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Kanai, Akihiko*; Kasada, Ryuta*; Nakajima, Motoki; Hirose, Takanori; Tanigawa, Hisashi; Enoeda, Mikio; Konishi, Satoshi*
Journal of Nuclear Materials, 455(1-3), p.431 - 435, 2014/12
Times Cited Count：0 Percentile：0.01(Materials Science, Multidisciplinary)Kanai, Akihiko*; Park, C.*; Noborio, Kazuyuki*; Kasada, Ryuta*; Konishi, Satoshi*; Hirose, Takanori; Nozawa, Takashi; Tanigawa, Hiroyasu
Fusion Engineering and Design, 89(7-8), p.1653 - 1657, 2014/10
Times Cited Count：4 Percentile：30.92(Nuclear Science & Technology)Konishi, Satoshi*; Enoeda, Mikio
Purazuma, Kaku Yugo Gakkai-Shi, 90(6), p.332 - 337, 2014/06
Test Blanket Module (TBM) program is to evaluate important functions of prototypical modules of DEMO breeding blankets in the real DT fusion plasma environment of ITER. Therefore, it is regarded as one of the most important milestones toward DEMO blanket. Japan is proposing a Water Cooled Ceramic Breeder (WCCB) TBM as the primary option of TBM program. Japan Atomic Energy Agency (JAEA) is performing the development of the WCCB blanket as the candidate breeding blanket of Japan, with a collaboration of universities and National Institute for Fusion Science (NIFS). Regarding the TBM development, the engineering R and Ds are ongoing, aiming at the demonstration of fabrication technology and structural integrity of the full size mockup of the WCCB TBM. Regarding the test blanket module fabrication technology development, the real scale back wall mockup was successfully fabricated. Also, the design activities are being performed to show the soundness under various loading conditions of electromagnetic force and thermo-mechanical loading. The evaluation of shutdown dose rate behind the TBM test port is also carried out as one of most important design requirement. Furthermore, key technologies toward DEMO blanket, such as, the development of advanced breeder and multiplier pebbles for DEMO blanket, fabrication technology development of Li rich Li
TiO
pebble and BeTi pebble was performed.
Kwon, S.*; Sato, Satoshi; Kasada, Ryuta*; Konishi, Satoshi*
Fusion Science and Technology, 64(3), p.599 - 603, 2013/09
Times Cited Count：2 Percentile：18.63(Nuclear Science & Technology)Tritium production/breeding behavior in LiPb blanket module was evaluated by neutron transport code MCNP with nuclear cross-section data from FENDL-2.1 libraries. The calculation results were suggested that the sufficient TBR can be obtained in the SiC-LiPb blanket concept. A proper integral experiment on LiPb with DT neutrons in a small test module was evaluated. Also, tritium breeding ratio, tritium production ratio, proper neutron shielding material and nuclear heating in the module were evaluated. With the results of TPR and actual neutron generation devices, we have proposed the plan of the integral experiment and measurable tritium amount.
Isobe, Kanetsugu; Yamanishi, Toshihiko; Konishi, Satoshi*
Fusion Engineering and Design, 85(7-9), p.1012 - 1015, 2010/12
Times Cited Count：10 Percentile：56.32(Nuclear Science & Technology)The measurement of tritium permeation behavior of NITE-SiC/SiC composites in both low tritium partial pressure and tritium diluted with hydrogen was carried out. Steady-state tritium permeation fluxes of NITE-SiC/SiC that has low permeability of hydrogen could be measured successfully by using tritium, even though low partial pressure (0.6 Pa). Steady-state tritium permeation fluxes were estimated to be 9.5
10
[mol/m
sec]. In the experiment of tritium diluted with hydrogen, it was found that steady-states permeation fluxes was decreased with the increase of distillation rate, although the partial pressure of tritium in all condition was same (0.6 Pa).
Konishi, Satoshi*; Glugla, M.*; Hayashi, Takumi
Fusion Engineering and Design, 83(7-9), p.954 - 958, 2008/12
Times Cited Count：16 Percentile：70.82(Nuclear Science & Technology)Ushigusa, Kenkichi; Seki, Masahiro; Ninomiya, Hiromasa; Norimatsu, Takayoshi*; Kamada, Yutaka; Mori, Masahiro; Okuno, Kiyoshi; Shibanuma, Kiyoshi; Inoue, Takashi; Sakamoto, Keishi; et al.
