Self-cooled liquid-metal blanket concept
A blanket concept for the Next European Torus (NET) where 83Pb-17Li serves both as breeder material and as coolant is described. The concept is based on the use of novel flow channel inserts for a decisive reduction of the magnetohydrodynamic (MHD) pressure drop and employs beryllium as neutron multiplier in order to avoid the need for breeding blankets at the inboard side of the torus. This study includes the design, neutronics, thermal hydraulics, stresses, MHDs, corrosion, tritium recovery, and safety of a self-cooled liquid-metal blanket. The results of the investigations indicate that the self-cooled blanket is an attractive alternative to other driver blanket concepts for NET and that it can be extrapolated to the conditions of a DEMO reactor.
- Research Organization:
- Kernforschungszentrum Karlsruhe GmbH, Karlsruhe (DE); NIS Ingenieurgesellschaft mbH, Hanau (DE)
- OSTI ID:
- 6244604
- Journal Information:
- Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 14:3; ISSN FUSTE
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALINE EARTH METALS
BERYLLIUM
BREEDING BLANKETS
CHEMICAL REACTIONS
COOLANT LOOPS
COOLING SYSTEMS
CORROSION
DESIGN
ELEMENTS
ENERGY SYSTEMS
FLUID MECHANICS
HYDRODYNAMICS
LEAD
LIQUID METAL COOLED REACTORS
LITHIUM COOLED REACTORS
MAGNETOHYDRODYNAMICS
MATERIALS TESTING
MECHANICS
METALS
MHD CHANNELS
NET TOKAMAK
NEUTRON SOURCES
PARTICLE SOURCES
PRESSURE DROP
RADIATION SOURCES
REACTOR COMPONENTS
REACTORS
RECOVERY
SAFETY
STRESSES
TESTING
THERMAL STRESSES
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM RECOVERY