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首页> 外文期刊>Plasma physics and controlled fusion >Comparison of fusion alpha performance in JET advanced scenario and H-mode plasmas
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Comparison of fusion alpha performance in JET advanced scenario and H-mode plasmas

机译:在JET高级场景和H模式等离子体中融合alpha性能的比较

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摘要

Currently, plasmas with internal transport barriers (ITBs) appear the most likely candidates for steady-state scenarios for future fusion reactors. In such plasmas, the broad hot and dense region in the plasma core leads to high fusion gain, while the cool edge protects the integrity of the first wall. Economically desirable large bootstrap current fraction and low inductive current drive may, however, lead to degraded fast ion confinement. In this work the confinement and heating profile of fusion alphas were compared between H-mode and ITB plasmas in realistic JET geometry. The work was carried out using the Monte Carlo-based guiding-center-following code ASCOT. For the same plasma current, the ITB discharges were found to produce four to eight times more fusion power than a comparable ELMy H-mode discharge. Unfortunately, also the alpha particle losses were larger (similar to 16%) compared with the H-mode discharge (7%). In the H-mode discharges, alpha power was deposited to the plasma symmetrically around the magnetic axis, whereas in the current-hole discharge, the power was spread out to a larger volume in the plasma center. This was due to wider particle orbits, and the magnetic structure allowing for a broader hot region in the centre.
机译:当前,具有内部运输壁垒(ITB)的等离子体似乎是未来聚变反应堆稳态方案的最可能候选者。在这样的等离子体中,等离子体核心中较宽的热区和致密区会导致较高的熔合增益,而冷边缘会保护第一壁的完整性。然而,经济上理想的大自举电流份额和低感应电流驱动可能会导致快速离子约束降低。在这项工作中,在实际的JET几何结构中,比较了H型等离子体和ITB等离子体之间的融合α的约束和加热曲线。该工作是使用基于蒙特卡洛的制导中心跟随代码ASCOT进行的。对于相同的等离子体电流,发现ITB放电产生的熔化功率是可比ELMy H模式放电的四到八倍。不幸的是,与H模式放电(7%)相比,α粒子的损耗也更大(约16%)。在H模式放电中,α功率围绕磁轴对称地沉积到等离子体中,而在电流空穴放电中,功率在等离子体中心扩散到更大的体积。这是由于更宽的粒子轨道,以及磁性结构使得中心区域具有更宽的热区。

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