HEATING OF TOROIDAL PLASMAS IN UNIVERSITIES IN JAPAN
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概要
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Experimental studies on heating of toroidal plasmas in universities in Japan are summarized. In Japan major fusion activities in universities are oriented to the development of so-called alternative concepts, that could improve some of the difficulties such as pulsive operation, complicated structure, and low plasma beta, that tokamaks must improve to develop into a fusion reactor. From this point of view, the purpose of plasma heating is not only to study and develop efficient heating method for fusion plasmas in general, but also to elaborate the way to produce high density and high temperature plasmas enough to be comparable to Joule-heated plasmas of tokamak. Three major activities in the alternative concepts are Nagoya Bumpy Torus (NBT) and JIPP T-II, stellarator-tokamak hybrid, both at the Institute of Plasma Physics, Nagoya University, and Heliotron-E at Kyoto University. Ion cyclotron heating (ICH) is studied on NBT where impurity oxygen ions are observed to increase in temperature from 10eV to approximately 60eV with 80kW input when ICH is tuned to protons. Provided Coulomb collisions for energy transfer between the proton and the oxygen ion, the proton temperature is estimated to be as high as 200-300eV. Lower hybrid heating (LHH) and neutral beam injection (NBI) is examined on JIPP T-II, showing the heating efficiency of 1eV/kW for LHH up to 120kW and approximately 2eV/kW for NBI up to 50kW. The stellarator configuration is observed less efficient in heating because of larger loss region due to helical ripples. Electron cyclotron heating (ECH) is applied to NBT and JIPP T-II, In the former, the plasma is produced and bulk electrons are heated to a few 100eV by several kW of ECH where the maximum density is limited by the applied microwave frequency when it equals to the electron plasma frequency. In the latter, ECH is examined on Joule-heated tokamak plasmas where the heating efficiency of approximately 2eV/kW is detected in electron temperature. Turbulent heating experiment on TRIAM-1 tokamak of Kyushu University shows that the bulk ions are heated from 140eV to 240eV within 200μsec. The interesting feature lies in the observation that the heated electrons remain only within the plasma surface of 1cm thickness continuing for 500μsec.
- 核融合科学研究所の論文
著者
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Ikegami H.
Research Information Center Institute Of Plasma Physics Nagoya University
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Ikegami H.
Research Information Center Institute Of Plasma Physice Nagoya University
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