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Towards understanding reactor relevant tokamak pedestals
Nuclear Fusion ( IF 3.3 ) Pub Date : 2021-08-02 , DOI: 10.1088/1741-4326/ac12e9
C.J. Ham 1 , A. Bokshi 2 , D. Brunetti 1 , G.Bustos Ramirez 3 , B. Chapman 1 , J.W. Connor 1 , D. Dickinson 4 , A.R. Field 1 , L. Frassinetti 5 , A. Gillgren 6 , J.P. Graves 3 , T.P. Kiviniemi 7 , S. Leerink 7 , B. McMillan 8 , S. Newton 1 , S. Pamela 1 , C.M. Roach 1 , S. Saarelma 1 , J. Simpson 1 , S.F. Smith 1 , E.R. Solano 9 , P. Strand 6 , A.J. Virtanen 7 , the JET Contributors
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The physics of the tokamak pedestal is still not fully understood, for example there is no fully predictive model for the pedestal height and width. However, the pedestal is key in determining the fusion power for a given scenario. If we can improve our understanding of reactor relevant pedestals we will improve our confidence in designing potential fusion power plants. Work has been carried out as part of a collaboration on reactor relevant pedestal physics. We report some of the results in detail here and review some of the wider work which will be reported in full elsewhere. First, we attempt to use a gyrokinetic-based calculation to eliminate the pedestal top density as a model input for Europed/EPED pedestal predictions. We assume power balance at the top of the pedestal, that is, the heat flux crossing the separatrix must be equal to the heat source at the top of the pedestal and investigate the consequences of this assumption. Unfortunately, the transport assumptions of the EPED model mean that this method does not discriminate between different pairs of density and temperature profiles for a given pressure profile. Second, we investigate the effects of non flux surface density on the bootstrap current. Third, type I ELMs will not be tolerable for a reactor relevant regime due to the damage that they are expected to cause to plasma facing components. In recent years various methods of running tokamak plasmas without large ELMs have been developed. These include small and no ELM regimes, the use of resonant magnetic perturbations and the use of vertical kicks. We discuss the quiescent H-mode here. Finally we give a summary and directions for future work.



中文翻译:

了解反应堆相关的托卡马克基座

托卡马克基座的物理学仍未完全了解,例如没有完全预测基座高度和宽度的模型。然而,基座是确定给定场景的聚变功率的关键。如果我们能够提高对反应堆相关基座的了解,我们将提高对设计潜在聚变发电厂的信心。作为与反应堆相关基座物理合作的一部分,已经开展了工作。我们在这里详细报告了一些结果,并回顾了一些更广泛的工作,这些工作将在其他地方完整报告。首先,我们尝试使用基于陀螺动力学的计算来消除基座顶部密度作为 Europed/EPED 基座预测的模型输入。我们假设基座顶部的功率平衡,即,穿过分界线的热通量必须等于基座顶部的热源,并调查此假设的结果。不幸的是,EPED 模型的传输假设意味着对于给定的压力分布,该方法不能区分不同的密度和温度分布对。其次,我们研究了非磁通表面密度对自举电流的影响。第三,由于 I 型 ELM 会对面向等离子体的组件造成损坏,因此它们对于反应堆相关制度将是不可容忍的。近年来,已经开发了多种运行托卡马克等离子体的方法,无需大型 ELM。这些包括小型和无 ELM 机制、共振磁扰的使用和垂直踢腿的使用。我们在这里讨论静态 H 模式。

更新日期:2021-08-02
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