Surface harmonics method for burnup calculations of VVER-1000 fuel assemblies with uranium and MOX fuel
- Russian Research Center Kurchatov Inst., Nuclear Reactor Inst., 123182, Moscow (Russian Federation)
Development of the SUHAM-U code for burnup calculations of VVER-1000 fuel assemblies with uranium and MOX fuel is described. Developed SUHAM-U code has capacity to calculate burnup in each fuel or poison zone of each cell of VVER-1000 fuel assembly. In so doing Surface Harmonics Method is used for calculation of the detail neutron spectra in fuel assembly at separated burnup values. Verification of SUHAM-U code by burnup calculations of VVER-1000 fuel assemblies with uranium and MOX fuel has been carried out. Comparisons were carried out with calculations by UNK and RECOL codes. UNK code uses the first collisions probabilities method for solution of the neutron transport equation and RECOL code uses Monte-Carlo method with point-wise continues energy presentation of cross-sections. The main conclusion of all comparisons is the SUHAM-U code calculates the fuel burnup of VVER-1000 fuel assemblies with uranium and MOX fuel with enough high accuracy. Time expenditures are adduced. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 22039471
- Resource Relation:
- Conference: PHYSOR-2006: American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, Vancouver, BC (Canada), 10-14 Sep 2006; Other Information: Country of input: France; 9 refs.
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
97 MATHEMATICAL METHODS AND COMPUTING
ACCURACY
BURNUP
COLLISION PROBABILITY METHOD
COMPARATIVE EVALUATIONS
CROSS SECTIONS
FUEL ASSEMBLIES
MIXED OXIDE FUELS
MONTE CARLO METHOD
NEUTRON SPECTRA
NEUTRON TRANSPORT THEORY
S CODES
U CODES
URANIUM
VERIFICATION
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