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dc.contributor.authorFISCHER Ulrichen_GB
dc.contributor.authorIIDA Hiromasaen_GB
dc.contributor.authorLI Yingen_GB
dc.contributor.authorLOUGHLIN Michaelen_GB
dc.contributor.authorSATO Satoshien_GB
dc.contributor.authorSERIKOV Arkadyen_GB
dc.contributor.authorTSIGE-TAMIRAT Haileyesusen_GB
dc.contributor.authorTAUTGES Timothy Jen_GB
dc.contributor.authorWILSON Paul P.en_GB
dc.contributor.authorWU Yicanen_GB
dc.identifier.citationFUSION SCIENCE AND TECHNOLOGY vol. 56 no. 2 p. 702-709en_GB
dc.description.abstractAn extensive benchmark exercise has been conducted on ITER with the objective to test and validate different approaches for the use of CAD generated geometry data for Monte Carlo transport calculations with the MCNP code. The exercise encompassed the generation of a dedicated neutronics CATIA model based on available engineering CAD design data, the conversion into MCNP geometry, the verification of the converted models, and a number of calculations to compare the different approaches with regard to the performance and the validity of the results obtained. The paper briefly reviews the different approaches and provides a detailed description of the ITER benchmark effort, its results and conclusions showing that the approaches have reached the maturity level to allow their application to real ITER design analyses. This is considered an essential step forward for neutronics analysis tools to satisfy ITER quality assurance rules.en_GB
dc.description.sponsorshipJRC.F.4-Safety of future nuclear reactorsen_GB
dc.publisherAMER NUCLEAR SOCen_GB
dc.titleUse of CAD Generated Geometry Data in MONTE CARLO Transport Calculations for ITERen_GB
dc.typeArticles in periodicals and booksen_GB
JRC Directorate:Energy, Transport and Climate

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