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Ninomiya, Hiromasa; Akiba, Masato; Fujii, Tsuneyuki; Fujita, Takaaki; Fujiwara, Masami*; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Hosogane, Nobuyuki; Ikeda, Yoshitaka; Inoue, Nobuyuki; et al.
Journal of the Korean Physical Society, 49, p.S428 - S432, 2006/12
To contribute DEMO and ITER, the design to modify the present JT-60U into superconducting coil machine, named National Centralized Tokamak (NCT), is being progressed under nationwide collaborations in Japan. Mission, design and strategy of this NCT program is summarized.
Kikuchi, Mitsuru; Tamai, Hiroshi; Matsukawa, Makoto; Fujita, Takaaki; Takase, Yuichi*; Sakurai, Shinji; Kizu, Kaname; Tsuchiya, Katsuhiko; Kurita, Genichi; Morioka, Atsuhiko; et al.
Nuclear Fusion, 46(3), p.S29 - S38, 2006/03
Times Cited Count：13 Percentile：41.76(Physics, Fluids & Plasmas)The National Centralized Tokamak (NCT) facility program is a domestic research program for advanced tokamak research to succeed JT-60U incorporating Japanese university accomplishments. The mission of NCT is to establish high beta steady-state operation for DEMO and to contribute to ITER. The machine flexibility and mobility is pursued in aspect ratio and shape controllability, feedback control of resistive wall modes, wide current and pressure profile control capability for the demonstration of the high-b steady state.
Tsuchiya, Katsuhiko; Akiba, Masato; Azechi, Hiroshi*; Fujii, Tsuneyuki; Fujita, Takaaki; Fujiwara, Masami*; Hamamatsu, Kiyotaka; Hashizume, Hidetoshi*; Hayashi, Nobuhiko; Horiike, Hiroshi*; et al.
Fusion Engineering and Design, 81(8-14), p.1599 - 1605, 2006/02
Times Cited Count：1 Percentile：9.98(Nuclear Science & Technology)no abstracts in English
Naito, Kazuya*; Tanaka, Hirohisa*; Taniguchi, Masashi*; Uenishi, Mari*; Tan, Isao*; Kajita, Nobuhiko*; Takahashi, Ichiro*; Suzuki, Hiromasa*; Narita, Keiichi*; Hirai, Akimasa*; et al.
SAE 2006 World Congress & Exhibition Technical Papers, 8 Pages, 2006/00
no abstracts in English
plasma operationTamai, Hiroshi; Akiba, Masato; Azechi, Hiroshi*; Fujita, Takaaki; Hamamatsu, Kiyotaka; Hashizume, Hidetoshi*; Hayashi, Nobuhiko; Horiike, Hiroshi*; Hosogane, Nobuyuki; Ichimura, Makoto*; et al.
Nuclear Fusion, 45(12), p.1676 - 1683, 2005/12
Times Cited Count：15 Percentile：45.53(Physics, Fluids & Plasmas)Design studies are shown on the National Centralized Tokamak facility. The machine design is carried out to investigate the capability for the flexibility in aspect ratio and shape controllability for the demonstration of the high-beta steady state operation with nation-wide collaboration, in parallel with ITER towards DEMO. Two designs are proposed and assessed with respect to the physics requirements such as confinement, stability, current drive, divertor, and energetic particle confinement. The operation range in the aspect ratio and the plasma shape is widely enhanced in consistent with the sufficient divertor pumping. Evaluations of the plasma performance towards the determination of machine design are presented.
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
Times Cited Count：2 Percentile：6.49(Physics, Fluids & Plasmas)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.
Ushigusa, Kenkichi; Ide, Shunsuke; Oikawa, Toshihiro; Suzuki, Takahiro; Kamada, Yutaka; Fujita, Takaaki; Ikeda, Yoshitaka; Naito, Osamu; Matsuoka, Mamoru*; Kondoh, Takashi; et al.
Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.255 - 277, 2002/09
Times Cited Count：10 Percentile：15.15(Nuclear Science & Technology)Studies on non-inductive current drive and development of an integrated steady-state high performance operation in JT-60 are reviewed. Experiments on lower hybrid current drive in JT-60 haven shown a large non-inductive current up to 3.5MA, high current drive efficiency of 3.6x1019m-2A/W. Basic studies on LH waves in JT-60 have contributed to understand current drive physics. Significant progress in neutral beam current drive has been made in JT-60 by testing the performance of negative ion based NBI (N-NBI). The CD efficiency of ~1.5x1019m-2A /W, and N-NB driven current of ~1MA have been demonstrated in N-NBCD. Strongly localized driven current by electron cyclotron current drive was identified with a fundamental O-mode scheme. Efficiency of 0.5x1019m-2A/W and EC driven current of 0.2MA were achieved and suppression of neo-classical tearing mode was demonstrated. Based on these developments, two integrated steady-state operation scenarios were developed in JT-60, which are reversed magnetic shear (R/S) plasmas and high bp ELMy H-mode. In these operation regimes, discharges have been sustained near the steady-state current profile under full non-inductive current drive. High performance plasmas with a high nDotETio and at high normalized density were also produced under fully non-inductive condition in high bp ELMy H-mode and R/S mode.
Kamada, Yutaka; Fujita, Takaaki; Ishida, Shinichi; Kikuchi, Mitsuru; Ide, Shunsuke; Takizuka, Tomonori; Shirai, Hiroshi; Koide, Yoshihiko; Fukuda, Takeshi; Hosogane, Nobuyuki; et al.
Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.185 - 254, 2002/09
Times Cited Count：34 Percentile：48.48(Nuclear Science & Technology)With the main aim of providing physics basis for ITER and the steady-state tokamak reactors, JT-60/JT-60U has been developing and optimizing the operational concepts, and extending the discharge regimes toward sustainment of high integrated performance in the reactor relevant parameter regime. In addition to achievement of the equivalent break-even condition (QDTeq up to 1.25) and a high fusion triple product = 1.5E21 m-3skeV, JT-60U has demonstrated the integrated performance of high confinement, high beta-N, full non-inductive current drive with a large fraction of bootstrap current in the reversed magnetic shear and in the high-beta-p ELMy H mode plasmas characterized by both internal and edge transport barriers. The key factors in optimizing these plasmas are profile and shape controls. As represented by discovery of various Internal Transport Barriers, JT-60/JT-60U has been emphasizing freedom and restriction of profiles in various confinement modes. JT-60U has demonstrated applicability of these high confinement modes to ITER and also clarified remaining issues.
Ninomiya, Hiromasa; Kitsunezaki, Akio; Shimizu, Masatsugu; Kuriyama, Masaaki; JT-60 Team; Kimura, Haruyuki; Kawashima, Hisato; Tsuzuki, Kazuhiro; Sato, Masayasu; Isei, Nobuaki; et al.
Fusion Science and Technology, 42(1), p.7 - 31, 2002/07
Times Cited Count：13 Percentile：27.27(Nuclear Science & Technology)In order to establish scientific basis for the sustainment of highly integrated performance required in the advanced steady-state operation, JT-60U has been optimizing the discharge control scenarios of improved confinement plasmas and expanding the operation regions. Promising results toward the steady-state tokamak were obtained. The detail of such results is reported. JFT-2M has performed advanced and basic research for the development of high performance tokamak plasma as well as the structural material for a fusion reactor. The toroidal ripple reduction with ferritic steel plates outside the vacuum vessel was successfully demonstrated. No adverse effects were observed in the pre-testing on compatibility between ferritic steel plates, covering ~20% of the inside wall of the vacuum vessel, and plasma. The results of TRIAM-1M is also reported.
; Kimura, Toyoaki; Yonekawa, Izuru; Kurihara, Kenichi; ; ; Hosogane, Nobuyuki; Yoshino, Ryuji; Ninomiya, Hiromasa; Kawamata, Yoichi; et al.
Fusion Engineering and Design, 5, p.69 - 84, 1987/00
Times Cited Count：9 Percentile：66.68(Nuclear Science & Technology)no abstracts in English
Fujita, Takaaki; Tamai, Hiroshi; Matsukawa, Makoto; Suzuki, Takahiro; Hayashi, Nobuhiko; Kurita, Genichi; Tsuchiya, Katsuhiko; Sakurai, Shinji; Oyama, Naoyuki; Kamada, Yutaka; et al.
no journal, ,
no abstracts in English
Sato, Hidetomo*; Nakano, Hiromasa*; Yokota, Hitoshi*; Suzuki, Tetsuya*; Maekawa, Katsuhiro*; Kurata, Yuji
no journal, ,
Liquid lead-bismuth is a candidate material used for accelerator driven systems and fast reactors. One of difficulties to apply Pb-Bi to nuclear systems is the corrosiveness of liquid Pb-Bi to structural steels. For this reason the study has been focused on improvement of corrosion resistance due to addition of Si and Al to steels. In this study, type 316 stainless steel was coated by Al-Ti-Fe eutectic alloy layer to enhance corrosion resistance in liquid lead-bismuth. The coating was conducted by a powder eutectic method using laser heating. The optimum condition to produce good coating layers was obtained concerning laser pulse energy and chemical composition of powders.
Sato, Hidetomo*; Nakano, Hiromasa*; Yokota, Hitoshi*; Suzuki, Tetsuya*; Maekawa, Katsuhiro*; Kurata, Yuji
no journal, ,
Liquid lead-bismuth is a candidate material used for accelerator driven systems and fast reactors. One of difficulties to apply Pb-Bi to nuclear systems is the corrosiveness of liquid Pb-Bi to structural steels. Recently, an Al alloy coating technique using Al and Ti powders was developed. In this study, type 316 stainless steel was coated with Al-Ti-Fe alloy layer to enhance corrosion resistance in liquid lead-bismuth. As a result of the corrosion test of the Al alloy coated specimens in liquid lead-bismuth, it was found that the coated layer exhibited good corrosion resistance to lead-bismuth.
Furuno, Akiko; Nagai, Haruyasu; Terada, Hiroaki; Tsuzuki, Katsunori; Nakayama, Hiromasa; Kadowaki, Masanao
no journal, ,
SPEEDI (System for Prediction of Environmental Emergency Dose Information) is a computer system that quickly predicts the atmospheric dispersion and the environmental impact of radioactive substances released into the atmosphere in a nuclear accident. During the Fukushima accident in 2011, SPEEDI calculation was executed according to the monitoring guideline by the former Nuclear Safety Commission, but prediction results were not utilized for evacuation planning by decision makers. The Nuclear Regulation Authority concluded that it is not adequate to use SPEEDI for the judgment of protective measures in emergency because it is difficult to accurately predict the timing and amount of release. However, the usefulness of SPEEDI has not been denied, and the local government can utilize SPEEDI with their own judgment and responsibility. We will also present our activities for the Fukushima accident, mainly about the release amount estimation.
