Analysis of NEA C5MOX benchmark with computer code “cohint” based on interface current approach |
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Authors: | P. Mohanakrishnan |
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Affiliation: | Reactor Physics Division, IGCAR, Kalpakkam, TN, 603102, INDIA |
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Abstract: | Interface current approach to solution of neutron transport equation has been earlier used for LWR lattice problems. The analysis of the C5MOX benchmark is a opportunity to test its applicability to heterogeneous reactor problem. Computer code COHINT, which incorporates a routine for solution of neutron transport equation in X-Y geometry by interface current approach was used for this analysis by representing the fuel rod as a square one. Region interface angular fluxes are represented by a four-term expansion. It is found that the average pin power error is about 2.28 % (peak pin error 4.1 %) relative to reference calculations. Further improvement is possible by introduction of the capability to represent circular rods with in a square cell in COHINT. |
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Keywords: | Interface current approach PN half space expansion, C5MOXbenchmark, Computer code COHINT, Square fuel rod |
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