Published May 10, 2002
| Version v1
Journal article
Cryogenic system for KSTAR Tokamak
- 1. National Fusion R and D Center, Korea Basic Science Institute, Daejeon 305-333 (Korea, Republic of)
Description
The Korea Superconducting Tokamak Advanced Research (KSTAR) Project has been in progress since 1996. Major parameters of the KSTAR tokamak are: major radius 1.8 m, minor radius 0.5 m, toroidal field 3.5 Tesla. The KSTAR device has a fully CICC type superconducting coil system. Cooling of the superconducting coil is forced cooling by supercritical helium using a low temperature SHE circulation system at 4.5 K. The total cold mass is around 380 tons and required cooling capacity is 10 kW in base-line operation mode and 12 kW in up-graded operation mode at 4.5 K
Additional details
Identifiers
- DOI
- 10.1063/1.1472004;
Publishing Information
- Journal Title
- AIP Conference Proceedings
- Journal Volume
- 613
- Journal Issue
- 1
- Journal Page Range
- p. 55-59
- ISSN
- 0094-243X
- CODEN
- APCPCS
Conference
- Title
- Cryogenic engineering and international cryogenic materials conference on advances in cryogenic engineering
- Acronym
- CEC/ICMC 2001
- Dates
- 16-20 Jul 2001
- Place
- Madison, WI (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35081803
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLING; CRYOGENICS; HELIUM; OPERATION; SUPERCONDUCTING COILS; TEMPERATURE RANGE 0000-0013 K; TOKAMAK DEVICES
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; ELEMENTS; EQUIPMENT; FLUIDS; GASES; NONMETALS; RARE GASES; TEMPERATURE RANGE; THERMONUCLEAR DEVICES
Optional Information
- Notes
- (c) 2002 American Institute of Physics.