用于优化欧盟 DEMO 送料机隔热罩的热分析模型

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-09-03 DOI:10.1016/j.fusengdes.2024.114650
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引用次数: 0

摘要

本工作旨在通过探索来自不同来源(包括真空管道、安全壳管道和热屏蔽上的低温氦气管)的辐射和传导所产生的温度分布,确定 DEMO EU CFT 的馈源热屏蔽的初步设计。为了获得这些结果,首先制作了数值有限元表示法并对其进行了参数化。为了减轻这种复杂和高度非线性解决方案的负担,还创建了一个分析模型,并与数值模型进行了验证,结果非常好。计算了若干参数对隔热箱温度分布和安全壳管道热流的敏感性,从而找到了隔热箱的候选配置。为了完成这项研究,还实施了基于梯度下降的演化优化,以了解冷却 He 管线圆周定位的影响。
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An analytical thermal model for the optimization of EU DEMO feeder thermal shields

The present work aims at defining a first design of the DEMO EU’s feeder thermal shield for the CFT, by exploring the temperature distribution resulting from radiation and conduction coming from different sources including the vacuum duct, the containment duct and the cryogenic He lines on the thermal shield. In order to achieve these results, at first a numerical FEM representation was produced and parameterized. To ease the burden of such a complex and highly non-linear solution, an analytical model however was created and validated against the numerical one with very good results. The sensitivity of several parameters was computed with respect to the temperature distribution of the thermal shield and the heat flow to the containment duct, finding a candidate configuration for the thermal shield. To complete the study, an evolutive optimization based on gradient descent was implemented to understand the influence of the circumferential positioning of the cooling He lines.

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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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