Advances in Plasma-Wall Interaction Control for H-Mode Operation over 100 s with ITER-like Tungsten Divertor on EAST
Creators
- 1. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui (China)
Description
Full text: Managing excessively high divertor power and particle fluxes and related plasma-wall interactions (PWI) is one of the most critical issues for the steady-state operation of the EAST superconducting tokamak and future fusion devices, such as ITER and CFETR. A world record long pulse H-mode operation of 101.2 s with H98 = 1.1 and total power injection of 0.3 GJ has been successfully achieved in EAST with ITER-like top tungsten (W) divertor, which has steady-state power exhaust capability of 10MW/m2 . The peak temperature of the Wtarget of T ≈ 500°C and a heat flux ≈3MW/m2 was maintained stably. Great efforts have been made to simultaneously control peak heat flux and particle/impurity exhaust towards the long pulse of 100 s time scale. Particle exhaust was optimized by preferentially directing the plasma flow toward the outer target with the ion B x ∇B drift away from theWdivertor and improving divertor pumping with the top cryo-pump. Effective power dispersal was achieved by tailoring the 3D divertor plasma footprint using lower hybrid wave (LHW) through induced edge magnetic topology change and broadened plasma wetted area, thus reducing peak heat flux andWsputtering. Extensive lithium coating was employed to lower edge recycling, low-Z impurity content andWsputtering. In addition, divertor detachment in H-mode for PWI handling was achieved for the first time with a W divertor in EAST. Compared with previous L-mode in EAST, in H-mode the detachment has a higher density threshold with ne/nG ∼ 0.65. Active feedback control of radiative divertor with neon impurity seeding was successfully achieved with frad ∼ 18-36%, and a slight loss of plasma stored energy ∼ 7-11%, offering a promising technique for steady-state divertor radiation and heat flux control. The upgrade plan and status of EAST bottom divertor from graphite to water-cooledWto accommodate more challenging PWI for steady-state H-mode over 400 s and L-mode operation over 1000 s will also be presented. (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. 232
- 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
- 50050957
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- GRAPHITE; HEAT FLUX; H-MODE PLASMA CONFINEMENT; ITER TOKAMAK; LITHIUM; L-MODE PLASMA CONFINEMENT; LOWER HYBRID CURRENT DRIVE; LOWER HYBRID HEATING; NEON; PLASMA; PLASMA IMPURITIES; STEADY-STATE CONDITIONS; STORED ENERGY; TUNGSTEN; WALL EFFECTS
- Descriptors DEC
- ALKALI METALS; CARBON; CLOSED PLASMA DEVICES; CONFINEMENT; ELEMENTS; ENERGY; FLUIDS; GASES; HEATING; HIGH-FREQUENCY HEATING; IMPURITIES; MAGNETIC CONFINEMENT; METALS; MINERALS; NON-INDUCTIVE CURRENT DRIVE; NONMETALS; PHYSICAL PROPERTIES; PLASMA CONFINEMENT; PLASMA HEATING; RARE GASES; REFRACTORY METALS; THERMODYNAMIC PROPERTIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENTS
Optional Information
- Collaborations
- EAST Team
- Secondary number(s)
- IAEA-CN--258-336