Multigroup neutron diffusion in two-dimensional multiregion domains with interior corners

Journal Article · Tue Dec 31 04:00:00 EST 1996 · Transactions of the American Nuclear Society

OSTI ID:436891

Cacuci, D G ^[1]

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1. Univ. of Karlsruhe (Germany)

Considerable attention has been devoted in the last two decades to the behavior of the solution of simple linear elliptic equations on piecewise homogeneous domains separated by interfaces with corners. The equations typically studied were the Poisson, Laplace, and Helmholtz equations, while the domains typically consisted of two-region squares, rectangles, or L shapes involving adjacent materials with distinct properties. These works have shown that the respective solutions are not everywhere regular but take on special, singular forms at corners. Consequently, the customary (e.g., finite difference, finite element) numerical methods break down if used naively at or in the immediate neighborhood of such singular corners. The goal of this work is to present the exact analytical solution of the multigroup diffusion equation (MGDE) at corners formed by piecewise homogeneous domains that stem from the spatially homogenized subassemblies customarily used for modeling the reactor core in two-dimensional neutronics calculations.

• OSTI ID: 436891
• Report Number(s): CONF-9606116--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 74; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
66 PHYSICS
EIGENVALUES
MATHEMATICAL MODELS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
REACTOR CORES