| Project/Area Number |
06680479
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| Research Category |
Grant-in-Aid for General Scientific Research (C)
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| Allocation Type | Single-year Grants |
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| Research Field |
Nuclear fusion studies
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| Research Institution | Okayama University |
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Principal Investigator |
FUKUYAMA Atsushi Okayama University Faculty of Engineering Associate Professor, 工学部, 助教授 (60116499)
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| Project Period (FY) |
1994 – 1995
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| Project Status |
Completed (Fiscal Year 1995)
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| Budget Amount *help |
¥2,000,000 (Direct Cost: ¥2,000,000)
Fiscal Year 1995: ¥500,000 (Direct Cost: ¥500,000)
Fiscal Year 1994: ¥1,500,000 (Direct Cost: ¥1,500,000)
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| Keywords | Toroidal Plasma / Transport Phenomena / H Mode / Radial Electric Field / Plasma Rotation |
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| Research Abstract |
In order to study the particle transport and transient transport processes in toroidal plasmas, we have developed a transport simulation code including radial electric field and plasma rotation. Neoclassical transport and turbulent transport are included. Without an empirical pinch term, stationary density profile was obtained. The modification of a density profile during neutral beam injection, which has been observed in tokamak experiments, was reproduced by the simulation.
The dependence of the stationary density profile on the plasma current and the plasma temperature was studied in Ohmic plasmas. The central density is approximately proportional to the square of the plasma current and the inverse of the central temperature.
The influence of particle recycling rate, ion orbit loss and edge temperature on the density profile was studied by the transport analysis including the scrape-off layr.
The preliminary result of the analysis including heat transport shows flattening of the density profile by central heating.
The simulation code was modified to include toroidal viscosity essential for plasmas in helical systems. The effect on the plasma rotation and density profile was studied.
The simulation code was extended to exchange simulation data with the wave analysis codes and the Fokker-Planck code in order to analyze the wave heating and current drive.
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