A shinethrough detector and interlock for neutral beam injection operations on MAST-U

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

Fusion Engineering and Design Pub Date : 2025-09-05 DOI:10.1016/j.fusengdes.2025.115408

Roy McAdams, Philippe Jacquet, Ian Day, Effy Rose, Andrew Ash, Jake Ashton, Hana El-Haroun, Paul Jepson, David Keeling, Damian King, Robert King, Stephen Marsden, Alistair McShee, Maria Nicassio, Dean Payne, Robert Proudfoot, Ridhima Sharma, Jamie Smith, Christopher Tame, Thomas Wilson

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引用次数: 0

Abstract

Neutral Beam Injection (NBI) is a powerful tool and is very commonly used for heating, current drive and diagnostics on magnetically confined devices for fusion power development. Not all the neutral beam power is deposited within the plasma. This shinethrough power must be dealt with at the first wall and any components irradiated by it must be protected against excessive heating. This paper describes the design, implementation and testing of a shinethrough detector and interlock for the MAST-U machine. It is based on the detection of the infra-red emission from the beam dump which can then be used to terminate the beam pulse if this exceeds a required threshold. The effects on the detected signal of loosely bound material (“dust”) on the beam dump is also discussed.

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用于mat - u中性束注入操作的穿透探测器和联锁

中性束注入（NBI）是一种强大的工具，通常用于核聚变动力发展中磁约束装置的加热、电流驱动和诊断。并不是所有的中性光束能量都沉积在等离子体中。这种穿透功率必须在第一堵墙上处理，任何被它照射的部件都必须防止过热。本文介绍了一种用于MAST-U机器的透光检测器和联锁装置的设计、实现和测试。它基于对光束转储的红外发射的检测，如果这超过所需的阈值，则可以使用它来终止光束脉冲。本文还讨论了松散束缚物质（“尘埃”）在束流上对探测信号的影响。

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.