Progress of divertor simulation research toward the realization of detached plasma using a large tandem mirror device

Nakashima, Yosuke*; Takeda, Hisahito*; Ichimura, Kazuya*; Hosoi, Katsuhiro*; Oki, Kensuke*; Sakamoto, Mizuki*; Hirata, Mafumi*; Ichimura, Makoto*; Ikezoe, Ryuya*; Imai, Tsuyoshi*; et al.

Journal of Nuclear Materials, 463, p.537 - 540, 2015/08

https://doi.org/10.1016/j.jnucmat.2014.12.063

Overview of recent Japanese activities and plans in fusion technology

Yamamoto, Ichiro*; Nishitani, Takeo; Sagara, Akio*

Fusion Science and Technology, 52(3), p.347 - 356, 2007/10

https://doi.org/10.13182/FST07-A1513

no abstracts in English

Overview of national centralized tokamak program; Mission, design and strategy to contribute ITER and DEMO

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.

Overview of the national centralized tokamak programme

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

https://doi.org/10.1088/0029-5515/46/3/S05

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.

Overview of design and R&D of test blankets in Japan

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

https://doi.org/10.1016/j.fusengdes.2005.08.097

no abstracts in English

Plan and strategy for ITER blanket testing in Japan

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

https://doi.org/10.13182/FST05-A822

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.

Electric power flow in a nuclear fusion power plant

Matsukawa, Makoto; Tobita, Kenji; Chikaraishi, Hirotaka*; Sagara, Akio*; Norimatsu, Takayoshi*

Purazuma, Kaku Yugo Gakkai-Shi, 80(7), p.559 - 562, 2004/07

https://doi.org/10.1585/jspf.80.559

Final purpose of the fusion energy development is to utilize the produced fusion power mainly as electric power for the easiness of transmission and conversion. In spite of the type of fusion power plant, large circulating electric power should exist in the plant for the plasma heating, current drive. This paper describes the electric power flow in the nuclear fusion power plants to be built as the DEMO reactor beyond ITER. Here, the necessity of the local energy storage and high efficient converter will be also discussed.

Measurements of evaporation rate of lithium from Al-Li alloy by depth profiling with an ion beams

Sagara, Akio*; *; Sasaki, Teikichi; Baba, Yuji

Nuclear Instruments and Methods in Physics Research B, 44, p.373 - 376, 1990/00

https://doi.org/10.1016/0168-583X(90)90653-C

no abstracts in English

Influence of the LHD glow discharge cleaning that born thin film

Yagyu, Junichi; Kizu, Kaname; Ishimoto, Yuki*; Ashikawa, Naoko*; Nishimura, Kiyohiko*; Yoshikawa, Akira*; Miya, Naoyuki; Okuno, Kenji*; Sagara, Akio*; Oya, Kiyohisa*

no journal, , 

no abstracts in English

Overview of recent Japanese activities and plans in fusion technology

Shimizu, Akihiko*; Hayashi, Takumi; Sagara, Akio*

no journal, , 

Development scenario to DEMO, 2; Blanket and material development

Enoeda, Mikio; Sagara, Akio*; Muroga, Takeo*

no journal, , 

Blanket is a key component which is expected to have capability of conversion of fusion energy to heat and production of fusion fuel tritium. Blanket is required to maintain the integrity under the heavy irradiation of fusion neutron through a few years of time period in service. In such demanding requirements of functions and durability, it is important to perform the development in mutual consistency between strategies of material development, Blanket structure development and Blanket system technology development. This lecture presents the draft development scenario of blanket and material for DEMO.