Interface-flux nodal transport method
Conference
·
OSTI ID:7247722
The development of the interface-flux nodal (IFN) method is presented to determine the flux distribution in reactor cells, cores and shielding. The method offers geometric flexibility, high order of spatial expansions of the node-interior sources and the node surface quantities. The surface-integral formulation is reduced to response-matrix-like global equations through coupling coefficients which are generalized expressions for escape and transmission probabilities. The spatial distribution of the neutron flux may be represented by high order polynomials using geometric basis functions determined by a least-square minimalization technique. The angular dependency of the outgoing/incoming surface flux components is treated using a general DP{sub n} expansion and the spatial variation is handled with a boundary element technique. The scattering iterations are eliminated by using an explicit expansion of the scalar fluxes. Based on the IFN method a computer code has been developed capable of calculating fixed-source and eigenvalue problems. Test problems for 1-D and 2-d X-Y and hexagonal geometries are presented including comparison with other techniques to demonstrate the validity and accuracy of the IFN method. 15 refs., 3 figs., 5 tabs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 7247722
- Report Number(s):
- BNL-43929; CONF-9004138--3; ON: DE90008515
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
656003 -- Condensed Matter Physics-- Interactions between Beams & Condensed Matter-- (1987-)
75 CONDENSED MATTER PHYSICS
SUPERCONDUCTIVITY AND SUPERFLUIDITY
ACCURACY
BOUNDARY CONDITIONS
EIGENFUNCTIONS
FLEXIBILITY
FLUX DENSITY
FUNCTIONS
GAUSS FUNCTION
HOMOGENEOUS PLASMA
MATHEMATICAL MODELS
MATRICES
MEASURING METHODS
MECHANICAL PROPERTIES
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
ONE-DIMENSIONAL CALCULATIONS
PLASMA
PROBABILITY
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
SAFETY
STABILITY
SURFACE PROPERTIES
TENSILE PROPERTIES
TESTING
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS
VALIDATION
VARIATIONS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
656003 -- Condensed Matter Physics-- Interactions between Beams & Condensed Matter-- (1987-)
75 CONDENSED MATTER PHYSICS
SUPERCONDUCTIVITY AND SUPERFLUIDITY
ACCURACY
BOUNDARY CONDITIONS
EIGENFUNCTIONS
FLEXIBILITY
FLUX DENSITY
FUNCTIONS
GAUSS FUNCTION
HOMOGENEOUS PLASMA
MATHEMATICAL MODELS
MATRICES
MEASURING METHODS
MECHANICAL PROPERTIES
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
ONE-DIMENSIONAL CALCULATIONS
PLASMA
PROBABILITY
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
SAFETY
STABILITY
SURFACE PROPERTIES
TENSILE PROPERTIES
TESTING
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS
VALIDATION
VARIATIONS