Nuclear Technology / Volume 168 / Number 3 / December 2009 / Pages 843-847
MC Calculations / Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Miscellaneous
We developed a conversion system from three-dimensional computer-aided design (CAD) drawing data to MCNP geometry input data. This system consists of programs of "void creation" and "conversion into MCNP input data." By using this system, it is possible to convert large and complicated CAD drawing data such as a fusion reactor into MCNP geometry input data. We applied this system to ITER CAD drawing data and created MCNP input data for ITER nuclear analysis. We calculated the neutron flux and nuclear heating using this input data. The calculation results agreed well with those by the other parties participating in this ITER research and development.