Published October 16, 2018 | Version v1
Report

Study of Passively Stable, Fully-Detached Divertor Plasma Regimes Attained in Innovative Long-Legged Divertor Configurations

  • 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)

Part of:
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts

Additional details

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