Analysis of NEA C5MOX benchmark with computer code “cohint” based on interface current approach
✍ Scribed by P. Mohanakrishnan
- Publisher
- Elsevier Science
- Year
- 2004
- Tongue
- English
- Weight
- 331 KB
- Volume
- 45
- Category
- Article
- ISSN
- 0149-1970
No coin nor oath required. For personal study only.
✦ Synopsis
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.