Linear discontinuous finite difference formulation for synthetic coarse-mesh few-group diffusion calculations
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:6744647
A linear discontinuous finite difference formulation to solve the diffusion equations in coarse mesh and few groups is developed. The correction factors for heterogeneities, coarse mesh, and spectral effects are general interface flux discontinuity factors that can be explicitly calculated (synthetized) from detailed diffusion or transport solutions in fine mesh (heterogeneous) and multigroups, preserving the integrated fluxes and interface net currents. The stability is explicitly established for general synthetizations and for specific fine to coarse mesh and group reductions. Computing methods have been implemented for one-group (grey) synthetic diffusion acceleration, two-dimensional nodal/local solutions, and three-dimensional nodal simulation of pressurized water reactor cores. Results demonstrate the simplicity and stability of the formulation, a regular behaviour of the correction factors, an outstanding acceleration performance, and high potential for parallel and vector computing.
- Research Organization:
- Instituto de Fusion Nuclear (DENIM), Universidad Politecnica de Madrid, Po. Castellana, 80; 28046 Madrid
- OSTI ID:
- 6744647
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 94:4; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCELERATION
COMPUTERIZED SIMULATION
CORRECTIONS
DIFFERENTIAL EQUATIONS
EQUATIONS
FINITE DIFFERENCE METHOD
HETEROGENEOUS EFFECTS
ITERATIVE METHODS
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
PARALLEL PROCESSING
PERFORMANCE
PROGRAMMING
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
SIMULATION
STABILITY
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS
VECTOR PROCESSING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCELERATION
COMPUTERIZED SIMULATION
CORRECTIONS
DIFFERENTIAL EQUATIONS
EQUATIONS
FINITE DIFFERENCE METHOD
HETEROGENEOUS EFFECTS
ITERATIVE METHODS
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
PARALLEL PROCESSING
PERFORMANCE
PROGRAMMING
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
SIMULATION
STABILITY
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS
VECTOR PROCESSING
WATER COOLED REACTORS
WATER MODERATED REACTORS