A Consideration on the use of shear waves to improve the sensitivity of an optical ultrasonic sensor for under-sodium viewers

Saruta, Koichi; Shirahama, Takuma*; Yamaguchi, Toshihiko; Ueda, Masashi

E-Journal of Advanced Maintenance (Internet), 10(2), p.1 - 8, 2018/08

http://www.jsm.or.jp/ejam/Vol.10No.2/AA/AA148/AA148.html

Japan - IAEA Joint Nuclear Energy Management School 2016

Yamaguchi, Mika; Hidaka, Akihide; Ikuta, Yuko; Murakami, Kenta*; Tomita, Akira*; Hirose, Hiroya*; Watanebe, Masanori*; Ueda, Kinichi*; Namaizawa, Ken*; Onose, Takatoshi*; et al.

JAEA-Review 2017-002, 60 Pages, 2017/03

JAEA-Review-2017-002.pdf:9.41MB

Since 2010, IAEA has held the NEM School to develop future leaders who plan and manage nuclear energy utilization in their county. Since 2012, JAEA together with Japan Nuclear HRD Network, University of Tokyo, Japan Atomic Industrial Forum and JAIF International Cooperation Center have cohosted the school in Japan in cooperation with IAEA. Since then, the school has been held in Japan every year. In 2006, Japanese nuclear technology and experience, such as lessons learned from the Fukushima Daiichi Nuclear Power Plant accident, were provided to offer a unique opportunity for the participants to learn about particular cases in Japan. Through the school, we contributed to the internationalization of Japanese young nuclear professionals, development of nuclear human resource of other countries including nuclear newcomers, and enhanced cooperative relationship with IAEA. Additionally, collaborative relationship within the network was strengthened by organizing the school in Japan.

Effects of metallic diaphragms on sensitivity characteristics of an optical ultrasonic sensor and reduction of interrogation time based on wavelength division multiplexing for under-sodium visual inspection

Saruta, Koichi; Yamaguchi, Toshihiko; Ueda, Masashi

E-Journal of Advanced Maintenance (Internet), 7(4), p.NT75_1 - NT75_8, 2016/02

http://www.jsm.or.jp/ejam/Vol.7No.4/NT/NT75/75.html

Progress in physics and technology developments for the modification of JT-60

Tamai, Hiroshi; Matsukawa, Makoto; Kurita, Genichi; Hayashi, Nobuhiko; Urata, Kazuhiro*; Miura, Yushi; Kizu, Kaname; Tsuchiya, Katsuhiko; Morioka, Atsuhiko; Kudo, Yusuke; et al.

Plasma Science and Technology, 6(1), p.2141 - 2150, 2004/02

https://doi.org/10.1088/1009-0630/6/1/006

The dominant issue for the the modification program of JT-60 (JT-60SC) is to demonstrate the steady state reactor relevant plasma operation. Physics design on plasma parameters, operation scenarios, and the plasma control method are investigated for the achievement of high-. Engineering design and the R&D on the superconducting magnet coils, radiation shield, and vacuum vessel are performed. Recent progress in such physics and technology developments is presented.

Objectives and design of the JT-60 superconducting tokamak

Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Cho, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.

Nuclear Fusion, 43(7), p.606 - 613, 2003/07

https://doi.org/10.1088/0029-5515/43/7/314

no abstracts in English

None

Ikeda, Norio*; Sasaki, Nobuyuki*; Oshima, Kazuo*; Yamaguchi, Kohei*; Saito, Shigeyuki*; Abe, Yoriyuki*; Katano, Takashi*; Ueda, Akira*

JNC TJ7440 2005-071, 122 Pages, 1998/03

JNC-TJ7440-2005-071.PDF:5.9MB

no abstracts in English

High temperature continuous observation of the thermal decomposition process of (Ba, Sr) CO by the electron microscope

; *

Denshi Kenbikyo, 7(2-3), P. 89, 1959/00

no abstracts in English

Sensitivity characteristics of optical ultrasonic sensors using a metallic membrane for under-sodium inspection

Saruta, Koichi; Yamaguchi, Toshihiko; Ueda, Masashi

no journal, , 

no abstracts in English

Status of physics and engineering conceptual design of the divertor for 1.5 GW-level fusion power Demo reactor

Asakura, Nobuyuki; Hoshino, Kazuo; Uto, Hiroyasu; Someya, Yoji; Tokunaga, Shinsuke; Shimizu, Katsuhiro; Suzuki, Satoshi; Tobita, Kenji; Ono, Noriyasu*; Ueda, Yoshio*; et al.

no journal, , 

Radiative cooling scenario by impurity seeding has been developed and the divertor geometry, and the plasma operation have been investigated for Demo with the fusion power of 1.5 GW, using SONIC simulation. Results showed the total peak heat load is reduced to less than 10 MWm for the total radiation power fraction of 0.7-0.8. The heat load can be handled by the water-cooling and tungsten (W) monoblock target design, provided that Cu-alloy cooling pipe is applied. The design is applied only in the divertor target. F82H cooling pipe design will be applied for the divertor baffle and dome under higher neutron flux and lower heat load condition. Heat transport analysis of the target design and cooling-water pipes showed that the divertor design can handle the heat load distribution. The conceptual design study of the Demo divertor and power exhaust is presented. Development issues of physics, engineering and plasma material interaction from ITER technology will be also discussed.

Local structural analysis on half metallic ferromagnet CrO

Kodama, Katsuaki; Ikeda, Kazutaka*; Takeda, Hikaru*; Isobe, Masahiko*; Ito, Masayuki*; Ueda, Yutaka*; Shamoto, Shinichi; Otomo, Toshiya*

no journal, , 

no abstracts in English