A molten salt cooling 17Li-83Pb breeding blanket concept
Conference
·
· Fusion Technol.; (United States)
OSTI ID:5794010
A description of a fusion breeding blanket concept using draw salt coolant and static 17Li-83Pb is presented. 17Li-83Pb has high breeding capability and low tritium solubility. Draw salt operates at low pressure and is inert to water. Corrosion, MHD, and tritium containment problems associated with the MARS design are alleviated because of the use of a static LiPb blanket. Blanket tritium recovery is by permeation toward the plasma. A direct contact steam generator is proposed to eliminate some generic problems associated with a tube shell steam generator.
- Research Organization:
- Fusion Power Program, Argonne National Laboratory, Argonne, IL
- OSTI ID:
- 5794010
- Report Number(s):
- CONF-850310-
- Journal Information:
- Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 8:1; ISSN FUSTE
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BOILERS
BREEDING BLANKETS
CONTAINMENT
COOLANTS
CORROSION PROTECTION
DESIGN
DIRECT CONTACT HEAT EXCHANGERS
HEAT EXCHANGERS
LEAD ALLOYS
LEAD BASE ALLOYS
LITHIUM ALLOYS
MAGNETIC MIRROR TYPE REACTORS
MARS REACTOR
MOLTEN SALTS
REACTOR COMPONENTS
RECOVERY
SALTS
STEAM GENERATORS
THERMONUCLEAR REACTORS
TRITIUM RECOVERY
VAPOR GENERATORS
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BOILERS
BREEDING BLANKETS
CONTAINMENT
COOLANTS
CORROSION PROTECTION
DESIGN
DIRECT CONTACT HEAT EXCHANGERS
HEAT EXCHANGERS
LEAD ALLOYS
LEAD BASE ALLOYS
LITHIUM ALLOYS
MAGNETIC MIRROR TYPE REACTORS
MARS REACTOR
MOLTEN SALTS
REACTOR COMPONENTS
RECOVERY
SALTS
STEAM GENERATORS
THERMONUCLEAR REACTORS
TRITIUM RECOVERY
VAPOR GENERATORS