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Matsuo, Tatsuhito; Takeda, Soichi*; Oda, Toshiro*; Fujiwara, Satoru
Biophysics and Physicobiology (Internet), 12, p.145 - 158, 2015/12
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：18.63(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.
Aburadani, Atsushi; Takeda, Nobukazu; Shigematsu, Soichiro; Murakami, Shin; Tanigawa, Hisashi; Kakudate, Satoshi; Nakahira, Masataka*; Hamilton, D.*; Tesini, A.*
Fusion Engineering and Design, 88(9-10), p.1978 - 1981, 2013/10
Times Cited Count：2 Percentile：18.63(Nuclear Science & Technology)no abstracts in English
Tanigawa, Hisashi; Aburadani, Atsushi; Shigematsu, Soichiro; Takeda, Nobukazu; Kakudate, Satoshi; Mori, Seiji*; Jokinen, T.*; Merola, M.*
Fusion Engineering and Design, 87(7-8), p.999 - 1003, 2012/08
Times Cited Count：13 Percentile：69.01(Nuclear Science & Technology)This paper presents results of R&D activities where the laser and TIG welding tools were developed to apply the blanket hydraulic connection. The target pipe is 48.26 mm in outer diameter and 2.77 mm-thick. A single path welding without filler materials is required to reduce the weld heat input related to re-weldability. For the laser welding, the focal spot diameter was expanded to increase allowable misalignment. The TIG welding tool was equipped with AVC (Arc Voltage Control) to avoid a torch sticking and to enlarge allowable misalignment. For each tool, the welding conditions were optimized for all position welding to horizontally located pipes. Obtained parameters such as the weld heat input, allowable misalignment, lifetime of the tools and amount of sputter and fume, were comparatively assessed.
Shigematsu, Soichiro; Tanigawa, Hisashi; Aburadani, Atsushi; Takeda, Nobukazu; Kakudate, Satoshi; Mori, Seiji*; Nakahira, Masataka*; Raffray, R.*; Merola, M.*
Fusion Engineering and Design, 87(7-8), p.1218 - 1223, 2012/08
Times Cited Count：6 Percentile：38.04(Nuclear Science & Technology)The current design of the ITER blanket system is a modular configuration and a total of 440 blanket modules are to be installed in the ITER vacuum vessel. Each blanket module consists of the first wall (FW) and the shield block (SB). The FW receives a high heat load from the plasma. The SB shields components from the neutrons generated by the nuclear fusion reaction. The FW will be damaged by the heat load and neutrons, so it requires scheduled replacement. For the FW replacement, cutting/welding tools for the cooling pipes must be able to conduct the following operations: access and cut/weld the pipe from the inside of the cooling pipe. The cutting tool for the pipe end is required to cut flat plate circularly from the surface side of the FW. This paper describes the current status of R&D of the cutting tools for maintenance of the cooling pipe of the FW.
Shigematsu, Soichiro; Aburadani, Atsushi; Takeda, Nobukazu; Kozaka, Hiroshi; Negishi, Yusuke; Kakudate, Satoshi
no journal, ,
no abstracts in English
Fujiwara, Satoru; Yonezawa, Yasushige*; Matsumoto, Fumiko; Oda, Toshiro*; Takeda, Soichi*
no journal, ,
no abstracts in English
Kakudate, Satoshi; Takeda, Nobukazu; Aburadani, Atsushi; Shigematsu, Soichiro; Matsumoto, Yasuhiro*; Tsuji, Koichi*
no journal, ,
Maintenance of the ITER blanket will be carried out in the vacuum vessel (VV) using remote handling equipment, including the in-vessel transporter (IVT) with vehicle type manipulators. An estimated 440 blanket modules, each with a maximum weight of 44.kN, will be installed in the VV. The 
ray dose rate is expected to be approximately 500 Gy/h during the periods of blanket maintenance. This paper describes the system integration of maintenance robot for ITER (International thermonuclear experimental reactor). This design items include design requirements, in-vessel transporter (maintenance robot) mechanism, installation mechanism and the rescue concept in case of failure mode.
Fujiwara, Satoru; Matsuo, Tatsuhito; Matsumoto, Fumiko; Oda, Toshiro*; Takeda, Soichi*
no journal, ,
Aburadani, Atsushi; Shigematsu, Soichiro; Tanigawa, Hisashi; Takeda, Nobukazu; Kakudate, Satoshi
no journal, ,
no abstracts in English
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 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.
Katagiri, Hideaki*; Sato, Wataru*; Enomoto, Ryoji*; Wakamotsu, Ryo*; Tanaka, Soichi*; Kagaya, Mika*; Takeda, Toru*; Muraishi, Hiroshi*; Yoshida, Tatsuo*; Watanabe, Takara*; et al.
no journal, ,
We developed All-Sky Gamma-Ray Compton Camera based on Scintillators. We measured the residual dose rate in F1 by using this detector. Additionally, we measured the residual dose rate at beam line in J-PARC 3 GeV RCS, where has a high dose-rate from 0.01 to 1 mSv/h caused by beam loss during beam operation. We performed the experiment that we can use the detector in the RCS. As the result, we evaluated to obtain -ray imaging of dose rate, which is consistency the measured one by using other detectors. In our presentation, we will report these results.
