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Journal Articles

Investigation of strengthening mechanism in Ni-38Cr-3.8Al alloy with fine lamellar structure by in situ neutron diffraction analysis

Koyanagi, Yoshihiko*; Ueta, Shigeki*; Kawasaki, Takuro; Harjo, S.; Cho, K.*; Yasuda, Hiroyuki*

Materials Science & Engineering A, 773, p.138822_1 - 138822_11, 2020/01

 Times Cited Count:1 Percentile:19.72(Nanoscience & Nanotechnology)

Journal Articles

Fuels and materials irradiation test plan at JMTR

Ise, Hideo; Ogiyanagi, Jin; Nakamura, Jinichi; Sasajima, Hideo; Takasa, Akira; Hanawa, Satoshi; Kawaguchi, Yoshihiko; Chimi, Yasuhiro; Nishiyama, Yutaka; Nakamura, Takehiko

FAPIG, (180), p.22 - 25, 2010/02

Refurbishment of Japan Materials Testing Reactor (JMTR) is conducted in Japan Atomic Energy Agency (JAEA) in order to solve irradiation related issues for safe long-term operation of current light water reactors (LWRs) and development of advanced LWRs. JMTR will restart its operation in FY 2011. Manufacturing and installation of the irradiation test facilities on safety research of fuels and materials are also in progress. The outline of the fuels and materials irradiation test plan is described in this report.

Journal Articles

Critical current measurement of prototype NbTi cable-in-conduit conductor for JT-60SA

Kizu, Kaname; Tsuchiya, Katsuhiko; Obana, Tetsuhiro*; Takahata, Kazuya*; Hoshi, Ryo; Hamaguchi, Shinji*; Nunoya, Yoshihiko; Yoshida, Kiyoshi; Matsukawa, Makoto; Yanagi, Nagato*; et al.

Fusion Engineering and Design, 84(2-6), p.1058 - 1062, 2009/06

 Times Cited Count:12 Percentile:62.42(Nuclear Science & Technology)

The maximum magnetic field and maximum current of EF coils for JT-60SA is 6.2T, 20 kA, respectively. The EF coil conductors are NbTi cable-in-conduit (CIC) conductor with SS316L conduit. In order to confirm the performance of current sharing temperature ($$T$$$$_{rm cs}$$) tests under coil operational condition was performed. As a results, the degradation of $$T$$$$_{rm cs}$$ was 0.01-0.08 K indicating that the conductor design and its fabrication method is appropriate. Experimental results were compared with the $$I$$ and $$T$$ by standard plasma operation scenario. It was confirmed that the conductor has $$T$$$$_{rm cs}$$ margin of $$>$$ 1K.

JAEA Reports

Thermal cycle test of elemental mockups of ITER breeding blanket

Yanagi, Yoshihiko*; Kosaku, Yasuo; Hatano, Toshihisa; Kuroda, Toshimasa*; Enoeda, Mikio; Akiba, Masato

JAERI-Tech 2002-046, 45 Pages, 2002/05

JAERI-Tech-2002-046.pdf:2.61MB

no abstracts in English

Journal Articles

Evaluation of tritium permeation in solid breeder blanket cooled by supercritical water

Kosaku, Yasuo; Yanagi, Yoshihiko*; Enoeda, Mikio; Akiba, Masato

Fusion Science and Technology, 41(3), p.958 - 961, 2002/05

As a candidate DEMO blanket, the design of solid breeder blanket cooled by supercritical water has been performed. The candidate structural material is F82H. The coolant is supercritical water (pressure; 25 MPa, temperature; 550-780K) to achieve high generation efficiency. The temperature of cooling tubes in tritium breeder zone has been evaluated at 650-800K. In this temperature range, tritium permeation must be investigated from the view point of safety management, because high temperature coolant is directly supplied to the power generation system. In the present work, the tritium permeation into the first wall cooling water by the implantation and that through cooling tubes in tritium breeder zone have been evaluated. Assuming tritium injection energy and flux are same as SSTR, the calculated value of the tritium permeation rate into the first wall cooling water is 68.3 g/day. On the other hand, that of the permeation rate through cooling tubes is 75.3 g/day (20% of generated tritium) when helium gas flows so that tritium partial pressure becomes 1 Pa at the outlet.

JAEA Reports

Conceptual design of solid breeder blanket system cooled by supercritical water

Enoeda, Mikio; Ohara, Yoshihiro; Akiba, Masato; Sato, Satoshi; Hatano, Toshihisa; Kosaku, Yasuo; Kuroda, Toshimasa*; Kikuchi, Shigeto*; Yanagi, Yoshihiko*; Konishi, Satoshi; et al.

JAERI-Tech 2001-078, 120 Pages, 2001/12

JAERI-Tech-2001-078.pdf:8.3MB

This report is a summary of the design works, which was discussed in the design workshop held in 2000 for the demonstration (DEMO) blanket aimed to strengthen the commercial competitiveness and technical feasibility simultaneously. The DEMO blanket must supply the feasibility and experience of the total design of the power plant and the materials. This conceptual design study was performed to determine the updated strategy and goal of the R&D of the DEMO blanket which applies the supercritical water cooling proposed in A-SSTR, taking into account the recent progress of the plasma research and reactor engineering technology.

Journal Articles

Nuclear and thermal analyses of supercritical-water-cooled solid breeder blanket for fusion DEMO reactor

Yanagi, Yoshihiko*; Sato, Satoshi; Enoeda, Mikio; Hatano, Toshihisa; Kikuchi, Shigeto*; Kuroda, Toshimasa*; Kosaku, Yasuo; Ohara, Yoshihiro

Journal of Nuclear Science and Technology, 38(11), p.1014 - 1018, 2001/11

 Times Cited Count:24 Percentile:83.32(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Development of procurement for ITER-TF coil; Trial winding

Takayanagi, Tadatoshi*; Kuno, Kazuo*; Hasegawa, Mitsuru*; Koizumi, Norikiyo; Nakajima, Hideo; Hamada, Kazuya; Nunoya, Yoshihiko; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Development of procurement for ITER-TF coil

Koizumi, Norikiyo; Nakajima, Hideo; Matsui, Kunihiro; Isono, Takaaki; Hamada, Kazuya; Nunoya, Yoshihiko; Nabara, Yoshihiro; Oshikiri, Masayuki; Okuno, Kiyoshi; Takayanagi, Tadatoshi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Screening of low temperature flowering lines and flower shape/color mutant lines from ion beam irradiated chrysanthemum

Asami, Itsuo*; Tsuji, Takako*; Fukuta, Shiro*; Kuroyanagi, Satoru*; Hasegawa, Toru*; Takeuchi, Yoshihiko*; Hase, Yoshihiro; Nozawa, Shigeki; Narumi, Issei

no journal, , 

no abstracts in English

Oral presentation

Screening of low temperature flowering strains and flower shape/color mutans from chrysanthemum seedlings irradiated with ion beams

Asami, Itsuo*; Tsuji, Takako*; Fukuta, Shiro*; Kuroyanagi, Satoru*; Hasegawa, Toru*; Takeuchi, Yoshihiko*; Hase, Yoshihiro; Nozawa, Shigeki*; Narumi, Issey*

no journal, , 

no abstracts in English

Oral presentation

The Design of pipes in the cryostat for the JT-60SA

Onishi, Yoshihiro; Kamiya, Koji; Kuramochi, Masaya; Yanagi, Shunki; Honda, Atsushi; Kizu, Kaname; Koide, Yoshihiko; Yoshida, Kiyoshi

no journal, , 

no abstracts in English

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