Reconstruction of pin burnup characteristics from nodal calculations in hexagonal geometry
Conference
·
OSTI ID:6913506
A reconstruction method has been developed for recovering pin burnup characteristics from fuel cycle calculations performed in hexagonal-z geometry using the nodal diffusion option of the DIF3D/REBUS-3 code system. Intra-modal distributions of group fluxes, nuclide densities, power density, burnup, and fluence are efficiently computed using polynomial shapes constrained to satisfy nodal information. The accuracy of the method has been tested by performing several numerical benchmark calculations and by comparing predicted local burnups to values measured for experimental assemblies in EBR-11. The results indicate that the reconstruction methods are quite accurate, yielding maximum errors in power and nuclide densities that are less than 2% for driver assemblies and typically less than 5% for blanket assemblies. 14 refs., 2 figs., 5 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6913506
- Report Number(s):
- CONF-900418-11; ON: DE90010547
- Country of Publication:
- United States
- Language:
- English
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BREEDER REACTORS
BURNUP
CARTESIAN COORDINATES
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COORDINATES
D CODES
DIMENSIONS
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUX DENSITY
FUEL ASSEMBLIES
FUEL CYCLE
FUEL ELEMENTS
GAS COOLED REACTORS
GEOMETRY
LIQUID METAL COOLED REACTORS
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MATHEMATICS
NEUTRON FLUENCE
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