An integral approach to plasma-wall interaction modelling for EU-DEMO

IF 3.5 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS Nuclear Fusion Pub Date : 2024-09-06 DOI:10.1088/1741-4326/ad73e7
D. Matveev, C. Baumann, J. Romazanov, S. Brezinsek, S. Ratynskaia, L. Vignitchouk, P. Tolias, K. Paschalidis, D. Tskhakaya, M. Komm, A. Podolník, J. Mougenot, Y. Charles, R. Delaporte-Mathurin, E. Hodille, C. Grisolia, F. Montupet-Leblond, K. Schmid, U. Von Toussaint, F. Granberg, F. Kporha, J. Kovačič, S. Costea
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Abstract

An integral approach to plasma-wall interaction (PWI) modelling for DEMO is presented, which is part of the EUROfusion Theory and Advanced Simulation Coordination activities that were established to advance the understanding and predictive capabilities for the modelling of existing and future fusion devices using a modern advanced computing approach. In view of the DEMO design, the aim of PWI modelling activities is to assess safety-relevant information regarding the erosion of plasma-facing components (PFCs), including its impact on plasma contamination, dust production, fuel inventory, and material response to transient events. This is achieved using a set of powerful and validated computer codes that deal with particular PWI aspects and interact with each other by means of relevant data exchange. Steady state erosion of tungsten PFC and subsequent transport and re-deposition of eroded material are simulated with the ERO2.0 code using a DEMO plasma background produced by dedicated SOLPS-ITER simulations. Dust transport simulations in steady state plasma also rely on the respective SOLPS-ITER solutions and are performed with the MIGRAINe code. In order to improve simulations of tungsten erosion in the divertor of DEMO, relevant high density sheath models are being developed based on particle-in-cell (PIC) simulations with the state-of-the-art BIT code family. PIC codes of the SPICE code family, in turn, provide relevant information on multi-emissive sheath physics, such as semi-empirical scaling laws for field-assisted thermionic emission. These scaling laws are essential for simulations of material melting under transient heat loads that are performed with the recently developed MEMENTO code, the successor of MEMOS-U. Fuel retention simulations assess tritium retention in tungsten and structural materials, as well as fuel permeation to the coolant, accounting for neutron damage. Simulations for divertor monoblocks of different sizes are performed using the FESTIM code, while for the first wall the TESSIM code is applied. Respective code-code dependencies and interactions, as well as modelling results achieved to date are discussed in this contribution.
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为 EU-DEMO 建立等离子体-壁相互作用模型的综合方法
该活动是欧洲聚变理论和先进模拟协调活动的一部分,旨在利用现代先进计算方法,提高对现有和未来聚变装置建模的理解和预测能力。鉴于 DEMO 的设计,PWI 建模活动的目的是评估与等离子体面组件(PFC)侵蚀有关的安全相关信息,包括其对等离子体污染、粉尘产生、燃料库存和材料对瞬态事件响应的影响。这是通过一套功能强大且经过验证的计算机代码实现的,这些代码处理特定的 PWI 方面,并通过相关数据交换进行交互。ERO2.0代码利用专门的SOLPS-ITER模拟产生的DEMO等离子背景,对钨全氟化碳的稳态侵蚀以及随后的侵蚀材料的传输和再沉积进行了模拟。稳态等离子体中的粉尘传输模拟也依靠各自的 SOLPS-ITER 解决方案,并使用 MIGRAINe 代码进行。为了改进对 DEMO 分流器中钨侵蚀的模拟,正在利用最先进的 BIT 代码系列,在粒子入室(PIC)模拟的基础上开发相关的高密度鞘模型。SPICE 代码系列的 PIC 代码则提供了多发射鞘物理学的相关信息,例如场辅助热释电的半经验缩放定律。最近开发的 MEMENTO 代码(MEMOS-U 的后续版本)对瞬态热负荷下的材料熔化模拟至关重要。燃料滞留模拟评估了氚在钨和结构材料中的滞留情况,以及燃料向冷却剂的渗透情况,并考虑了中子损伤。使用 FESTIM 代码对不同尺寸的分流器单体进行模拟,而对第一壁则使用 TESSIM 代码。本文将讨论代码与代码之间的相关性和相互作用,以及迄今为止取得的建模结果。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Nuclear Fusion
Nuclear Fusion 物理-物理:核物理
CiteScore
6.30
自引率
39.40%
发文量
411
审稿时长
2.6 months
期刊介绍: Nuclear Fusion publishes articles making significant advances to the field of controlled thermonuclear fusion. The journal scope includes: -the production, heating and confinement of high temperature plasmas; -the physical properties of such plasmas; -the experimental or theoretical methods of exploring or explaining them; -fusion reactor physics; -reactor concepts; and -fusion technologies. The journal has a dedicated Associate Editor for inertial confinement fusion.
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