Engineering considerations for optical diagnostics of European DEMO

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
I. Katona , D. Dunai
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引用次数: 0

Abstract

Optical diagnostics measurements were identified as necessary for plasma control in the initial concept for the plasma diagnostic and control (D&C) system of European DEMO. The protection of the first mirror is identified as a critical subject for future large sized fusion devices. Radio Frequency Plasma Discharge mirror cleaning solutions proposed for ITER have been discarded for fusion power plant environment. Erosion and deposition processes can be mitigated by neutral gas between the aperture and the front mirror. Currently 3 optical diagnostics are being developed for EU-DEMO. The Divertor Monitoring Diagnostic had the highest priority thus that was selected for conceptual development. Three optomechanical layout configurations were analyzed, with the optimal candidate further refined for improved integration and performance. The design emphasized the optical duct geometry, revealing that a shorter duct simplifies mechanical integration. Preliminary Monte Carlo N-Particle (MCNP) neutronics simulations estimated the diagnostic module's nuclear load, providing key insights for further refinement. This iterative workflow enables systematic optimization of the optical and mechanical structure to meet stakeholder requirements, yielding a robust, integrated diagnostic module design. The methodology offers a transferable framework for other optical diagnostics under development for EU-DEMO and future fusion power plants.
欧洲DEMO光学诊断的工程考虑
在欧洲DEMO等离子体诊断和控制(D&;C)系统的初始概念中,光学诊断测量被确定为等离子体控制的必要条件。第一反射镜的保护被认为是未来大型核聚变装置的关键问题。针对ITER提出的射频等离子体放电镜面清洗方案已被核聚变电站环境所抛弃。孔径和前镜之间的中性气体可以减轻侵蚀和沉积过程。目前正在为EU-DEMO开发3种光学诊断。转向器监测诊断具有最高的优先级,因此被选择用于概念开发。分析了三种光机械布局形式,并进一步优化了最优候选方案,以提高集成度和性能。设计强调了光学导管的几何形状,揭示了较短的导管简化了机械集成。初步的蒙特卡罗n粒子(MCNP)中子模拟估计了诊断模块的核负荷,为进一步改进提供了关键的见解。这种迭代的工作流程能够系统地优化光学和机械结构,以满足利益相关者的要求,从而产生一个强大的集成诊断模块设计。该方法为EU-DEMO和未来聚变发电厂正在开发的其他光学诊断提供了一个可转移的框架。
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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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