Stabilizing long pulse D− extraction for NBI using a Cs shower

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
C. Wimmer, A. Döring, T. Fellinger, M. Fröschle, A. Heiler, D. Mussini, U. Fantz
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引用次数: 0

Abstract

The Neutral Beam Injection (NBI) system of ITER is based on sources for negative hydrogen ions (H & D). Negative ions are produced by surface conversion of plasma particles on low work function materials. Cs is steadily evaporated from an oven into the ion source for the reduction of the surface work function. The extraction of negative ions from the source plasma is accompanied by the co-extraction of electrons. In long pulses, the electron current is steadily increasing and thus limiting the source performance in particular in deuterium operation. Simulations and measurements give hints that the flux of Cs onto the plasma grid – the first grid of the extraction system and the most important conversion surface – decreases in long pulses.
In order to increase the flux of neutral Cs, a new version of a Cs shower is tested at the BATMAN Upgrade test facility. The Cs shower consists of a small tube containing a multitude of small orifices for directed evaporation of Cs very close to the convertor surface. This allowed for the first time a steady state with extremely stable performance in long deuterium pulses (1000 s, beam time limited by radiation restrictions). However, the evaporation from the Cs shower (measured by Tunable Diode Laser Absorption Spectroscopy) shows a strong vertical asymmetry. Measures for homogenizing the evaporation need to be adapted in a next step.
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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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