Engineering design of a direct-cycle steam-generating blanket for a long-pulse fusion reactor
A comprehensive neutronics, thermohydraulic, and mechanical design of a tritium-breeding blanket for use by a conceptual long-pulse Reversed-Field Pinch Reactor (RFPR) is described. On the basis of constraints imposed by cost and the desire to use existing technology, a direct-cycle steam system and stainless-steel construction were used. For reasons of plasma stability, the RFPR blanket supports a 20-mm-thick copper first wall. Located behind the 1.5-m-radius first wall is a 0.50-m-thick stainless-steel blanket containing a granular bed of Li/sub 2/O through which flows low-pressure helium (0.1 MPa) for tritium extraction. Water/steam tubes radially penetrate this packed bed. The large thermal capacity and low thermal diffusivity of the Li/sub 2/O blanket are sufficient to maintain a nearly constant temperature during the approx. 25-s burn period (approx. 80% duty factor).
- Research Organization:
- Los Alamos Scientific Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5983897
- Report Number(s):
- LA-UR-79-808; CONF-790802-5
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700200* -- Fusion Energy-- Fusion Power Plant Technology
ALKALI METAL COMPOUNDS
BARYON REACTIONS
BOILERS
BREEDING BLANKETS
CHALCOGENIDES
COOLING SYSTEMS
DESIGN
FIRST WALL
FLUID MECHANICS
HADRON REACTIONS
HYDRAULICS
LITHIUM COMPOUNDS
LITHIUM OXIDES
MECHANICS
NEUTRON REACTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
OXIDES
OXYGEN COMPOUNDS
PINCH EFFECT
POWER PLANTS
REACTOR COMPONENTS
REVERSE-FIELD PINCH
SPECIFICATIONS
STEAM GENERATORS
THERMODYNAMICS
THERMONUCLEAR POWER PLANTS
THERMONUCLEAR REACTOR WALLS
VAPOR GENERATORS