Conceptual design proposal for the EU-DEMO electron cyclotron ex-vessel waveguide system with enhanced remote maintainability

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-06-25 DOI:10.1016/j.fusengdes.2025.115267

Daniel Birlan , Gabriele Benzoni , William Brace , Alessandro Bruschi , Antonio Cammi , René Chavan , Fabien Crisinel , Oliver Crofts , Saul Garavaglia , Timothy P. Goodman , Jean-Philippe Hogge , Cinta Lucia Marraco Borderas , Avelino Mas Sanchez , Changyang Li , Janne Lyytinen , Hannu Martikainen , Aditya Sinha , Peter Spaeh , Marc Torrance , Anna Unt , Anastasia Xydou

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引用次数: 0

Abstract

The EUropean DEMOnstration power plant (EU-DEMO) project, a EUROfusion initiative, seeks to advance fusion power technology by developing a reliable Electron Cyclotron (EC) heating and current drive system capable of delivering up to 130 MW of auxiliary heating power presently through six equatorial ports. This paper introduces an innovative alternative to the baseline ex-vessel waveguide (EW) system design, which could be major for effective EC operations. The proposed design reduces vacuum-sealed interfaces significantly — from 173 to seven — minimizing failure points and reducing the need for extensive monitoring in confined port spaces. Enhanced for remote maintainability, the design simplifies maintenance tasks and mitigates vacuum breach risks. The vacuum dimple-plated casing, acting as the primary confinement boundary, ensures nuclear safety and enables integration with current infrastructure, while addressing challenges like dynamic loads and vessel movements to maintain structural integrity. These advancements indicate that the modular and sealless waveguide approach offers a more reliable, maintainable solution.

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具有增强远程可维护性的EU-DEMO电子回旋加速器容器外波导系统的概念设计方案

欧洲示范电厂（EU-DEMO）项目是欧洲核聚变的一项倡议，旨在通过开发可靠的电子回旋加速器（EC）加热和电流驱动系统来推进核聚变发电技术，该系统目前能够通过六个赤道端口提供高达130兆瓦的辅助加热功率。本文介绍了一种创新的替代基线船外波导（EW）系统设计，这可能是有效的EC操作的主要方法。所建议的设计显著减少了真空密封接口，从173个减少到7个，最大限度地减少了故障点，并减少了对密闭端口空间进行广泛监控的需要。增强了远程可维护性，简化了维护任务，降低了真空泄漏风险。真空压痕镀壳作为主要约束边界，确保核安全，并与现有基础设施相结合，同时应对动态载荷和容器运动等挑战，以保持结构完整性。这些进步表明，模块化和非密封波导方法提供了一个更可靠，可维护的解决方案。

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

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.