Pool boiling helium heat transfer from two large monolithic copper stabilizers

Conference · Thu Jan 01 04:00:00 EST 1981 · Proc. Symp. Eng. Probl. Fusion Res.; (United States)

OSTI ID:6230714

Peck, S D; Christensen, E H

The heat transfer performance of two large, monolith, pool-boiling conductors designed for 12 Tesla service in Tokamak field coils has been measured in simulated vertical-axis conductor packs. The surface heat flux of a shallow, rectangular-grooved conductor was 15% lower than that of a simple rectangular conductor in temperature regimes of cryostability interest. However, the wetted surface area enhancement provides overall heat transfer for the grooved surface of about 2.1 times that of the flat surface. The data for the conductors away from the magnet wall agrees closely with design analysis predictions for both conductors and verifies their predicted cryostability performance. Effects on cryostability performance of two insulation systems made by molding processes and incorporated with these two conductors have also been determined.

• Research Organization: Gen Dyn, San Diego, CA, USA
• OSTI ID: 6230714
• Report Number(s): CONF-811040-
• Conference Information: Journal Name: Proc. Symp. Eng. Probl. Fusion Res.; (United States)
• Country of Publication: United States
• Language: English

Related Subjects

420201 -- Engineering-- Cryogenic Equipment & Devices
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
71 CLASSICAL AND QUANTUM MECHANICS
GENERAL PHYSICS
BOILING
COPPER
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
ELEMENTS
ENERGY TRANSFER
EQUIPMENT
HEAT TRANSFER
MAGNETS
METALS
PHASE TRANSFORMATIONS
POOL BOILING
SUPERCONDUCTING COILS
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRANSITION ELEMENTS