Validation study of depletion calculations performed with a Monte-Carlo code
Creators
- 1. IRSN, Fontenay-aux-Roses (France)
Description
Burnup Credit implementation requires a precise fuel characterization. The increase of computer calculation power makes it nowadays possible to perform Monte-Carlo burnup calculations which are of major interest for spent fuel characterization, but also for burnup calculations in geometrical configurations other than standard ones. The studies presented in this paper investigate the validation of two of these Monte-Carlo burnup codes (MONTEBURNS and VESTA) and explore different conceivable ways to optimize the calculations, which consists in decreasing the calculation time while conserving the calculation precision. Aside from these validation and optimization studies, attempts are also made to establish a radial burnup map for a UOX assembly and a calculated axial profile of burnup for a UOX fuel rod. (authors)
Additional details
Publishing Information
- Publisher
- Paul Scherrer Institut - PSI
- Imprint Place
- Villigen PSI (Switzerland)
- ISBN
- 978-3-9521409-5-6
- Imprint Pagination
- 8 p.
Conference
- Title
- International Conference on the Physics of Reactors 'Nuclear Power: A Sustainable Resource'
- Acronym
- PHYSOR'08
- Dates
- 14-19 Sep 2008
- Place
- Interlaken (Switzerland)
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- France
- INIS RN
- 41119121
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; BURNUP; COMPUTER CALCULATIONS; CONFIGURATION; FUEL RODS; IMPLEMENTATION; MONTE CARLO METHOD; OPTIMIZATION; SPENT FUELS; VALIDATION
- Descriptors DEC
- CALCULATION METHODS; ENERGY SOURCES; FUEL ELEMENTS; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; TESTING
Optional Information
- Notes
- 11 refs.; proceedings are available as a CD-ROM on request to info'at'physor08.ch