Fabrication and Test of a 60-kA HTS Current Lead for Fusion Magnet System
Creators
- 1. Naka Fusion Research Establishment, Japan Atomic Energy Research Institute, Naka-machi, Ibaraki, 311-0193 (Japan)
- 2. Fuji Electric Co. Ltd., 1-1 Tanabeshinden, Kawasaki-ku, Kawasaki-shi, Kanagawa, 210-8530 (Japan)
Description
A 60-kA HTS current lead was fabricated and tested in the frame of the R and D work for large fusion magnets such as the ITER magnet. The design of the current lead was characterized by its safe thermal protection for the current decay of about ten seconds after quench as well as lower electrical power consumption for its cryogenic equipment. The 60-kA current lead is composed of a lower temperature HTS part using HTS and a high temperature copper part using a conventional copper cable. The HTS part consists of 48 HTS units installed in the cylindrical array into the grooves provided on the outer surface of a stainless steel cylinder with a diameter of 146 mm. The unit was composed of six Bi2223/Ag-10at%Au tapes and its cross-sectional dimension is 6.5 mm x 2.7 mm. The stainless steel cylinder and Ag alloy sheath have a share in thermal protection for quench. The current lead was tested under the cooling condition that the bottom of the HTS part was immersed into 4.2 K liquid helium, and the bottom of the copper part was forced cooled with a helium gas of 3.2 g/s at 20 K. The lead was successfully operated at 60 kA without quench. Heat load to liquid helium was 4.8 W. The total electrical power consumption for the cryogenic equipment was estimated as 37 % of that of conventional copper current lead
Additional details
Identifiers
- DOI
- 10.1063/1.1774773;
Publishing Information
- Journal Title
- AIP Conference Proceedings
- Journal Volume
- 710
- Journal Issue
- 1
- Journal Page Range
- p. 929-936
- ISSN
- 0094-243X
- CODEN
- APCPCS
Conference
- Title
- Cryogenic engineering and international cryogenic materials conference on advances in cryogenic engineering
- Acronym
- CEC 2003
- Dates
- 22-26 Sep 2003
- Place
- Anchorage, AK (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36092777
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BISMUTH; COOLING; COPPER; CRYOGENICS; CYLINDERS; CYLINDRICAL CONFIGURATION; FABRICATION; HEATING LOAD; HELIUM; HIGH-TC SUPERCONDUCTORS; ITER TOKAMAK; LIQUIDS; PLASMA CONFINEMENT; SAFETY; SILVER; STAINLESS STEELS; SUPERCONDUCTING CABLES; SUPERCONDUCTING MAGNETS; TEMPERATURE RANGE 0000-0013 K; TEMPERATURE RANGE 0013-0065 K
- Descriptors DEC
- ALLOYS; CABLES; CARBON ADDITIONS; CLOSED PLASMA DEVICES; CONDUCTOR DEVICES; CONFIGURATION; CONFINEMENT; ELECTRIC CABLES; ELECTRICAL EQUIPMENT; ELECTROMAGNETS; ELEMENTS; EQUIPMENT; FLUIDS; GASES; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MAGNETS; METALS; NONMETALS; RARE GASES; STEELS; SUPERCONDUCTING DEVICES; SUPERCONDUCTORS; TEMPERATURE RANGE; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; TYPE-II SUPERCONDUCTORS
Optional Information
- Notes
- (c) 2004 American Institute of Physics