Tritium control in helium-cooled blankets

Conference · Sun Sep 01 04:00:00 EDT 1985 · Fusion Technol.; (United States)

OSTI ID:5761127

Wong, C P.C.; Kessel, C; Maya, I; Roelant, D; Schultz, K R

As a part of the Blanket Comparison and Selection Study (BCSS), GA Technologies was responsible for the design of helium-cooled, solidand liquid-metal breeder blankets. Conceptual blanket designs were developed, including the consideration of the generation, transport, and extraction of tritium. Evaluations were made of the inventory and leakage of tritium for helium-cooled Li/sub 2/O and LiA10/sub 2/ and liquid lithium breeder blankets for tokamak and tandem mirror reactors. To facilitate the evaluation, a solid breeder tritium code TRIT4 was developed.

• Research Organization: GA Technologies Inc., San Diego, CA
• OSTI ID: 5761127
• Report Number(s): CONF-850405-
• Conference Information: Journal Name: Fusion Technol.; (United States) Journal Volume: 8:2
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METAL COMPOUNDS
ALUMINIUM COMPOUNDS
ALUMINIUM OXIDES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
CHALCOGENIDES
COMPUTERIZED SIMULATION
CONTROL
DIFFUSION
ELEMENTS
EXTRACTION
FLUIDS
GASES
HELIUM
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LIQUID METALS
LIQUIDS
LITHIUM COMPOUNDS
LITHIUM OXIDES
MAGNETIC MIRROR TYPE REACTORS
MATERIALS
MATERIALS TESTING
METALS
NONMETALS
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
RADIOISOTOPES
RARE GASES
REACTOR COMPONENTS
RECOVERY
SEPARATION PROCESSES
SIMULATION
TESTING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
TMR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
TRITIUM RECOVERY
YEARS LIVING RADIOISOTOPES