Title: Use of McCad for the Conversion of ITER CAD Data to MCNP Geometry
Authors: TSIGE-TAMIRAT HaileyesusFISCHER UlrichSERIKOV ArkadySTICKEL Stephanie
Citation: FUSION ENGINEERING AND DESIGN vol. 83 no. 10-12 p. 1771-1773
Publisher: ELSEVIER SCIENCE SA
Publication Year: 2008
JRC N°: JRC52292
ISSN: 0920-3796
URI: http://www.elsevier.com/locate/fusengdes
http://publications.jrc.ec.europa.eu/repository/handle/JRC52292
DOI: 10.1016/j.fusengdes.2008.07.040
Type: Contributions to Conferences
Abstract: The program McCad provides a CAD interface for the Monte Carlo transport code MCNP. It is able to convert CAD data into MCNP input geometry description and provides GUI components for modeling, visualization, and data exchange. It performs sequences of tests on CAD data to check its validity and neutronics appropriateness including completion of the final MCNP model by void geometries. McCad has been used to convert a 40° ITER torus sector CAD model to a suitable MCNP geometry model. Results of MCNP calculations performed to validate the converted geometry are presented.
JRC Institute:Institute for Energy and Transport

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