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Journal Articles

Rail deployment operation test for ITER blanket handling system with positioning misalignment

Takeda, Nobukazu; Aburadani, Atsushi; Tanigawa, Hisashi; Shigematsu, Soichiro; Kozaka, Hiroshi; Murakami, Shin; Kakudate, Satoshi; Nakahira, Masataka; Tesini, A.*

Fusion Engineering and Design, 88(9-10), p.2186 - 2189, 2013/10

 Times Cited Count:2 Percentile:20.35(Nuclear Science & Technology)

R&D for rail deployment equipment was performed for the ITER blanket remote handling system. The target torque for the automatic operation was investigated. The result shows that the 20% of the rated torque is adequate as the torque limitation for the automatic operation. A schedule for the procurement of the blanket remote handling system, which will be delivered to the ITER in 2020, was also shown.

Journal Articles

Irradiation test progress for the ITER maintenance robot

Noguchi, Yuto; Anzai, Katsunori; Kozaka, Hiroshi; Aburadani, Atsushi; Kazawa, Minoru; Takeda, Nobukazu; Kakudate, Satoshi

Dai-31-Kai Nihon Robotto Gakkai Gakujutsu Koenkai Yokoshu (DVD-ROM), 2 Pages, 2013/09

BB2013-1301.pdf:0.22MB

Journal Articles

R&D on major components of control system for ITER blanket maintenance equipment

Takeda, Nobukazu; Kakudate, Satoshi; Matsumoto, Yasuhiro; Kozaka, Hiroshi; Aburadani, Atsushi; Negishi, Yusuke; Nakahira, Masataka*; Tesini, A.*

Fusion Engineering and Design, 85(7-9), p.1190 - 1195, 2010/12

 Times Cited Count:1 Percentile:10.69(Nuclear Science & Technology)

Several R&Ds for the ITER blanket remote handling system had been performed from the Engineering Design Activity phase until now and only several technical issues regarding the control system remained such as noise caused by slip ring, control of cable handling system, signal transmission through very long cable and radiation-hard amplifier. This study concentrates on these issues. As a conclusion, major issues for the control system have been solved and the ITER blanket remote handling system becomes further feasible.

Journal Articles

Mock-up test on key components of ITER blanket remote handling system

Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka; Matsumoto, Yasuhiro; Taguchi, Ko; Kozaka, Hiroshi; Shibanuma, Kiyoshi; Tesini, A.*

Fusion Engineering and Design, 84(7-11), p.1813 - 1817, 2009/06

 Times Cited Count:11 Percentile:61.95(Nuclear Science & Technology)

The maintenance operation of the ITER in-vessel component, such as a blanket and divertor, must be executed by the remote equipment because of the high $$gamma$$-ray environment. During the Engineering Design Activity (EDA), the Japan Atomic Energy Agency had been fabricated the prototype of the vehicle manipulator system for the blanket remote handling and confirmed feasibility of this system including automatic positioning of the blanket and rail deployment procedure of the articulated rail. The JAEA is continuing several R&Ds so that the system can be procured smoothly to ITER. The residual key issues after the EDA are rail connection, cable handling and in-situ replacement of first wall. The last issue is newly raised and currently under the discussion. This presentation concentrates on the former two issues.

Oral presentation

Current status of research and development for ITER blanket remote maintenance system

Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka; Matsumoto, Yasuhiro; Taguchi, Ko; Kozaka, Hiroshi; Shibanuma, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Rail deploying equipment of ITER blanket remote handling system

Matsumoto, Yasuhiro; Kakudate, Satoshi; Takeda, Nobukazu; Taguchi, Ko; Kozaka, Hiroshi; Koizumi, Koichi; Shibanuma, Kiyoshi

no journal, , 

The ITER Blanket (BL) has to be maintained by remote handling means due to high radiation level in the VV after D-D operation. The ITER blanket system is maintained by a BL remote handling (RH) system consist of vehicles with manipulator traveled through an articulated rail deployed inside the VV. Towards the construction, the BL RH system design has been improved and developed in more detail. On the BL RH system, the articulated rail has to be assembled inside transfer casks to deploy the rail inside the VV. In particular, the technical issues of the rail connection in the cask are (1) tight tolerance of a pin at a hinge and (2) limited space for the rail connection inside a cask. To solve the issues, a rail connection mechanism which has compliance mechanisms and positioning mechanisms to realize the rail connection in good accuracy has been developed. This paper summarizes a result of the design work and status of R&D on the rail connection mechanism for the ITER BM RH system.

