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Ono, Ayako; Okawa, Tomio*
Proceedings of 2025 International Congress on Advances in Nuclear Power Plants (ICAPP 2025) (Internet), 12 Pages, 2025/09
We aim to establish a new prediction method for departure from nucleate boiling (DNB) in fuel assemblies, contributing to the design and safety evaluation of next-generation reactors. Since the formation of a large vapor mass on the heating surface is considered the initial trigger of DNB, we focus on predicting the heat flux required for its formation. To achieve this, we integrate two-phase flow computational fluid dynamics (CFD) with a mechanistic large vapor mass formation model. In this study, we develop a simplified numerical analysis method that simulates bubble generation, growth, motion, and coalescence to predict large vapor mass formation. Additionally, we investigate the vapor volume on the heating surface at the onset of large vapor mass formation and predict their formation conditions.
Nishimura, Arata*; Muroga, Takeo*; Takeuchi, Takao*; Nishitani, Takeo; Morioka, Atsuhiko
Fusion Engineering and Design, 81(8-14), p.1675 - 1681, 2006/02
Times Cited Count：3 Percentile：22.98(Nuclear Science & Technology)In a fusion reactor plant, a neutral beam injector (NBI) will be operated for a long time, and it will allow neutron streaming from NBI ports to outside of the plasma vacuum vessel. It requires the superconducting magnet to develop nuclear technology to produce stable magnetic field and to reduce activation of the magnet components. In this report, the back ground of the necessity and the contents of the nuclear technology of the superconducting magnets for fusion application are discussed and some typical investigation results are presented, which are the neutron irradiation effect on Nb
Sn wire, the development of low activation superconducting wire, and the design concept to reduce nuclear heating and nuclear transformation by streaming. In addition, recent activities in high energy particle physics are introduced and potential ripple effect of the technology of the superconducting magnets is described briefly.
Hoshino, Katsumichi; Yamamoto, Takumi; Tamai, Hiroshi; Oasa, Kazumi; Kawashima, Hisato; Miura, Yukitoshi; Ogawa, Toshihide; Shoji, Teruaki*; Shibata, Takatoshi; Kikuchi, Kazuo; et al.
Fusion Science and Technology, 49(2), p.139 - 167, 2006/02
Times Cited Count：2 Percentile：16.39(Nuclear Science & Technology)The main results obtained by the various heating and current drive systems, external coil system and divertor bias system are reviewed from the viewpoint of the advanced active control of the tokamak plasma. Also, the features of each system are described. The contribution of the JFT-2M in these areas are summarized.
Inoue, Takashi; Sakamoto, Keishi
Nihon Genshiryoku Gakkai-Shi, 47(2), p.120 - 127, 2005/02
no abstracts in English
Kaneko, Osamu*; Yamamoto, Takumi; Akiba, Masato; Hanada, Masaya; Ikeda, Katsunori*; Inoue, Takashi; Nagaoka, Kenichi*; Oka, Yoshihide*; Osakabe, Masaki*; Takeiri, Yasuhiko*; et al.
Fusion Science and Technology, 44(2), p.503 - 507, 2003/09
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)High energy negative-ion-based neutral beam injection (N-NBI) is expected as an efficient and reliable tool of heating and current driving for reactor plasmas such as ITER. A world wide activity on developing technology of negative ion production and beam formation started in 1980's and the great progress has been achieved up to now. In particular, Japan has two large projects that planned adopting N-NBI for real plasma experiments; the JT-60U tokamak and the LHD heliotron, which further motivated the R&D activity. These R&D programs were carried out at JAERI and NIFS separately in Japan, and both were successfully done. The first beam injection experiment was made on the JT-60U in 1996, followed by the LHD in 1998. They were the first experiments on heating plasma by high energy beam in tokamaks and in stellerators, and the obtained results were very promising.
Inoue, Takashi
Purazuma, Kaku Yugo Gakkai-Shi, 78(5), p.398 - 404, 2002/05
Neutral beam (NB) heating and current drivesystem for ITER fires the energetic particle beams of 1 MeV, 33 MW (16.5 MW/NB injector) into the fusion plasma. The design allows late installation of third NB injector for upgrade in current drive experiment toward steady state operation. The ITER NB system has been designed to fulfill requirements of the plasma physics, including advanced scenario achieved with off-axis current drive by NB. A design overview of the ITER NB system is described. The paper also reports recent R&D status of ion source and accelerator, as key components of the NB system, toward ITER construction. NB heating and current drive performance required in future tokamak reactors are discussed together with the necessary R&D issues.
