Computational efficiency of numerical methods for the multigroup, discrete-ordinates neutron transport equations: the slab geometry case

Journal Article · Wed Aug 01 04:00:00 EDT 1979 · Nucl. Sci. Eng.; (United States)

OSTI ID:5784235

Alcouffe, R E; Larsen, E W; Miller, Jr, W F; Wienke, B R

A study of spatial discretization schemes for the multigroup discrete-ordinates transport equations in slab geometry is described. The purpose of the study is to determine the most computationally efficient method, defined as the one that produces the minimum error for a given cost. Cost is defined as the total amount of computer time required to complete one inner iteration, given a limit on storage, and three error norms are used to measure the accuracies of edge fluxes, cell average fluxes, and integral parameters. Three test problems are studied: the first is a model one-group problem examined in detail, while the second and third are more realistic multigroup problems. One conclusion is that a new method, labeled linear characteristic, significantly outperforms all other methods that have been implemented up to the present time. 15 references.

• Research Organization: Los Alamos Scientific Lab., NM
• OSTI ID: 5784235
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 71:2; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
654002 -- Radiation & Shielding Physics-- Shielding Calculations & Experiments-- (-1987)
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CDC COMPUTERS
COMPUTER CODES
COMPUTERS
COORDINATES
CROSS SECTIONS
DATA
DATA FORMS
DISCRETE ORDINATE METHOD
DISTRIBUTION
EFFICIENCY
EIGENVALUES
ERRORS
GEOMETRY
GRAPHS
INFORMATION
ISOLATED VALUES
ITERATIVE METHODS
MATHEMATICS
MULTIGROUP THEORY
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
NUMERICAL DATA
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
SHIELDING
SLABS
SPATIAL DISTRIBUTION
THEORETICAL DATA
TRANSPORT THEORY