Study of Passively Stable, Fully-Detached Divertor Plasma Regimes Attained in Innovative Long-Legged Divertor Configurations
Creators
- 1. Lawrence Livermore National Laboratory (LLNL), Livermore, CA 94550 (United States)
- 2. Plasma Science & Fusion Center, MIT, Cambridge, MA 02139 (United States)
- 3. York Plasma Institute, University of York, Heslington (United Kingdom)
Description
Full text: Passively-stable fully detached divertor regimes have been found in numerical modelling of divertor configurations with radially or vertically extended, tightly baffled, outer divertor legs, with or without a secondary X-point in the leg volume. Simulations carried out with the tokamak edge transport code UEDGE using the base parameters of the ADX tokamak design show that long-legged divertors provide up to an order-of-magnitude increase in the peak power-handling capability compared to conventional divertors, and a fully detached plasma state can be passively maintained over a wide range of parameters. In the simulations, the radial transport in the scrape-off layer is set to reproduce profiles observed in the experiment, which includes "shoulders" indicative of main-chamber recycling phenomena. In the UEDGE model used here, strong radial transport is assumed to occur in the outer divertor leg as well, leading to plasma predominantly recycling on the divertor leg outer sidewall. Analysis of simulations shows that the detachment front location is set by the balance between the power entering the divertor leg and the losses to the walls of the divertor channel. Therefore, for a fixed level of power exhaust, the location of the detachment front is insensitive to the divertor leg length—as long as the leg length exceeds the front location. The key physics for attaining the passively stable, fully detached regime involves an interplay of strong convective plasma transport to the divertor leg outer sidewall, confinement of neutral gas in the divertor volume, geometric effects possibly including a secondary X-point, and atomic radiation. In response to variation of model assumptions (magnitude of anomalous radial transport, impurity radiation, neutral transport model, geometry of plasma-facing components), the overall divertor plasma behaviour remains qualitatively similar: a stable fully detached regime is maintained, lending confidence in the modelling results. Work supported by U.S. Department of Energy contract DE-AC52-07NA27344 and cooperative agreement DE-SC0014264. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- 27th IAEA Fusion Energy Conference. Programme and Book of Abstracts
- Imprint Pagination
- 844 p.
- Journal Page Range
- p. 435
- Report number
- IAEA-CN--258
Conference
- Title
- 27. IAEA Fusion Energy Conference
- Acronym
- FEC 2018
- Dates
- 22-27 Oct 2018
- Place
- Ahmedabad (India)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50055493
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DIVERTORS; FIRST WALL; PEAK LOAD; PLASMA SCRAPE-OFF LAYER; SIMULATION; TOKAMAK DEVICES; TRANSPORT THEORY
- Descriptors DEC
- BOUNDARY LAYERS; CLOSED PLASMA DEVICES; LAYERS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS
Optional Information
- Contract/Grant/Project number
- Contract DE-AC52-07NA27344; DE-SC0014264
- Notes
- 4 refs.
- Secondary number(s)
- IAEA-CN--258-183