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|Title:||Current Status of the CAD Interface Program McCad for MC Particle Transport Calculations|
|Authors:||GROSSE Dennis; TSIGE-TAMIRAT Haileyesus|
|Citation:||Proceedings of the 2009 International Conference on Mathematics Computational Methods and Reactor Physics|
|Publisher:||American Nuclear Society|
|Type:||Articles in periodicals and books|
|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 visualization, data exchange and modeling. It performs sequences of tests on CAD data to check its suitability for neutronics analysises. McCad has been validated in several applications including the generation of a 40º torus sector of ITER. It is coded for Linux platforms in the programming language C++. The implemented conversion algorithm uses the Open CASCADE CAD kernel for its geometric computations and the GUI is based on the Qt4 libraries. The paper provides an insight in the current status of McCad and its functionality. The implemented algorithms for conversion and void completion are described in detail.|
|JRC Institute:||Institute for Energy and Transport|
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