Reduced transport modelling of fast ions in MAST Upgrade
MAST 升级中减少快离子传输模型
基本信息
- 批准号:2820013
- 负责人:
- 金额:--
- 依托单位:
- 依托单位国家:英国
- 项目类别:Studentship
- 财政年份:2022
- 资助国家:英国
- 起止时间:2022 至 无数据
- 项目状态:未结题
- 来源:
- 关键词:
项目摘要
In fusion plasmas, fast ions have energies much higher than the thermal plasma background. Fast ions are generated by external auxiliary heating such as Neutral Beam Injection (NBI) and Ion Cyclotron Resonance Heating(ICRH) or by the fusion reactions themselves. In the former cases, fast ions are hydrogen isotopes with energies in the range from tens of keVs up to a few MeVs. Fusion reactions produce, in addition to hydrogen isotopes, alpha particles with energies in the MeV range.Fast ions play an important role in heating the plasma, maintaining the high temperatures necessary to sustain the fusion reactions and crucial in achieving a burning plasma. NBI heating is also important for current drive, that is for long pulse operation of tokamaks beyond the inductive regime and therefore for the realization of a fusion reactor.Confining fast ions in the plasma for time long enough so that they can transfer their energy to the background plasma is therefore crucial for achieving the goal of a power plant based on thermonuclear fusion reactions. However, fast ion confinement is degraded by plasma instabilities some of which are triggered by the fast ion themselves. In this case, energy exchange between the fast ions and the instabilities result in the redistribution and loss of fast ions, ultimately reducing the performances of fusion reactors. Furthermore, the loss of fast ions in the plasma can result in the damage of the reactor first wall, an issue particularly for the very energetic alpha particles that will be produced in ITER and DEMO.The interaction between FIs and MHD instabilities is an active and intense field of research Recent modelling developments include MHD and particle kinetics codes (with realistic description of the instabilities' amplitude and spatial structure and full orbit calculations) such as HALO (developed at CCFE) and the reduced transport "kick-model" for TRANSP/NUBEAM (developed at PPPL). Of particular importance, especially for MAST Upgrade, is the modelling of the FIs full orbits for the validation of theoretical predictions of the interplay between FIs and MHD instabilities such as sawteeth, fishbones, toroidal Alfvén eigenmodes, long-lived modes and edge localized modes. The spatial structure and temporal evolution of these instabilities, at times non-linearly coupled to the dynamics of the FIs, is crucial for the correct prediction of the confinement of FIs. The project is aimed at a systematic comparison of full-orbit and guiding-center reduced transport calculations with a set of fast ions experimental measurements on MAST Upgrade in presence of perturbations of the plasma equilibrium due to sawteeth, TEAs and fishbones. A particular focus will be dedicated to the modelling and interpretation of collimated neutron flux measurements using the upgraded neutron camera installed on MAST Upgrade and the comparison with other FI diagnostics (FILD, FIDA, compact NPA and charged fusion product detector). This is a modelling project for which good numerical computation skills are required. The research will be carried out mainly at Durham University with collaborations with CCFE (for HALO), the Princeton Plasma Physics Laboratory (for TRANSP/NUBEAM) and Aalto University (for ASCOT). The outcome of this project is a framework of reduced, rapid fast ion transport models that will be used to compare simulations and measurements probing different regions of the phase space thus providing an integrated understanding of the FIs dynamics. In turn, the outcome of this project will enable the development of operating scenarios where the effect of performance limiting distributions will be suppressed thus allowing improved FI confinement and non-inductive current drive. The main focus of this project is MAST Upgrade thanks to its on-axis/off-axis NB injection flexibility but the developed framework will be applicable to conventional tokamaks and will be of relevance to STEP, ITER and DEMO.
