XIAOPING LIU, LILI TONG, YUETONG LUO, YU YANG, XIAOYI WENG, QUNYING HUANG AND YICAN WU
Institute of Plasma Physics, Chinese Academy of Sciences, 230031, Hefei, China CAD&CG Division, Computer college.Hefei University of Technology, 230009, Hefei, China
E-mail: lxp@mail.ipp.ac.cn

MCNP is a transport simulation system program using Monte Carlo technology for the conceptual design results of new nuclear fusion reactor. To achieve accurate calculations, the preparation of detailed and fully described geometrical models is required, which is usually very time-consuming and error incidental by hand. MCAM2.0 is a system tool using visual method to aid conceptual design of fusion reactor, which is based on program of version 1.0. The paper studies modeling mechanism of MCNP based on the developing design system for nuclear fusion reactor, presents one novel design method for automatic transformation between CAD and MCNP system, and introduces new version of MCNP auto-modeling tool-MACM2.0 which is under kernel code of ACIS7.0 supported by Spatial Co. MCAM2.0 can be used as a visual modeling tool for characteristics of fusion reactor and outputs geometry card as input-file of MCNP automatically. It makes the design and simulation satisfactory. As examples, the geometry input files for MCNP calculations have been prepared for the 3D models of the superconducting Tokamak HT-7U, designed by ASIPP.