Inoue, Takashi; Di Pietro, E.*; Hanada, Masaya; Hemsworth, R. S.*; Krylov, A.*; Kulygin, V.*; Massmann, P.*; Mondino, P. L.*; Okumura, Yoshikazu; Panasenkov, A.*; et al.
Fusion Engineering and Design, 56-57, p.517 - 521, 2001/10
Times Cited Count：64 Percentile：96.06(Nuclear Science & Technology)no abstracts in English
Inoue, Takashi; Di Pietro, E.*; Mondino, P. L.*; Bayetti, P.*; Hemsworth, R. S.*; Massmann, P.*; Fujiwara, Yukio; Hanada, Masaya; Miyamoto, Kenji; Okumura, Yoshikazu; et al.
Review of Scientific Instruments, 71(2), p.744 - 746, 2000/02
Times Cited Count：18 Percentile：68.34(Instruments & Instrumentation)no abstracts in English
ITER Physics Expert Group on Energetic Particles, Heating and Current Drive
Nuclear Fusion, 39(12), p.2495 - 2539, 1999/00
no abstracts in English
Fujiwara, Yukio; Inoue, Takashi; Miyamoto, Kenji; Miyamoto, Naoki*; Ohara, Yoshihiro; Okumura, Yoshikazu; Shibata, Keiichiro*; Suzuki, Satoshi; Tanii, Masahiro*; Watanabe, K
Fusion Technology, 30(3P2A), p.810 - 814, 1996/12
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)no abstracts in English
Inoue, Takashi; ; ; Yamashita, Y.*
Fusion Technology 1996, 0, p.1799 - 1802, 1996/00
no abstracts in English
Inoue, Takashi; Okumura, Yoshikazu; Fujiwara, Yukio; Miyamoto, Kenji; Ohara, Yoshihiro; Miyamoto, Naoki*; Watanabe, Kazuhiro; B.Heinemann*; Tanii, Masahiro*
Fusion Technology 1996, 1, p.701 - 704, 1996/00
no abstracts in English
S.Zimin*; ; Takatsu, Hideyuki; Sato, Satoshi; Tsunematsu, Toshihide; Inoue, Takashi; Ohara, Yoshihiro
JAERI-Tech 94-015, 37 Pages, 1994/08
no abstracts in English
He fusion yield with a Fokker-Planck codeYamagiwa, Mitsuru; Kishimoto, Yasuaki; Fujii, Tsuneyuki; Kimura, Haruyuki
Nuclear Fusion, 33(3), p.493 - 500, 1993/00
Times Cited Count：6 Percentile：31.03(Physics, Fluids & Plasmas)no abstracts in English
; ; ; ; ; Yokokawa, Mitsuo
JAERI-M 92-142, 117 Pages, 1992/09
no abstracts in English
Yoshino, Ryuji; Kamada, Yutaka; Shimizu, Katsuhiro; Ozeki, Takahisa; Hirayama, Toshio; Sugie, Tatsuo; Nishitani, Takeo
Kaku Yugo Kenkyu, 65(SPECIAL ISSUE), p.163 - 183, 1991/03
no abstracts in English
He fusion yield with higher harmonic ICRF heating of He beamsYamagiwa, Mitsuru; Kimura, Haruyuki
Nuclear Fusion, 31(8), p.1519 - 1526, 1991/00
Times Cited Count：4 Percentile：27.89(Physics, Fluids & Plasmas)no abstracts in English
fusion yield in higher harmonic ICRF heated plasmaYamagiwa, Mitsuru; Kimura, Haruyuki; Takizuka, Tomonori; Fujii, Tsuneyuki
Proc. of the 17th EPS Conf. on Controlled Fusion and Plasma Heating, p.1007 - 1010, 1990/00
no abstracts in English
; ; ; ; JT-60 Team
JAERI-M 87-029, 30 Pages, 1987/03
no abstracts in English
JAERI-M 85-205, 214 Pages, 1986/01
no abstracts in English
