Design standard issues for ITER in-vessel components
نویسندگان
چکیده
منابع مشابه
Neutron Transport Analysis for In-vessel Diagnostics in ITER
Nuclear transport analysis using the MCNP code and heat analysis using a general purpose Finite Element Method code ANSYS 11, respectively, have been carried out for in-vessel components of the microfission chamber (MFC) and the poloidal polarimeter. The nuclear heating rates of the MI cable and the exhaust pipe of the MFC are highest in the gap between two adjacent blanket modules and decrease...
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ژورنال
عنوان ژورنال: Fusion Engineering and Design
سال: 1995
ISSN: 0920-3796
DOI: 10.1016/0920-3796(95)80017-r