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Maruyama, Takahito; Noguchi, Yuto; Komai, Masafumi; Takeda, Nobukazu; Kakudate, Satoshi
no journal, ,
no abstracts in English
Inoue, Ryuichi; Noguchi, Yuto; Maruyama, Takahito; Tanigawa, Hisashi; Takeda, Nobukazu; Kakudate, Satoshi
no journal, ,
no abstracts in English
Komai, Masafumi; Anzai, Katsunori; Noguchi, Yuto; Saito, Makiko; Maruyama, Takahito; Takeda, Nobukazu; Kakudate, Satoshi
no journal, ,
-ray Environment of ~250 Gy/hr in International Thermonuclear Experimental Reactor (ITER) requires a full remote maintenance of in-vessel components such as blanket modules. JAEA is carrying out development of radiation hard components for the ITER blanket remote handling system. The current status of the radiation hardness component development is presented.
Takeda, Nobukazu; Noguchi, Yuto; Maruyama, Takahito; Inoue, Ryuichi; Komai, Masafumi; Kozaka, Hiroshi; Tanigawa, Hisashi; Kakudate, Satoshi
no journal, ,
In general, nuclear fusion device requires remote maintenance system to avoid human access because of -ray emitted from structural material, which is activated by neutron of fusion reaction. The remote maintenance system was first introduced in the Joint European Torus (JET) which was constructed in UK based on international cooperation in Europe. The JET used so-called "Boom type" remote handling system which introduces articulated arm from a port. The arm is supported from the port with canti-levered and therefore the capacity is relatively low: 300 kg in JET. On the contrary, the ITER uses different type of remote handling system. The JT-60SA, which is under construction in Japan, also considers remote maintenance. This paper describes outline of remote maintenance systems for the international fusion experimental reactor, ITER.
Kakudate, Satoshi; Takeda, Nobukazu; Matsuhira, Nabuto*; Senda, Ikuo*
no journal, ,
no abstracts in English