基于 SOLPS 参数化热核实验堆堆芯边缘模型的岔道安全非线性燃烧控制

IF 3.5 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS
Vincent Graber and Eugenio Schuster
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引用次数: 0

摘要

就热核实验堆的运行而言,具有高聚变功率输出的理想燃烧等离子体状态的范围将受到各种运行制约因素的限制。这些制约因素包括热核实验堆各种加热和燃料驱动装置的饱和,如中性束注入器、离子和电子回旋加热系统、气体膨化系统和氘氚颗粒注入器。除了这些致动器限制外,H 模式功率阈值、岔流器分离以及岔流器目标上的热负荷也可能对热核实验堆的运行空间造成限制。在这项工作中,等离子体运行等值线(POPCON)图将上述限制映射到温度-密度空间,用于研究哪些限制对进入具有高聚变功率输出的状态最为不利。所展示的 POPCON 图基于面向控制的核心-边缘模型,该模型将核心-等离子体区域的非线性密度和能量响应模型与 SOLPS4.3 边缘-等离子体区域(刮除层和分流器)条件的参数化结合起来。利用这个以控制为导向的核心-边缘模型,本文构建了一个非线性燃烧控制器,旨在调节核心-等离子体区域的等离子体温度和密度。该控制器采用在线优化方案,对控制基准进行管理,从而引导等离子体进入高聚变功率状态,同时保护转发器目标免受危险的高热负荷。闭环模拟研究说明了这种燃烧控制方案的能力。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Divertor-safe nonlinear burn control based on a SOLPS parameterized core-edge model for ITER
For ITER operations, the range of desirable burning-plasma regimes with high fusion power output will be restricted by various operational constraints. These constraints include the saturation of ITER’s various heating and fueling actuators such as the neutral beam injectors, the ion and electron cyclotron heating systems, the gas puffing system, and the deuterium–tritium pellet injectors. In addition to these actuator constraints, the H-mode power threshold, divertor detachment, and the heat load on the divertor targets may apply limitations to ITER’s operational space. In this work, Plasma Operation Contour (POPCON) plots that map the aforementioned constraints to the temperature-density space are used to investigate which constraints are most limiting towards accessing regimes with high fusion power output. The presented POPCON plots are based on a control-oriented core-edge model that couples the nonlinear density and energy response models for the core-plasma region with SOLPS4.3 parameterizations for conditions in the edge-plasma regions (scrape-off-layer and divertor). Using this control-oriented core-edge model, a nonlinear burn controller, which aims to regulate the plasma temperature and density in the core-plasma region, is constructed in this work. This controller is augmented with an online optimization scheme that governs the control references such that the plasma can be guided towards regimes with high fusion powers while protecting the divertor targets from dangerously high heat loads. A closed-loop simulation study illustrates the capability of this burn control scheme.
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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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