Development of tritium breeding blankets for DT-burning fusion reactors

Conference · Mon Dec 31 23:00:00 EST 1979

OSTI ID:6377863

Clemmer, R G

This study examines the status of understanding of blanket tritium recovery and the performance of potentially viable tritium breeding materials under conditions anticipated in a DT-fueled fusion reactor environment. The existing physicochemical, thermophysical, and ceramographic data for candidate liquid and solid breeders are reviewed and appropriate operating conditions defined. It is shown that selection of a breeding material and an appropriate tritium recovery method can impose significant constraints upon blanket design, particularly when considerations of breeder/coolant/structure compatibility and temperature limitations are taken into account.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6377863
• Report Number(s): CONF-801011-92; ON: DE81023904
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ALKALI METALS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING RATIO
CONVERSION RATIO
DESIGN
DEUTERIUM
ELEMENTS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LITHIUM
METALS
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
RECOVERY
STABLE ISOTOPES
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
TRITIUM RECOVERY
YEARS LIVING RADIOISOTOPES