Published 2008 | Version v1
Book

Validation study of depletion calculations performed with a Monte-Carlo code

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