Thermal analysis of the forced cooled conductor for the TF (toroidal field) superconducting coils in the TIBER II ETR design

Conference · Thu Jun 11 00:00:00 EDT 1987

OSTI ID:6158126

Kerns, J A; Slack, D S; Miller, J R

The Tokamak Ignition/Burn Experimental Reactor (TIBER) is being designed to provide nuclear testing capabilities for first wall and blanket design concepts. The baseline design for TIBER II is to provide steady-state nuclear burn capabilities. These objectives must be met using reactor relevant components, such as state-of-the-art current drive schemes coupled with superconducting toroidal field (TF) and poloidal field (PF) coils. The design is also constrained to be cost effective, which forces the machine to be as small as possible. This last constraint limits the nuclear shielding in TIBER. Therefore, the TF coils will have a high nuclear heat load of up to 4.5 kW per coil. The cooling scheme and the thermal analysis for this design are presented.

• Research Organization: Lawrence Livermore National Lab., CA (USA)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 6158126
• Report Number(s): UCRL-96001; CONF-8706125-5; ON: DE87011922
• Resource Relation: Conference: Cryogenic engineering conference, St. Charles, IL, USA, 14 Jun 1987; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
SUPERCONDUCTING MAGNETS
COOLING SYSTEMS
DESIGN
TIBER-X TOKAMAK
HEAT TRANSFER
HELIUM
NIOBIUM
THEORETICAL DATA
TIN
DATA
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
EQUIPMENT
FLUIDS
GASES
INFORMATION
MAGNETS
METALS
NONMETALS
NUMERICAL DATA
RARE GASES
SUPERCONDUCTING DEVICES
TRANSITION ELEMENTS
700202* - Fusion Power Plant Technology- Magnet Coils & Fields