Fusion reactor breeder material safety compatibility studies

Journal Article · Thu Sep 01 04:00:00 EDT 1983 · Nucl. Technol./Fusion; (United States)

OSTI ID:6185900

Jeppson, D W; Cohen, S; Muhlestein, L D

Tritium breeder material selection for fusion reactors is strongly influenced by the desire to minimize safety and environmental concerns. Breeder material safety compatibility studies are being conducted to identify and characterize breeder-coolant-material interactions under postulated reactor accident conditions. Recently completed scoping compatibility tests indicate the following. 1. Ternary oxides (LiAlO/sub 2/, Li/sub 2/ZrO/sub 3/, Li/sub 2/SiO/sub 3/, Li/sub 4/SiO/sub 4/, and LiTiO/sub 3/) at postulated blanket operating temperatures are chemically compatible with water coolant, while liquid lithium and Li/sub 7/Pb/sub 2/ reactions with water generate heat, aerosol, and hydrogen. 2. Lithium oxide and 17Li-83Pb alloy react mildly with water requiring special precautions to control hydrogen release. 3. Liquid lithium reacts substantially, while 17Li83Pb alloy reacts mildly with concrete to produce hydrogen. 4. Liquid lithium-air reactions may present some major safety concerns. Additional scoping tests are needed, but the ternary oxides, lithium oxide, and 17Li-83Pb have definite safety advantages over liquid lithium and Li/sub 7/Pb/sub 2/. The ternary oxides present minimal safetyrelated problems when used with water as coolant, air or concrete; but they do require neutron multipliers, which may have safety compatibility concerns with surrounding materials. The combined favorable neutronics and minor safety compatibility concerns of lithium oxide and 17Li-83Pb make them prime candidates as breeder materials. Current safety efforts are directed toward assessing the compatibility of lithium oxide and the lithium-lead alloy with coolants and other materials.

• Research Organization: Westinghouse Hanford Company, Richland, Washington
• OSTI ID: 6185900
• Journal Information: Nucl. Technol./Fusion; (United States), Journal Name: Nucl. Technol./Fusion; (United States) Vol. 4:2 PT 1; ISSN NTFUD
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
AIR
ALKALI METAL COMPOUNDS
ALKALI METALS
ALLOYS
ALUMINATES
ALUMINIUM COMPOUNDS
BREEDING BLANKETS
CHEMICAL COMPOSITION
COMPARATIVE EVALUATIONS
COMPATIBILITY
COOLANTS
ELEMENTS
FLUIDS
GASES
HYDROGEN
HYDROGEN COMPOUNDS
LEAD ALLOYS
LIQUID METALS
LIQUIDS
LITHIUM
LITHIUM ALLOYS
LITHIUM COMPOUNDS
MATERIALS
MATERIALS TESTING
METALS
NONMETALS
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTOR SAFETY
SAFETY
SILICATES
SILICON COMPOUNDS
TESTING
THERMONUCLEAR REACTOR MATERIALS
TITANATES
TITANIUM COMPOUNDS
TRANSITION ELEMENT COMPOUNDS
WATER
ZIRCONATES
ZIRCONIUM COMPOUNDS