Fusion-reactor blanket and coolant material compatibility

Conference · Thu Jan 01 00:00:00 EST 1981

OSTI ID:6208052

Jeppson, D W; Keough, R F

Fusion reactor blanket and coolant compatibility tests are being conducted to aid in the selection and design of safe blanket and coolant systems for future fusion reactors. Results of scoping compatibility tests to date are reported for blanket material and water interactions at near operating temperatures. These tests indicate the quantitative hydrogen release, the maximum temperature and pressures produced and the rates of interactions for selected blanket materials.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC14-76FF02170
• OSTI ID: 6208052
• Report Number(s): HEDL-SA-2355-FP; CONF-810831-56; ON: DE81030018; TRN: 81-017822
• 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
ALUMINIUM OXIDES
COMPATIBILITY
BREEDING BLANKETS
HELIUM
LEAD ALLOYS
LITHIUM ALLOYS
LITHIUM OXIDES
LITHIUM SILICATES
WATER
ZIRCONIUM OXIDES
COOLANTS
EXPERIMENTAL DATA
GRAPHS
MATERIALS TESTING
ALKALI METAL COMPOUNDS
ALLOYS
ALUMINIUM COMPOUNDS
CHALCOGENIDES
DATA
ELEMENTS
FLUIDS
GASES
HYDROGEN COMPOUNDS
INFORMATION
LITHIUM COMPOUNDS
NONMETALS
NUMERICAL DATA
OXIDES
OXYGEN COMPOUNDS
RARE GASES
REACTOR COMPONENTS
SILICATES
SILICON COMPOUNDS
TESTING
TRANSITION ELEMENT COMPOUNDS
ZIRCONIUM COMPOUNDS
700201* - Fusion Power Plant Technology- Blanket Engineering
700209 - Fusion Power Plant Technology- Component Development & Materials Testing
360205 - Ceramics
Cermets
& Refractories- Corrosion & Erosion