In a complex and huge system as in ITER fusion reactor, the creation of the geometrical input data of Monte Carlo (MC) codes such as MCNP is a highly exhausting task. Accordingly, it is a general approach to shift the geometric modeling into a computer aided design (CAD) system and to use an interface, which performs the exchange of CAD data into a representation appropriate for MC code. We have developed efficient algorithms and computer code, which are used to convert Parasolid format CAD files including solid and void data into MCNP input data. The CAD-MCNP conversion processes include creating surface equations; determining surface senses; constructing cell geometry and creating MCNP input file. This paper describes the basic algorithms used for the CAD/MCNP interface along with some applications for different geometries.
- Nuclear Engineering Division
A New Developed Interface for CAD/MCNP Data Conversion
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Shaaban, N, Masuda, F, Nasif, H, Yamada, M, Sawamura, H, Morota, H, Sato, S, Iida, H, & Nishitani, T. "A New Developed Interface for CAD/MCNP Data Conversion." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy. Miami, Florida, USA. July 17–20, 2006. pp. 467-473. ASME. https://doi.org/10.1115/ICONE14-89742
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