Published 1998 | Version v1
Book

Application of HTSC coils for mitigation of VDE during a major disruption

  • 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)

Part of:
Fusion technology 1998

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.