Genshiryoku Handobukku, p.906 - 1029, 2007/11
no abstracts in English
Yamamoto, Yoshihiko*; Yamanishi, Toshihiko; Kawamura, Yoshinori; Isobe, Kanetsugu; Yamamoto, Yasushi*; Konishi, Satoshi*
Fusion Science and Technology, 52(3), p.692 - 695, 2007/10
Times Cited Count：1 Percentile：11.32(Nuclear Science & Technology)A solid electrolyte (ionic conductor) cell has been developed for measurement and control of hydrogen and oxygen density in liquid metal blanket with LiPb. The ceramic tubes of the SrCe
Yb
O
(proton conductor) and Yttria Stabilized Zirconia (oxygen ion conductor) that can be used at operating temperature of LiPb blanket have been utilized for electrolytes of the devices, which enable the continuous measurement of respectively hydrogen and oxygen in liquid LiPb. Fundamental electrochemical data such as EMF for a partial pressure and ion conductivity were measured, and the results were used to evaluate the feasibility of these devices.
Takamura, Shuichi*; Kado, Shinichiro*; Fujii, Takashi*; Fujiyama, Hiroshi*; Takabe, Hideaki*; Adachi, Kazuo*; Morimiya, Osamu*; Fujimori, Naoji*; Watanabe, Takayuki*; Hayashi, Yasuaki*; et al.
Kara Zukai, Purazuma Enerugi No Subete, P. 164, 2007/03
no abstracts in English
Isobe, Kanetsugu; Nakamura, Hirofumi; Kaminaga, Atsushi; Tsuzuki, Kazuhiro; Higashijima, Satoru; Nishi, Masataka; Kobayashi, Yasunori*; Konishi, Satoshi*
Fusion Engineering and Design, 81(1-7), p.827 - 832, 2006/02
Times Cited Count：11 Percentile：60.27(Nuclear Science & Technology)Exhaust gas from JT-60U during experimental operation has been measured with Gas Chromatography (GC), and the gas exhaust characteristic from JT-60U on plasma discharge conditions has been investigated during the JT-60U experimental campaign in 2003-2004. During experimental operation of JT-60U, hydrogen isotope concentration strongly depended on the type of discharges such as high performance, long pulse and so on. On the other hand, impurity species, such as helium, hydrocarbon and carbon oxide, were detected during plasma discharges occasionally. During the experimental operation, plasma disruption remarkably tended to produce high concentration impurities. Glow discharge and Taylor discharge for wall conditioning also produced impurities. In the case of normal plasma, impurity was detected and high performance plasma, such as high 
plasma, tended to produce high concentration impurities. This result indicated that impurities concentration might be higher in the case of normal plasma in ITER, because of its high performance.
Enoeda, Mikio; Akiba, Masato; Tanaka, Satoru*; Shimizu, Akihiko*; Hasegawa, Akira*; Konishi, Satoshi*; Kimura, Akihiko*; Koyama, Akira*; Sagara, Akio*; Muroga, Takeo*
Fusion Engineering and Design, 81(1-7), p.415 - 424, 2006/02
Times Cited Count：62 Percentile：96.4(Nuclear Science & Technology)no abstracts in English
Takatsu, Hideyuki; Konishi, Satoshi*
Purazuma, Kaku Yugo Gakkai-Shi, 81(11), p.837 - 902, 2005/11
Technology research and development issues, other than Breeding Blankets and Structural Materials, nesessary to be developed toward a fusion DEMO plant are introduced. Taking five critical technologies (Divertor, Superconducting Magnets, Tritium System, Heating and Current Drive system and Remote Maintenance System), target specifications and current status of technology research and development are outlined.
