Shielding analysis of ITER/TBM

Sato, Satoshi; Iida, Hiromasa*; Tanigawa, Hisashi; Hirose, Takanori; Ochiai, Kentaro; Konno, Chikara ; Enoeda, Mikio

Shielding analyses have been performed on the ITER/TBM and its port by using Monte Carlo radiation transport calculation code MCNP and activation calculation code ACT-4. CAD data were automatically converted to MCNP data on the TBM, shield, pipes and bio-shield by the CAD/MCNP conversion code, and their MCNP data have been inserted to the ITER 40 degree model. We evaluated the effective dose rate in operation, nuclear heating, tritium production rate, effective dose rate after shutdown and induced activity.

Language	:	Japanese
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Meeting title	:	Plasma Conference 2014 (PLASMA 2014)
Held date	:	2014/11
Location (city)	:	Niigata
Location (country)	:	Japan
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Keywords	:	no keyword
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Registration No. : BB20141257
JAEA Abstracts No. :
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