Ignition Analysis for D Plasma with Non-Maxwellian 3He Minority in Fusion Reactors
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概要
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Possible fusion reactivity enhancement due to 3He minority ICRF heating in D-3He toroidal plasma is demonstrated in present numerical simulations. On this purpose the particle code based on test-particle approach is developed. This code solves guiding center equations for 3He ions in toroidal magnetic field including Coulomb collisions of these ions with the background deuterons and electrons. A simple Monte Carlo model for ICRF heating is implemented in this code as well. The transformation of 3He distribution function from Maxwellian to non-Maxwellian due to heating plays the key role for reactivity enhancement. The formation of significant energetic tail gives rise to the reactivity enhancement. This is an important issue for the performance of fusion reactors with minority heating of ICRF.
- 社団法人 プラズマ・核融合学会の論文
著者
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SAGARA Akio
National Insitute for Fusion Science
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YANAGI Nagato
National Institute for Fusion Science
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SHYSHKIN Oleg
V.N. Karazin Kharkiv National University, Kharkiv, Svobody sq., 4, 61077, Ukraine
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MOSKVITIN Anton
V.N. Karazin Kharkiv National University, Kharkiv, Svobody sq., 4, 61077, Ukraine
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MOSKVITINA Yuliya
V.N. Karazin Kharkiv National University, Kharkiv, Svobody sq., 4, 61077, Ukraine
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