在聚变等离子体中,快离子具有比热等离子体背景高得多的能量。快离子是由外部辅助加热产生的,如中性束注入(NBI)和离子回旋共振加热(ICRH)或由聚变反应本身产生。在前一种情况下,快离子是氢同位素,其能量范围从几十keV到几MeV。聚变反应除了产生氢同位素外,还产生能量在MeV范围内的α粒子。快离子在加热等离子体、维持维持聚变反应所需的高温以及实现燃烧等离子体方面发挥着重要作用。NBI加热对于电流驱动也很重要,即托卡马克在感应区之外的长脉冲运行,因此对于实现聚变反应堆也很重要。因此,将快离子限制在等离子体中足够长的时间,使它们能够将能量转移到背景等离子体中,对于实现基于热核聚变反应的发电厂的目标至关重要。然而,快离子约束退化的等离子体不稳定性,其中一些是由快离子本身触发。在这种情况下,快离子之间的能量交换和不稳定性导致快离子的重新分布和损失,最终降低聚变反应堆的性能。此外,等离子体中快离子的损失会导致反应器第一壁的损坏,对于ITER和DEMO中将要产生的高能α粒子来说,这是一个特别重要的问题。FI和MHD不稳定性之间的相互作用是一个活跃而激烈的研究领域。最近的模拟发展包括MHD和粒子动力学代码(对不稳定性的幅度和空间结构以及全轨道计算的真实描述),如HALO(由CCFE开发)和TRANSP/NUBEAM的简化传输“反冲模型”(由PPPL开发)。特别重要的是,特别是MAST升级,是FI的完整轨道的建模验证FI和MHD不稳定性之间的相互作用的理论预测,如锯齿,鱼骨,环形阿尔文本征模式,长寿命模式和边缘本地化模式。这些不稳定性的空间结构和时间演变,有时非线性耦合到FI的动态,是正确预测FI的限制的关键。该项目的目的是在锯齿、TEA和鱼骨等离子体平衡扰动的情况下,对全轨道和制导中心简化输运计算与MAST升级的一组快离子实验测量进行系统比较。一个特别的重点将致力于使用安装在MAST升级和与其他FI诊断(FILD,FIDA,紧凑型NPA和带电聚变产物探测器)的比较升级中子相机准直中子通量测量的建模和解释。这是一个需要良好的数值计算技能的建模项目。这项研究将主要在达勒姆大学进行,并与CCFE(为HALO),普林斯顿等离子体物理实验室(为TRANSP/NUBEAM)和阿尔托大学(为阿斯科特)合作。该项目的成果是一个框架,减少,快速快速离子传输模型,将用于比较模拟和测量探测不同区域的相空间,从而提供了一个综合的理解金融机构的动态。反过来,该项目的成果将使运行方案的发展,其中性能限制分布的影响将被抑制,从而允许改善FI限制和无感电流驱动。该项目的主要重点是MAST升级,这要归功于其轴上/离轴NB注入的灵活性,但开发的框架将适用于常规托卡马克,并将与STEP,ITER和DEMO相关。
项目成果
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其他文献
吉治仁志 他: "トランスジェニックマウスによるTIMP-1の線維化促進機序"最新医学. 55. 1781-1787 (2000)
Hitoshi Yoshiji 等:“转基因小鼠中 TIMP-1 的促纤维化机制”现代医学 55. 1781-1787 (2000)。
- DOI:
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LiDAR Implementations for Autonomous Vehicle Applications
- DOI:
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2021 - 期刊:
- 影响因子:0
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吉治仁志 他: "イラスト医学&サイエンスシリーズ血管の分子医学"羊土社(渋谷正史編). 125 (2000)
Hitoshi Yoshiji 等人:“血管医学与科学系列分子医学图解”Yodosha(涉谷正志编辑)125(2000)。
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Effect of manidipine hydrochloride,a calcium antagonist,on isoproterenol-induced left ventricular hypertrophy: "Yoshiyama,M.,Takeuchi,K.,Kim,S.,Hanatani,A.,Omura,T.,Toda,I.,Akioka,K.,Teragaki,M.,Iwao,H.and Yoshikawa,J." Jpn Circ J. 62(1). 47-52 (1998)
钙拮抗剂盐酸马尼地平对异丙肾上腺素引起的左心室肥厚的影响:“Yoshiyama,M.,Takeuchi,K.,Kim,S.,Hanatani,A.,Omura,T.,Toda,I.,Akioka,
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