Application of HTSC coils for mitigation of VDE during a major disruption
Creators
- 1. Tokyo Univ. (Japan). Nuclear Engineering Research Lab., Graduate School of Engineering
- 2. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Description
The authors proposed the new method to control plasma position passively with use of high Tc superconducting coils (HTSCs). HTSCs are robust against the thermal disturbance, so that they can be installed in the vicinity of plasmas. In this study, we examine that the VDEs during disruptions can be mitigated or not by using HTSC coils as a stabilizer. Shape and profile of plasmas will change considerably during a disruption, so that the linearized model cannot be applied to this problem. Tokamak Simulation Code (TSC) is employed to evaluate the stabilizing effect of HTSC during a major disruption. The configuration of International Thermonuclear Experimental Reactor (ITER) is taken as an example for numerical analyses. The result of simulations using linear model agreed with that of TSC computation. The results of the simulation show that VDEs during disruptions are mitigated due to the stabilizing effect of HTSC. The vertical instability growth rate is improved if HTSC coils are installed on the backplate. The electromagnetic forces on HTSCs during a disruption were also estimated. A design to accommodate these forces is possible without any difficulty. (author)
Additional details
Publishing Information
- Publisher
- Association Euratom-CEA Cadarache
- Imprint Place
- Saint-Paul-Lez-Durance (France)
- Imprint Title
- Fusion technology 1998
- Imprint Pagination
- (v.1-2) 1744 p.
- Journal Page Range
- p. 599-602
Conference
- Title
- 20. symposium on fusion technology
- Dates
- 7-11 Sep 1998
- Place
- Marseille (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 31007999
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTROL SYSTEMS; ITER TOKAMAK; PLASMA DISRUPTION; PLASMA INSTABILITY; PLASMA SIMULATION; SUPERCONDUCTING COILS
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; INSTABILITY; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- 4 refs.