OV/4-1 Plasma Physics Study and Laser Development for the Fast Ignition Realization Experiment (FIREX) Project
نویسندگان
چکیده
H. Azechi, K. Mima, Y. Fujimoto, S. Fujioka, H. Homma, T. Jitsuno, T. Johzaki, M. Koga, J. Kawanaka, N. Miyanaga, M. Murakami, H. Nagatomo, K. Nagai, M. Nakai, T. Nakamura, K. Nishihara, H. Nishimura, T. Norimatsu, K. Shigemori, H. Shiraga, K. Tsubakimoto Institute of Laser Engineering, Osaka Univ., 2-6 Yamada-oka, Suita, Osaka 565-0871 Japan e-mail: [email protected] A. Iwamoto, T. Mito, H. Sakagami, M. Isobe, T. Ozaki, O. Motojima National Institute for Fusion Science, Oroshi-cho, Toki, Gifu 509-5292, Japan R. Kodama, K. Kondo, K.A. Tanaka Graduate School of Engineering, Osaka Univ., 2-1 Yamada-oka, Suita Osaka 565-0871, Japan Y. Nakao Graduate School of Engineering, Kyushu Univ., 6-10-6 Hakozaki, Higashi-ku, Fukuoka 812-8581, Japan Y. Sentoku Nevada Tera Watt Facility, Reno, Nevada 89506, USA A. Sunahara Institute for Laser Technology, Osaka Univ., 2-6 Yamada-oka, Suita, Osaka 565-0871 Japan T. Taguchi Graduate School of Engineering, Setsunan Univ., 17-8 Ikedanaka-machi, Neyagawa, Osaka 572-8508, Japan
منابع مشابه
Numerical Study of Advanced Target Design for FIREX-I
In the fast ignition (FI) scheme, at first high-density fuel core plasma is assembled by implosion laser, and it is then heated by peta watt laser to achieve fusion burning condition. A typical target for FI is a shell fitted with a reentrant Au cone to make a pass for heating laser. It is found that a high-Z material such as Au has disadvantage as a cone material in the long-duration and high-...
متن کاملIntegrated Simulations and Respective Simulation Modeling for FIREX-I
Integrated simulations for the fast ignition with a cone-guided target and 10[ps] heating laser have been performed to investigate the core heating property of FIREX-I experiments. It was found that the core reached higher average temperature when the preformed plasma on an inner surface of the cone tip had longer scale length. As the scale length of the preformed plasma was not easily controll...
متن کاملEnergy Gain of Magnetized Cylindrical D-T Targets in Fast Ignition Fusion
In recent years, many different plans have been considered to use the nuclear energy gained from inertial confinement fusion (ICF) as attempts to obtain high energy efficiencies. In conventional ICF methods, a small amount (about mg) of the deuterium–tritium compound is confined in a small spherical chamber of a few millimeters in radius and compressed by laser or heavy ion beams with powers in...
متن کاملEnergy Gain of Magnetized Cylindrical D-T Targets in Fast Ignition Fusion
In recent years, many different plans have been considered to use the nuclear energy gained from inertial confinement fusion (ICF) as attempts to obtain high energy efficiencies. In conventional ICF methods, a small amount (about mg) of the deuterium–tritium compound is confined in a small spherical chamber of a few millimeters in radius and compressed by laser or heavy ion beams with powers in...
متن کاملEncapsulation of low density plastic foam materials for the fast ignition realization experiment (FIREX) –control of microstructure and density–
Development of foam capsule fabrication for cryogenically cooled fuel targets is overviewed in the present paper. The fabrication development was initiated as a part of the Fast Ignition Realization Experiment (FIREX) Project at the ILE, Osaka University in the way of bilateral collaboration between Osaka University and National Institute for Fusion Science (NIFS). A foam cryogenic target was d...
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تاریخ انتشار 2008