Abstract
AbstractTokamak Energy has developed a liquid metal experiment featuring a lithium loop that circulates lithium through the HIDRA stellarator at the University of Illinois at Urbana-Champaign. The loop includes a replaceable divertor module, designed to demonstrate fast, steady, open-surface liquid metal flow. The first-generation divertor module was deliberately kept simple—an open-surface chute—to enable modelling validation and establish a benchmark for future design iterations. This paper presents the theoretical foundations of the experimental design. Specifically, we identify module overflooding as the primary challenge and determine the limits of fluid velocity and magnetic field strength necessary to prevent it. The steady-state flow patterns are expected to exhibit relatively slow surface velocities, which do not fully align with the fast-flow concept. Nevertheless, the experiment is designed to achieve controllable, continuous open-surface flow within an operational fusion device, representing a significant step toward the development of liquid metal divertor technology.
| Original language | English (US) |
|---|---|
| Article number | 115760 |
| Journal | Fusion Engineering and Design |
| Volume | 228 |
| DOIs | |
| State | Published - Jul 2026 |
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- General Materials Science
- Nuclear Energy and Engineering
- Mechanical Engineering
Keywords
- Experiment
- Fast flow concept
- Fusion device
- Liquid lithium
- Liquid metal divertor
- Modelling
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