Changes in near-surface microstructure of metallic limiters following one year of service in Doublet III

Conference · Sat Aug 01 00:00:00 EDT 1981

OSTI ID:6221056

Trester, P. W.; Sevier, D. L.; Sabado, M. M.

The structural alloys Ta-10W, Mo, and Inconel X-750 were used for plasma limiters during the 3-MW ohmic heating experiments of the Doublet III tokamak. Post-service examinations of these limiters are reviewed. Near-surface melting, cracking, and microstructural changes are shown and discussed. During III service, elements from other metallic components were transported by the plasma and deposited on the limiter surface; significantly, high concentrations of Ni, Fe, Mo, and C were detected in the regions found to be microcracked in the Ta-10W. Observations and analyses are made that are relevant to the design of limiter and armor components for larger tokamaks.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• DOE Contract Number: AT03-76ET51011
• OSTI ID: 6221056
• Report Number(s): GA-A-16429; CONF-810831-35; ON: DE81029487; TRN: 81-016433
• Resource Relation: Conference: Fusion reactor materials meeting, Seattle, WA, USA, 9 Aug 1981
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
36 MATERIALS SCIENCE
DOUBLET REACTORS
LIMITERS
INCONEL X750
MICROSTRUCTURE
MOLYBDENUM
TANTALUM ALLOYS
TUNGSTEN ALLOYS
CRACKS
MELTING
ALLOYS
CHROMIUM ALLOYS
CRYSTAL STRUCTURE
ELEMENTS
INCONEL ALLOYS
IRON ALLOYS
METALS
NICKEL ALLOYS
NICKEL BASE ALLOYS
PHASE TRANSFORMATIONS
REFRACTORY METALS
THERMONUCLEAR REACTORS
TITANIUM ALLOYS
TOKAMAK TYPE REACTORS
TRANSITION ELEMENTS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing
360106 - Metals & Alloys- Radiation Effects