A spectral nodal method for one-group X,Y-geometry discrete ordinates problems

Journal Article · Fri May 01 04:00:00 EDT 1992 · Nuclear Science and Engineering; (United States)

OSTI ID:7047795

De Barros, R C; Larsen, E W ^[1]

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1. Univ. of Michigan, Dept. of Nuclear Engineering, Ann Arbor, MI (US)

This paper reports on a nodal method that is developed for the solution of one-group discrete ordinates (S{sub N}) problems with linearly anisotropic scattering in x, y-geometry. In this method, the spectral Green's function (SGF) scheme, originally developed for solving S{sub N} problems in slab geometry with no spatial truncation error, is generalized to solve the one-dimensional transverse-integrated S{sub N} nodal equations with the constant approximation for the transverse leakage terms. The resulting SGF-constant nodal (SGF-CN) method is more accurate than conventional coarse-mesh methods for deep penetration problems because it treats the scattering source terms implicitly and exactly; the only approximation involves the transverse leakage terms. In conventional S{sub N} nodal methods, the transverse leakage terms and scattering source are both approximated. The authors solve the SGF-CN equations using the one-node block inversion iterative scheme, which uses the best available estimates for the node-entering fluxes to evaluate the node-exiting fluxes in the directions that constitute the incoming fluxes for the adjacent nodes as the equations are swept across the system. Finally, the authors give numerical results that illustrate the accuracy of the SGF-CN method for coarse-mesh calculations.

• OSTI ID: 7047795
• Journal Information: Nuclear Science and Engineering; (United States), Journal Name: Nuclear Science and Engineering; (United States) Vol. 111:1; ISSN 0029-5639; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
663610* -- Neutron Physics-- (1992-)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ANISOTROPY
CALCULATION METHODS
DATA
FUNCTIONS
GEOMETRY
GREEN FUNCTION
INFORMATION
ITERATIVE METHODS
MATHEMATICS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NODAL EXPANSION METHOD
NUMERICAL DATA
RADIATION TRANSPORT
SCATTERING