A massively parallel discrete ordinates response matrix method for neutron transport
Journal Article
·
· Nuclear Science and Engineering; (United States)
OSTI ID:5165399
- Northwestern Univ., Dept. of Mechanical Engineering, Evanston, IL (US)
In this paper a discrete ordinates response matrix method is formulated with anisotropic scattering for the solution of neutron transport problems on massively parallel computers. The response matrix formulation eliminates iteration on the scattering source. The nodal matrices that result from the diamond-differenced equations are utilized in a factored form that minimizes memory requirements and significantly reduces the number of arithmetic operations required per node. The red-black solution algorithm utilizes massive parallelism by assigning each spatial node to one or more processors. The algorithm is accelerated by a synthetic method in which the low-order diffusion equations are also solved by massively parallel red-black iterations. The method is implemented on a 16K Connection Machine-2, and S{sub 8} and S{sub 16} solutions are obtained for fixed-source benchmark problems in x-y geometry.
- OSTI ID:
- 5165399
- 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
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Related Subjects
663610* -- Neutron Physics-- (1992-)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ALGORITHMS
ANISOTROPY
BENCHMARKS
COMPUTERS
DIFFERENTIAL EQUATIONS
EQUATIONS
MATHEMATICAL LOGIC
NEUTRAL-PARTICLE TRANSPORT
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT
NODAL EXPANSION METHOD
PARALLEL PROCESSING
PROGRAMMING
RADIATION TRANSPORT
REACTOR KINETICS EQUATIONS
RESPONSE MATRIX METHOD
SCATTERING
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ALGORITHMS
ANISOTROPY
BENCHMARKS
COMPUTERS
DIFFERENTIAL EQUATIONS
EQUATIONS
MATHEMATICAL LOGIC
NEUTRAL-PARTICLE TRANSPORT
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT
NODAL EXPANSION METHOD
PARALLEL PROCESSING
PROGRAMMING
RADIATION TRANSPORT
REACTOR KINETICS EQUATIONS
RESPONSE MATRIX METHOD
SCATTERING