Neutral Beam Injection for a tokamak-based Volumetric Neutron Source

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-02-18 DOI:10.1016/j.fusengdes.2025.114870
C. Hopf , C. Bachmann , T. Fellinger , T. Franke , C. Gliss , T. Härtl , B. Heinemann , G. Orozco
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Abstract

Neutral Beam Injection (NBI) is an essential system of the Volumetric Neutron Source (VNS) currently studied by EUROfusion. The VNS is a medium-sized tokamak with a tritium plasma. Approximately 42 MW deuterium NBI provides heating, non-inductive current drive and fast ions for beam–target dominated fusion. The mission of the VNS is to test and qualify components such as breeding blankets in reactor-relevant conditions and exposure to high fluences of 14 MeV neutrons in continuous operation. Consistent with the size of the tokamak, the beam energy is around 120 keV, which can be achieved with the well-established technology of positive-ion-based NBI. However, no previously built NBI has been designed for continuous operation and in an environment with reactor-like neutron radiation, leading to numerous design challenges. The evolving conceptual design is based on ASDEX Upgrade’s well tested and reliable NBI injectors. Each injector beamline will have four beams from four individual sources that together provide 14MW NBI. Three injectors are foreseen to operate simultaneously while the cryo pumps in a fourth injector regenerate. All beamlets of each of the four beams intersect between the toroidal field magnets at the midplane, maximising transmission and limiting the duct cross section. The remote handling concept foresees that an entire injector box is removed from the torus on rails and replaced by a spare. Repair and maintenance is then carried out in an active maintenance facility (AMF) to keep VNS down-times short. Ion source high-voltage conditioning uses a calorimeter at the AMF, eliminating the need for a calorimeter in each injector box. The paper reviews the current state of the NBI concept with an emphasis on solutions to the challenges arising from continuous operation; space limitations, beamline length and reionisation; operation in a nuclear environment and remote handling.
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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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