Geometry-independent approach to coarse-mesh neutron diffusion calculations
Conference
·
OSTI ID:5986798
Powerful coarse-mesh and nodal methods have been recently developed to calculate accurate node-average fluxes and eigenvalues. The nodal methods solve for the node-average flux by reducing the multidimensional diffusion problem to a coupled system of 1-D equations. These schemes are mainly limited to rectangular (xyz) nodes and cannot easily be extended to other geometries. The polynomial-based coarse-mesh methods have been applied to thetaRZ and HEXZ geometries. This summary describes the development of a boundary coarse-mesh nodal method applicable to arbitrary geometries using the boundary integral technique coupled with nodal source expansion.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5986798
- Report Number(s):
- BNL-NUREG-37002; CONF-851115-19; ON: TI86000028
- Country of Publication:
- United States
- Language:
- English
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210300* -- Power Reactors
Nonbreeding
Graphite Moderated
210500 -- Power Reactors
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BARYONS
DESIGN
DIFFERENTIAL EQUATIONS
EIGENVALUES
ELEMENTARY PARTICLES
EPITHERMAL REACTORS
EQUATIONS
FAST REACTORS
FERMIONS
GAS COOLED REACTORS
GEOMETRY
HADRONS
MATHEMATICAL MODELS
MATHEMATICS
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRONS
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