JOPSS - Search Results

Journal Articles

Development of a new fusion power monitor based on activation of flowing water

Verzilov, Y. M.; Nishitani, Takeo; Ochiai, Kentaro; Kutsukake, Chuzo; Abe, Yuichi

Fusion Engineering and Design, 81(8-14), p.1477 - 1483, 2006/02

https://doi.org/10.1016/j.fusengdes.2005.08.061

Times Cited Count：2 Percentile：17.14(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Design study of a neutral beam injector for fusion DEMO plant at JAERI

Inoue, Takashi; Hanada, Masaya; Kashiwagi, Mieko; Nishio, Satoshi; Sakamoto, Keishi; Sato, Masayasu; Taniguchi, Masaki; Tobita, Kenji; Watanabe, Kazuhiro; DEMO Plant Design Team

Fusion Engineering and Design, 81(8-14), p.1291 - 1297, 2006/02

https://doi.org/10.1016/j.fusengdes.2005.08.074

Times Cited Count：11 Percentile：60.11(Nuclear Science & Technology)

Requirement and technical issues of the neutral beam inejctor (NBI) is discussed for fusion DEMO plant. The NBI for the fusion DEMO plant should be high efficiency, high energy and high reliability with long life. From the view point of high efficiency, use of conventional electrostatic accelerator is realistic. Due to operation under radiation environment, vacuum insulation is essential in the accelerator. According to the insulation design guideline, it was clarified that the beam energy of 1.52 MeV is possible in the accelerator. Development of filamentless, and cesium free ion source is required, based on the existing high current/high current density negative ion production technology. The gas neutralization is not applicable due to its low efficiency (60%). R&D on an advanced neutralization scheme such as plasma neutralization (efficiency: 80%) is required. Recently, development of cw high power semiconductor laser is in progress. The paper shows a conceptual design of a high efficiency laser neutralizer utilizing the new semiconductor laser array.

JAEA Reports

Annual report of Naka Fusion Research Establishment from April 1, 2004 to March 31, 2005

Naka Fusion Research Establishment

JAERI-Review 2005-046, 113 Pages, 2005/09

JAERI-Review-2005-046.pdf:24.35MB

This annual report provides an overview of research and development activities at Naka Fusion Research Establishment, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities, during the period from 1 April, 2004 to 31 March, 2005. The activities in the Naka Fusion Research Establishment are highlighted by researches in JT-60 and JFT-2M, theoretical and analytical plasma researches, research and development of fusion reactor technologies towards ITER and fusion power demonstration plants, and activities in support of ITER design and construction.

JAEA Reports

Annual report of Naka Fusion Research Establishment from April 1, 2003 to March 31, 2004

Naka Fusion Research Establishment

JAERI-Review 2004-023, 126 Pages, 2004/11

JAERI-Review-2004-023.pdf:28.0MB

no abstracts in English

JAEA Reports

Annual report of Naka Fusion Research Establishment from April 1, 2002 to March 31, 2003

Naka Fusion Research Establishment

JAERI-Review 2003-035, 129 Pages, 2003/11

JAERI-Review-2003-035.pdf:13.55MB

This annual report provides an overview of research and development (R&D) activities at Naka Fusion Research Establishment in collaboration with other research establishment of JAERI, research institutes, and universities during the period from 1 April, 2002 to 31 March, 2003. The activities in the Naka Fusion Research Establishment are highlighted by high performance plasma researches in JT-60 and JFT-2M, R&D of fusion reactor technologies towards ITER and fusion power demonstration plants, and activities in support of ITER design and construction.

Journal Articles

Thermofluid analysis of free surface liquid divertor in tokamak fusion reactor

Kurihara, Ryoichi

Fusion Engineering and Design, 61-62, p.209 - 216, 2002/11

https://doi.org/10.1016/S0920-3796(02)00171-0

Times Cited Count：4 Percentile：29.2(Nuclear Science & Technology)

To attain high fusion power density, the divertor must suffer high heat flux from the fusion plasma. It is very difficult to remove a high heat flux more than 20 MW/m $^{2}$ using the only solid divertor plate from the viewpoint of severe mechanical state such as thermal stress and crack growth. Therefore, a concept of liquid divertor is proposed to remove high heat flux by liquid films flowing on a solid wall. This paper mainly descries a preliminary thermofluid analysis of the free surface liquid flow, made of the FliBe molten salt, using the finite element analysis code ADINA-F. The heat flux of 25100 MW/m $^{2}$ was given on the free surface liquid of the flow. I explored a possibility of applying the secondary flow to enhance the heat transfer of the liquid flow suffering high heat flux. This analysis shows that the heat flux of 100 MW/m $^{2}$ can be removed by inducing the secondary flow in the free surface liquid FLiBe. And this paper shows that the liquid divertor using solid-liquid multi-phase flow makes possible large heat removal by utilizing the latent heat of fusion of solid phase.