Oral presentation

Tribological proof test results of Diamond Like Carbon (DLC) film to lubricate the mechanical gear for ITER remote handling equipment under GPa level high contact stress

Kakudate, Satoshi; Takeda, Nobukazu; Nakahira, Masataka*; Aburadani, Atsushi; Matsumoto, Yasuhiro; Kozaka, Hiroshi; Negishi, Yusuke

no journal, , 

no abstracts in English

Oral presentation

Verification test of rail connection mechanism for ITER blanket remote handling system

Kozaka, Hiroshi; Takeda, Nobukazu; Aburadani, Atsushi; Matsumoto, Yasuhiro; Negishi, Yusuke; Kakudate, Satoshi

no journal, , 

no abstracts in English

Oral presentation

Installation and removal of ITER blanket module using torque limiting control

Aburadani, Atsushi; Takeda, Nobukazu; Matsumoto, Yasuhiro; Kozaka, Hiroshi; Negishi, Yusuke; Kakudate, Satoshi

no journal, , 

no abstracts in English

Oral presentation

Remote handling of large and heavy component for ITER maintenance

Shigematsu, Soichiro; Aburadani, Atsushi; Takeda, Nobukazu; Kozaka, Hiroshi; Negishi, Yusuke; Kakudate, Satoshi

no journal, , 

no abstracts in English

Oral presentation

The Performance test of ITER blanket replacement using torque control

Aburadani, Atsushi; Takeda, Nobukazu; Kozaka, Hiroshi; Negishi, Yusuke; Kakudate, Satoshi; Matsumoto, Yasuhiro*

no journal, , 

no abstracts in English

Oral presentation

R&D for major devices of ITER blanket remote handling system to finalize design for procurement

Aburadani, Atsushi; Kozaka, Hiroshi; Kakudate, Satoshi; Negishi, Yusuke; Matsumoto, Yasuhiro*; Nakahira, Masataka*; Tesini, A.*; Takeda, Nobukazu

no journal, , 

R&D for the major devices, rail deployment equipment and cable handling system, was performed for the ITER blanket remote handling system. Regarding the rail deployment, the relation between the Oldham's coupling used for the positioning arm and the positioning error at the end of rail was investigated. The result shows that the coupling allowing 4 mm displacement causes the positioning error of 19 mm. The possible countermeasures are suggested. Regarding the cable handling system, a possibility is shown to keep the cable tension at the adequate level by controlling the torque of the cable handling system. A schedule for the procurement of the blanket remote handling system, which will be delivered to the ITER in 2016, is also shown.

Oral presentation

Status and plan for procurement of ITER blanket remote handling system

Takeda, Nobukazu; Aburadani, Atsushi; Tanigawa, Hisashi; Kozaka, Hiroshi; Shigematsu, Soichiro; Murakami, Shin; Minakawa, Noboru; Kakudate, Satoshi

no journal, , 

In the ITER, all the in-vessel components are maintained by remote equipment because of the high $$gamma$$ ray circumstance. This report describes about status and schedule of the ITER blanket maintenance system which will be procured by the Japan Atomic Energy Agency.

Oral presentation

Development of the blanket remote handling system for ITER

Noguchi, Yuto; Maruyama, Takahito; Anzai, Katsunori; Kozaka, Hiroshi; Kazawa, Minoru; Takeda, Nobukazu; Kakudate, Satoshi

no journal, , 

no abstracts in English

Oral presentation

Technological development of maintenance robot for ITER

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 $$gamma$$-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.

15 (Records 1-15 displayed on this page)
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