Controlled movement of lower strike points by applying a divertor coil on the EAST tokamak
Source abstract
Abstract
A new in-vessel water-cooled coil has been placed below the lower tungsten-covered divertor in EAST, aiming at moving the strike points in the divertor and spreading the heat flow on the targets. To achieve controlled movement of the strike points by the plasma control system (PCS) when applying the in-vessel coil, the plasma equilibrium configurations are predicted by the tokamak equilibrium (TEQ) code. The divertor coil current is involved in these calculations. The shape control parameters in the PCS are adjusted according to the predesigned equilibria from the TEQ code. The strike point movement over a wide range has been achieved in the experiment while keeping the main plasma stable. Thus, this method for divertor strike point movement with the assistance of the divertor coil is feasible.
Source: crossref · Quality: baseline
Research context
OpenAlex topics: Magnetic confinement fusion research · Fusion materials and technologies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
Affiliations
Institute of Plasma Physics, Chinese Academy of Sciences 1 , Hefei 230031, China
University of Science and Technology of China 2 , Hefei 230026, China
Funding
National Natural Science Foundation of China
References (20)
Show source-provided references
1. Why fusion? A discussion of energy alternatives10.1109/MCS.2006.1615271 ↗
2. Plasma facing components for the Experimental Advanced Superconducting Tokamak and CFETR10.1088/0031-8949/2014/t159/014001 ↗
3. Radiative divertor behavior and physics in Ar seeded plasma on EAST10.1088/1674-1056/26/9/095205 ↗
4. Taming the plasma-material interface with the ‘snowflake’ divertor in NSTX10.1088/0029-5515/51/1/012001 ↗
5. Super-X divertors and high power density fusion devices10.1063/1.3110984 ↗
6. High power neon seeded JET discharges: Experiments and simulations10.1016/j.nme.2016.10.012 ↗
7. Sweeping heat flux loads on divertor targets: Thermal benefits and structural impacts10.1016/j.fusengdes.2015.11.026 ↗
8. Limitations of transient power load on DEMO and analysis of mitigation techniques10.1016/j.fusengdes.2016.01.023 ↗
9. Mitigation of divertor heat loads by strike point sweeping in high power JET discharges10.1088/1402-4896/aa8db1 ↗
10. Implications of recent DIII-D experiments on plasma shaping for future tokamak designs10.13182/fst01-a11963357 ↗
11. The divertor program in stellarators10.1088/0741-3335/44/11/306 ↗
12. Study on divertor plasma behavior through sweeping strike point in new lower divertor on EAST10.1088/1674-1056/ac4a65 ↗
13. Simulations of Ar seeding by SOLPS-ITER for a slot-type divertor concept10.1063/1.5133832 ↗
14. Physics design of lower tungsten divertor for long-pulse high-power operation in EAST10.1088/1741-4326/ac3297 ↗
15. Plasma current, position and shape feedback control on EAST10.1088/0029-5515/53/4/043009 ↗
16. Control of plasma poloidal shape and position in the DIII-D tokamak
17. A model-based strike point sweeping technique applied to JET10.1088/0741-3335/46/9/003 ↗
18. 1994
19. 1997
20. Time parallelization of advanced operation scenario simulations of ITER plasma10.1088/1742-6596/410/1/012032 ↗