Development of the CAD/MCNP automatic conversion code: GEOMIT, 3; Analysis of ITER CAD/MCNP benchmark problem with GEOMIT

Iida, Hiromasa; Sato, Satoshi; Konno, Chikara ; Nishitani, Takeo; Nasif, H.*; Masuda, Fukuzo*; Yamada, Masao*; Morota, Hidetsugu*

The ITER benchmark problem has been analysed with a CAD/MCNP automatic conversion cord "GEOMIT" which is beeing developed by JAEA-FNS in cooperation with CSD. The analysis includes (1) First wall neutron load, (2) Neutron fluxes in divertor cassette (3) Inboard TF coil nuclear heat and (4) Neutron flux distribution behind the port plug rear in a equitorial port. Generally very similar results have been obtained by GEOMIT with those of other ITER participating parties, suggesting that development of GEOMIT is progressing smoothly.

Language	:	Japanese
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Meeting title	:	日本原子力学会2007年秋の大会
Held date	:	2007/09
Location (city)	:	北九州
Location (country)	:	日本
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Registration No. : BB20071320
JAEA Abstracts No. :
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