Development of CAD-MCNP Interface Program GEOMIT and Its Applicability for ITER Neutronics Design Calculations

Hesham R. NasifMHI Nuclear Engineering Company, 3-1 Minatomirai, 3-Chome, Nishi-Ku Yokohama, Kanagawa 220-8401, Japan

Fukuzo MasudaMHI Nuclear Engineering Company, 3-1 Minatomirai, 3-Chome, Nishi-Ku Yokohama, Kanagawa 220-8401, Japan

Hidetsugu MorotaMHI Nuclear Engineering Company, 3-1 Minatomirai, 3-Chome, Nishi-Ku Yokohama, Kanagawa 220-8401, Japan

Hitomasa IidaJapan Atomic Energy Agency, Fusion Research and Development Directorate 2-4 Shirakatashirane, Tokai-mura, Naka-guu, Ibaraki-ken 319-1195, Japan

Satoshi SatoJapan Atomic Energy Agency, Fusion Research and Development Directorate 2-4 Shirakatashirane, Tokai-mura, Naka-guu, Ibaraki-ken 319-1195, Japan

Chikara KonnoJapan Atomic Energy Agency, Fusion Research and Development Directorate 2-4 Shirakatashirane, Tokai-mura, Naka-guu, Ibaraki-ken 319-1195, Japan

References

“MCNP—A General Monte Carlo Particle Transport Code,” BRIESMEISTER J. F., Ed., Version 4C, LA-13709-M (2000).
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SHAABAN N. et al., “A New Developed Interface for CAD0 MCNP Data Conversion,” Proc. 14th Int. Conf. Nuclear Engineering (ICONE-14), Miami, Florida, July 17–20, 2006.
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NASIF H. et al., “GEOMIT,” presented at Progress Review Mtg. Neutronics Analyses for ITER, Cadarache, France, March 26–27, 2007.
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IIDA H. and NASIF H., “Calculation Results for ITER Benchmark Problem Using Input Data Converted with the GEOMIT Code,” presented at Progress Review Mtg. Neutronics Analyses for ITER, Cadarache, France, March 26–27, 2007.
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Development of CAD-MCNP Interface Program GEOMIT and Its Applicability for ITER Neutronics Design Calculations

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