfill explicitly the requirements that the flux and current associated with each neutron group be continuous across interfaces is eliminated.

• Research Organization: General Motors LLC, Detroit, MI (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: NONE
• NSA Number: NSA-14-019735
• OSTI ID: 4180785
• Journal Information: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 1 Vol. 8; ISSN 0029-5639
• Publisher: Taylor & Francis
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
DIFFERENTIAL EQUATIONS
DIFFUSION
EQUATIONS
GROUP THEORY
HELMHOLTZ EQUATION
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)