Tobita, Kenji; Konishi, Satoshi*; Tokimatsu, Koji*; Nishio, Satoshi; Hiwatari, Ryoji*
Purazuma, Kaku Yugo Gakkai-Shi, 81(11), p.875 - 891, 2005/11
no abstracts in English
Isobe, Kanetsugu; Nakamura, Hirofumi; Kaminaga, Atsushi; Higashijima, Satoru; Nishi, Masataka; Konishi, Satoshi*; Nishikawa, Masabumi*; Tanabe, Tetsuo*
Fusion Science and Technology, 48(1), p.302 - 305, 2005/07
Times Cited Count：5 Percentile：35.8(Nuclear Science & Technology)no abstracts in English
Enoeda, Mikio; Akiba, Masato; Tanaka, Satoru*; Shimizu, Akihiko*; Hasegawa, Akira*; Konishi, Satoshi*; Kimura, Akihiko*; Koyama, Akira*; Sagara, Akio*; Muroga, Takeo*
Fusion Science and Technology, 47(4), p.1023 - 1030, 2005/05
Times Cited Count：4 Percentile：30.51(Nuclear Science & Technology)The Fusion Council of Japan has established the long-term research and development program of the blanket in 1999. In the program, the solid breeder blanket was selected as the primary candidate blanket of the fusion power demonstration plant in Japan. In the program, Japan Atomic Energy Research Institute (JAERI) has been nominated as a leading institute of the development of solid breeder blankets, in collaboration with universities, for the near term power demonstration plant, while, universities including National Institute for Fusion Science (NIFS) are assigned mainly to develop advanced blankets for longer term power plant development. In the long term research and development program, ITER blanket module testing is identified as the most important milestone, by which integrity of candidate blanket concepts and structures are evaluated. In Japan, universities, NIFS and JAERI cover a variety of types of blanket development. This paper presents a plan and strategy for ITER blanket module testing in Japan.
Nagasaki, Takanori*; Yamaguchi, Kenji; Konishi, Satoshi*
Nihon Genshiryoku Gakkai-Shi, 46(11), p.770 - 779, 2004/11
no abstracts in English
Tobita, Kenji; Nishio, Satoshi; Konishi, Satoshi*; Jitsukawa, Shiro
Journal of Nuclear Materials, 329-333(Part2), p.1610 - 1614, 2004/08
Times Cited Count：12 Percentile：61.53(Materials Science, Multidisciplinary)no abstracts in English
Konishi, Satoshi*; Kimura, Akihiko*; Akiba, Masato; Nakamura, Hiroo; Nagasaka, Takuya*; Muroga, Takeo*; Hasegawa, Akira*; Matsui, Hideki*
Nihon Genshiryoku Gakkai-Shi, 46(5), p.311 - 322, 2004/05
no abstracts in English
Nakamura, Hirofumi; Higashijima, Satoru; Isobe, Kanetsugu; Kaminaga, Atsushi; Horikawa, Toyohiko*; Kubo, Hirotaka; Miya, Naoyuki; Nishi, Masataka; Konishi, Satoshi*; Tanabe, Tetsuo*
Fusion Engineering and Design, 70(2), p.163 - 173, 2004/02
Times Cited Count：19 Percentile：75.21(Nuclear Science & Technology)In order to establish the effective and conventional in-vessel tritium removal method, glow discharge methods, usually used as wall conditioning, have been applied and examined in vacuum vessel of JT-60U for tritium removal characteristics and kinetics. Release rates of all hydrogen isotopes as well as hydrocarbons from JT-60U vacuum vessel induced by Glow Discharge Cleaning (GDC) with He and H were measured. Release characteristics of hydrogen isotopes were classified into three different release processes each of which is well described by a simple exponential decay with time. It was found that H GDC showed the superior hydrogen isotope release characteristics than the He GDC, probably because chemical processes, such as isotope exchanges assisted by the chemical sputtering process between discharged hydrogen and hydrogen isotopes plasma facing carbon tiles are enhanced by the H glow discharge. Based on the release kinetics observed in the present work, it is estimated that it will take several days to reduce tritium inventory in the surface area of JT-60U to a half by continuous H GDC at 573 K.
Kawamura, Yoshinori; Konishi, Satoshi; Nishi, Masataka
Fusion Science and Technology, 45(1), p.33 - 40, 2004/01
Times Cited Count：25 Percentile：81.94(Nuclear Science & Technology)Aiming at realization of the efficient blanket tritium recovery system of a fusion reactor, research and development of the hydrogen pump using the proton conductor are furthered. One of the advantages of the system using the hydrogen pump is concurrent processing of hydrogen isotopes and water vapor by one component. In this work, experimental research on the hydrogen extraction characteristic in a water molecule was performed with the hydrogen pump using SrCeYbO
. In hydrogen extraction from a water molecule, application of the threshold, voltage corresponding to the decomposition energy of water, is necessary. The observed threshold was about 500-600mV at 873K and decreased with the increase in water vapor pressure. About pumping of H-HO mixture gas, the permeation of H anteceded water decomposition, and the threshold of water decomposition increased with the increase in hydrogen partial pressure. In order to process concurrently, application of fairly higher voltage is expected to be necessary.
