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A DT fusion reactor design in field-reversed configuration using normal conductive coils

Y. Hirano, J. Sekiguchi, T. Matsumoto, T. Asai, Y. Nogi, M. Watanabe, T. Takahashi2018年被引用 2Nuclear FusionIF 3出版社

Assuming continued stability, favorable energy confinement time scaling, and an effective current drive and maintenance methods, a feasible DT fusion reactor design is proposed for field-reversed configuration (FRC) which uses normal conductive copper magnetic field coils at room temperature. The reactor has 3 GW fusion power, 1.5 MW m−2 neutron wall loading at the first wall, and thermal loading less than 1 MW m−2 at diverter plates. Plasma has an almost straight cylindrical shape of 40 m in length and 8.6 m in diameter. FRC can obtain very high beta (over 0.7 in average) and the magnetic field strength of the reactor will be 1.215 T, which can be produced by normal conductive coils having 70 m in length, 17.6 m in diameter, and 1.5 m in thickness with 0.6 effective conductive area ratio. Its Ohmic power loss is ~74 MW, which is less than 10% of the expected electric power output. A scenario to reach ignition from the initial formation is considered. At first, two FRCs are formed at the both ends of the reactor by fast theta-pinch with a negative bias magnetic field 6 m in length and 0.5 m in diameter. The FRCs are accelerated up to 250 km s−1 by the gradient of magnetic field strength towards the center of the burning region, collide with each other, and form a single large FRC. Their kinetic energy is converted to thermal energy, and the merged FRC is 10 m in length and 1.8 m in diameter. This FRC plasma is brought to ignition by intensive neutral beam injection (NBI) heating and particle supply. Given 200 s heating duration, the maximum NBI power is ~250 MW before alpha particle heating becomes significant. After ignition, NBI heating is not required, but there is a possibility that some part of equilibrium current must be supplied by the NBI in the MeV region.

日本語訳

安定性の持続、良好なエネルギー閉じ込め時間スケーリング、および効果的な電流駆動・維持方法を仮定すると、室温で常伝導銅磁場コイルを用いる磁場反転配位(FRC)に対する実現可能なDT核融合炉設計が提案される。この炉は、3 GWの核融合出力、第一壁での1.5 MW m−2の中性子壁負荷、およびダイバータ板での1 MW m−2未満の熱負荷を有する。プラズマは、長さ40 m、直径8.6 mのほぼ直円筒形状を有する。FRCは非常に高いベータ値(平均で0.7超)を得ることができ、炉の磁場強度は1.215 Tとなり、これは長さ70 m、直径17.6 m、厚さ1.5 m、実効導電面積比0.6の常伝導コイルによって生成できる。そのオーミック電力損失は~74 MWであり、これは想定される電力出力の10%未満である。初期形成から点火に至るシナリオが検討される。まず、2つのFRCが、長さ6 m、直径0.5 mの負バイアス磁場を伴う高速シータピンチによって、炉の両端に形成される。それらのFRCは、燃焼領域の中心に向かう磁場強度の勾配によって250 km s−1まで加速され、互いに衝突して、単一の大きなFRCを形成する。それらの運動エネルギーは熱エネルギーに変換され、合体したFRCは長さ10 m、直径1.8 mとなる。このFRCプラズマは、強力な中性粒子ビーム入射(NBI)加熱と粒子供給によって点火に至る。加熱時間を200秒とすると、アルファ粒子加熱が顕著になる前の最大NBIパワーは~250 MWである。点火後はNBI加熱は不要であるが、平衡電流の一部はMeV領域のNBIによって供給されなければならない可能性がある。

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