Kinetic Modelling of Tungsten Impurity Transport Using the IMPGYRO Code
Creators
- 1. Faculty of Science and Technology (Yagami Campus), Keio University, Yokohama (Japan)
- 2. International Thermonuclear Experimental Reactor (ITER), Cadarache Centre, 13108 Saint-Paul-lès-Durance (France)
- 3. Japan Atomic Energy Agency (JAEA), Naka (Japan)
Description
Full text: With the move in current and future fusion devices to all-metal walls, and particularly with tungsten (W) plasma-facing components, understanding heavy ion impurity transport processes in the scrape-off layer (SOL)/divertor region is becoming one of the most critical issues for tokamak operation. To improve this understanding, we are continuing to develop the kinetic SOL/divertor impurity transport code IMPGYRO(IG), which tracks the trajectory of impurity ions in the plasma, resolving their full gyro-orbits. For the W transport in the SOL/divertor region, the friction force, the thermal force, the E x B drift and the anomalous radial transport are traditionally regarded as the dominant factors. In addition to these, it has recently been pointed out that neoclassical transport processes can have non-negligible effects on transport in the SOL/divertor region. In this paper, we mainly focus on neoclassical transport processes associated with the parallel transport of W impurities in single null divertor configurations. We focus the IG simulations using a plasma background obtained with the SOLPS5.0 plasma boundary code suite on the magnetic equilibrium of the JT-60U pulse #49540. When the background plasma is in a high recycling state, the W particles have been pushed upstream by the strong thermal force and transported to the top region of the SOL due to the existence of a steep parallel temperature gradient in front of the divertor plate. The W particles then stagnate near the top of the SOL where the parallel thermal force and the friction force are in balance. The W impurities then penetrate into the main plasma due to the ∇B drift and curvature drifts, which are automatically taken into account in the IG modelling, causing a net inward perpendicular flux. In order to better understand the W penetration process, we compare the IG model to a simpler guiding centre model with an anomalous transport. We find that in general the IG radial velocities tend to be larger than those from the guiding centre model. As a consequence, localized impurities have a larger radial flux in the IG calculation. The results suggest that not only the anomalous diffusion but also the drifts, specifically the ∇B drift and the curvature drift, should be taken into account in order to correctly predict the W core accumulation. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- 26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material
- Imprint Pagination
- 935 p.
- Journal Page Range
- p. 644
- Report number
- IAEA-CN--234
Conference
- Title
- 26. IAEA Fusion Energy Conference
- Acronym
- FEC 2016
- Dates
- 17-22 Oct 2016
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50008515
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DIVERTORS; FIRST WALL; HEAVY IONS; JT-60U TOKAMAK; NEOCLASSICAL TRANSPORT THEORY; PLASMA SCRAPE-OFF LAYER; RADIAL VELOCITY; SIMULATION; TUNGSTEN
- Descriptors DEC
- BOUNDARY LAYERS; CHARGED PARTICLES; CHARGED-PARTICLE TRANSPORT THEORY; CLOSED PLASMA DEVICES; ELEMENTS; IONS; LAYERS; METALS; REFRACTORY METALS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TOKAMAK DEVICES; TRANSITION ELEMENTS; TRANSPORT THEORY; VELOCITY
Optional Information
- Notes
- Abstract only
- Secondary number(s)
- IAEA-CN--234-0618