{"title":"Estimation of impact of non-local ion heat flux model on transport simulation for DEMO-relevant scrape-off layer plasma","authors":"Yuki Homma, Kazuo Hoshino, Shohei Yamoto, Shinsuke Tokunaga, Nobuyuki Asakura, Naoaki Miyato","doi":"10.1002/ctpp.202300142","DOIUrl":null,"url":null,"abstract":"<p>In a fusion DEMOnstration reactor (DEMO)-relevant scrape-off layer plasma (SOL), whose collisionality is lower than in the SOLs of present-day tokamaks, kinetic effects are predicted to reduce the plasma heat conductivity along the magnetic field below the value obtained with the classical Spitzer–Harm model. As a part of ongoing efforts to improve the predictive capability of SOL heat transport calculations, we have implemented the non-local heat flux model proposed by [Luciani, Mora and Virmont, Phys. Rev. Lett. <b>51</b> (1983) 1664–1667] (here referred to as the LMV model) in the integrated SOL–divertor simulation code SONIC in order to account for the kinetic effect on the heat conduction due to the parallel streaming of rapidly moving particles. Our transport simulations for the Japanese demonstration tokamak reactor concept, JA DEMO, show that the LMV model yields a significantly reduced ion parallel conductive heat flux density both on the low- and high-field side of the upstream SOL. The heat flux obtained with the LMV model seems to be consistent with earlier kinetic simulations of tokamak ion transport. As a consequence of the reduced heat flux, a significant increase in the ion temperature and a decrease in the density have also been found over a broad area of the upstream SOL.</p>","PeriodicalId":10700,"journal":{"name":"Contributions to Plasma Physics","volume":"64 7-8","pages":""},"PeriodicalIF":1.3000,"publicationDate":"2024-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Contributions to Plasma Physics","FirstCategoryId":"101","ListUrlMain":"https://onlinelibrary.wiley.com/doi/10.1002/ctpp.202300142","RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"PHYSICS, FLUIDS & PLASMAS","Score":null,"Total":0}
引用次数: 0
Abstract
In a fusion DEMOnstration reactor (DEMO)-relevant scrape-off layer plasma (SOL), whose collisionality is lower than in the SOLs of present-day tokamaks, kinetic effects are predicted to reduce the plasma heat conductivity along the magnetic field below the value obtained with the classical Spitzer–Harm model. As a part of ongoing efforts to improve the predictive capability of SOL heat transport calculations, we have implemented the non-local heat flux model proposed by [Luciani, Mora and Virmont, Phys. Rev. Lett. 51 (1983) 1664–1667] (here referred to as the LMV model) in the integrated SOL–divertor simulation code SONIC in order to account for the kinetic effect on the heat conduction due to the parallel streaming of rapidly moving particles. Our transport simulations for the Japanese demonstration tokamak reactor concept, JA DEMO, show that the LMV model yields a significantly reduced ion parallel conductive heat flux density both on the low- and high-field side of the upstream SOL. The heat flux obtained with the LMV model seems to be consistent with earlier kinetic simulations of tokamak ion transport. As a consequence of the reduced heat flux, a significant increase in the ion temperature and a decrease in the density have also been found over a broad area of the upstream SOL.
在核聚变演示反应堆(DEMO)相关的刮除层等离子体(SOL)中,其碰撞性低于当今托卡马克的等离子体,根据预测,动力学效应会使等离子体沿磁场的热传导率低于经典的斯皮策-哈姆模型所得到的值。为了提高 SOL 热传导计算的预测能力,我们在 SOL 分流器综合模拟代码 SONIC 中采用了[Luciani、Mora 和 Virmont,Phys. Rev. Lett. 51 (1983) 1664-1667]提出的非局部热通量模型(这里称为 LMV 模型),以考虑快速运动粒子平行流对热传导的动力学效应。我们对日本示范托卡马克反应堆概念(JA DEMO)的传输模拟表明,LMV 模型可显著降低上游 SOL 低场和高场一侧的离子平行传导热通量密度。利用 LMV 模型获得的热通量似乎与早期的托卡马克离子传输动力学模拟一致。由于热通量的降低,在上游 SOL 的广大区域内还发现了离子温度的显著上升和密度的降低。