Published 1987 | Version v1
Book

The explicitly-interfaced method and the response matrix method: two methods for the solution of the transport equation

  • 1. Westhinghouse Electric Corp., Pittsburgh, PA (USA)
  • 2. Sandia National Lab., Alburquerque, NM (USA)
  • 3. Michigan Univ., Ann Arbor, MI (USA). Dept. of Nuclear Engineering

Description

Two alternative implementations of the phase space finite element method for the solution of the transport equation are presented. Both rely on dividing the spatial domain into smaller regions to increase computational efficiency. The explicitly-interfaced method results in a series of matrix equations that are solved iteratively to find a flux distribution over the entire spatial domain. The response matrix method results in the familiar response matrix equations through direct inversion of each region's finite element matrix. The global flux distribution is again found iteratively. Both methods are applied to one- and two-dimensional test problems. For most one-dimensional applications the new methods are no more efficient than the conventional procedure. In two dimensions, however, the new methods are significantly more efficient

Part of:
Advances in Reactor Physics, Mathematics and Computation. Volume 2

Additional details

Publishing Information

Publisher
Societe Francaise d'Energie Nucleaire.
Imprint Place
Paris (France)
Imprint Title
Advances in Reactor Physics, Mathematics and Computation. Volume 2
Imprint Pagination
597 p.
Journal Page Range
p. 1021-1032.

Conference

Title
International Topical Meeting on Advances in Reactor Physics, Mathematics and Computation.
Dates
27-30 Apr 1987.
Place
Paris (France).

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
22060552
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPARATIVE EVALUATIONS; COST; F CODES; FINITE ELEMENT METHOD; NEUTRON TRANSPORT; RESPONSE MATRIX METHOD
Descriptors DEC
COMPUTER CODES; EQUATIONS; EVALUATION; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL SOLUTION; RADIATION TRANSPORT; REACTOR KINETICS EQUATIONS

Optional Information