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Recent progress in the fusion neutrons, 3; Nuclear analysis by automatic conversion of CAD data

Sato, Satoshi; Kondo, Keitaro

In the nuclear analysis of ITER, fusion DEMO reactor and IFMIF, etc., radiation transport calculations are conducted by using MCNP geometry data automatically created from 3-dimensional CAD data with CAD/MCNP conversion codes. In this review paper, we introduce the present status of the development on the CAD/MCNP conversion codes and examples of application. Also, we introduce how to visualize calculation results by MCNP.



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