Conceptual design of the INTOR first wall system
Conference
·
· Proc. Symp. Eng. Probl. Fusion Res.; (United States)
OSTI ID:6360289
The design concept and performance characteristics of the first wall design for the phase-1 INTOR (International Tokamak Reactor) study is described. The reference design consists of a water-cooled stainless steel panel. The major uncertainty regarding the performance of the bare stainless steel wall relates to the response of a thin melt layer predicted to form on limited regions during a plasma disruption. A more complex backup design, which incorporates radiatively cooled graphite tiles on the inboard wall, is briefly described.
- Research Organization:
- Argonne Natl Lab, IL, USA
- OSTI ID:
- 6360289
- Report Number(s):
- CONF-811040-
- Journal Information:
- Proc. Symp. Eng. Probl. Fusion Res.; (United States), Journal Name: Proc. Symp. Eng. Probl. Fusion Res.; (United States); ISSN PSERD
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
DESIGN
FIRST WALL
INTOR TOKAMAK
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
PERFORMANCE
STAINLESS STEELS
STEELS
TESTING
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
360103 -- Metals & Alloys-- Mechanical Properties
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
DESIGN
FIRST WALL
INTOR TOKAMAK
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
PERFORMANCE
STAINLESS STEELS
STEELS
TESTING
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS