Computational efficiency of numerical methods for the multigroup, discrete-ordinates neutron transport equations: the slab geometry case
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), Vol. 71:2
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
NEUTRON TRANSPORT THEORY
COMPUTER CODES
DISCRETE ORDINATE METHOD
MULTIGROUP THEORY
SPATIAL DISTRIBUTION
REACTOR CORES
SHIELDING
CDC COMPUTERS
COORDINATES
CROSS SECTIONS
EFFICIENCY
EIGENVALUES
ERRORS
GEOMETRY
GRAPHS
ISOLATED VALUES
ITERATIVE METHODS
NEUTRON FLUX
SLABS
THEORETICAL DATA
COMPUTERS
DATA
DATA FORMS
DISTRIBUTION
INFORMATION
MATHEMATICS
NUMERICAL DATA
RADIATION FLUX
REACTOR COMPONENTS
TRANSPORT THEORY
654003* - Radiation & Shielding Physics- Neutron Interactions with Matter
654002 - Radiation & Shielding Physics- Shielding Calculations & Experiments- (-1987)
220100 - Nuclear Reactor Technology- Theory & Calculation