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    Article

    Review of Japanese fusion program and role of inertial fusion

    The high compression of 600 times liquid density and the recent fast heating of a compressed core to 1-keV temperature have provided proof-of-principle of the fast ignition concept, and these results have sign...

    O. Motojima in The European Physical Journal D (2007)

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    Chapter

    Spatial Distribution Measurement of High Energy Particle using Time-Of-Flight Neutral Particle Energy Analyzer in Large Helical Device

    The time-of-flight neutral particle measurement system1 has been installed on the 10-O port at the 2nd campaign. It has the capability of two-dimensional measurement with a larger viewing angle by using the pivot...

    T. Ozaki, P. Goncharov, S. Murakami, S. Sudo in Advanced Diagnostics for Magnetic and Iner… (2002)

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    Chapter

    LHD Cryogenic-Control System Performance Under Various Operating Conditions

    The Large Helical Device (LHD), an experimental fusion apparatus, has conducted a second experiment cycle. The infrastructure of the LHD cryogenic control system (TESS) is a combination of a distributed contro...

    R. Maekawa, T. Mito, K. Takahata, S. Yamada in Advances in Cryogenic Engineering (2000)

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    Chapter

    Hydraulic Characteristics of Cable-in-Conduit Conductors for Large Helical Device

    Poloidal field coils for the Large Helical Device (LHD) consist of Nb-Ti cable-in-conduit conductors. The first cool-down of LHD started in February of 1998, and the LHD experienced the cool-down three times u...

    K. Takahata, A. Iwamoto, R. Maekawa, T. Mito, T. Satow in Advances in Cryogenic Engineering (2000)

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    Chapter

    Overall Operating Characteristics of Superconducting Current-Feeder System for the LHD

    A superconducting (SC) current-feeder system is used as the cuirait transmission lines fon the LHD. It consists of nine SC bus lines with total length of 497 m and nine pairs of gas-cooled current leads. The c...

    S. Yamada, T. Mito, R. Maekawa, H. Chikaraishi in Advances in Cryogenic Engineering (2000)

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    Chapter

    Reliable Long-Term Operation of the Cryogenic System for the Large Helical Device

    Reliability is discussed during long-term operations of the cryogenic system for the Large Helical Device (LHD). The cooled objects of LHD are the helical coils, the poloidal coils, the supporting structure an...

    T. Mito, R. Maekawa, T. Baba, S. Moriuchi, A. Iwamoto in Advances in Cryogenic Engineering (2000)

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    Article

    Broadening of the particle resonance drift trajectory and tritium injection into a fusion reactor with an I=3 helical winding

    Two fusion reactor problems, removal of helium ash and fuel (tritium) injection, can be solved using the concept of “drift island motion.” The motion of a drift island is an indicator of the broadening of the ...

    A. A. Shishkin, O. Motojima, É. I. Polunovskii in Technical Physics Letters (1999)

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    Chapter and Conference Paper

    Performances of the Superconducting Coils for the Large Helical Device

    The Large Helical Device (LHD) is a plasma physics experimental device with two superconducting helical coils and three pairs of poloidal coils. All assembly and attachment works of LHD were completed, and the...

    T. Satow, S. Imagawa, K. Takahata, N. Yanagi in Advances in Superconductivity XI (1999)

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    Article

    Radiation Safety Considerations for LHD Experiments

    For experiments with the Large Helical Device (LHD) which is now under construction at the Toki site in Japan, radiation safety issues were discussed. In the course of plasma experiments, radiations such as X-...

    T. Uda, H. Yamanishi, H. Miyake, J. Kodaira, Y. Sakuma in Journal of Fusion Energy (1997)

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    Article

    Large Helical Device (LHD) program

    The largest superconducting fusion machine, Large Helical Device (LHD), is now under construction in Japan and will begin operation in 1997. Design and construction of related R&D programs are now being carrie...

    M. Fujiwara, K. Yamazaki, M. Okamoto, J. Todoroki, T. Amano in Journal of Fusion Energy (1996)

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    Article

    Nuclear design of a heliotron-H fusion power reactor

    Nuclear analysis was carried out for the heliotron-H fusion power reactor employing anl=2 helical heliotron field. The neutronics aspects examined were (a) tritium breeding capability, (b) shielding effectiveness...

    T. Matsui, H. Nakashima, M. Ohta, O. Motojima, M. Nakasuga in Journal of Fusion Energy (1985)