Demonstration Tokamak Hybrid Reactor (DTHR) blanket design study, December 1978

Technical Report · Sun Jan 01 00:00:00 EST 1978

DOI:https://doi.org/10.2172/5810770· OSTI ID:5810770

This work represents only the second iteration of the conceptual design of a DTHR blanket; consequently, a number of issues important to a detailed blanket design have not yet been evaluated. The most critical issues identified are those of two-phase flow maldistribution, flow instabilities, flow stratification for horizontal radial inflow of boiling water, fuel rod vibrations, corrosion of clad and structural materials by high quality steam, fretting and cyclic loads. Approaches to minimizing these problems are discussed and experimental testing with flow mock-ups is recommended. These implications on a commercial blanket design are discussed and critical data needs are identified.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA). Fusion Power Systems Dept.
• DOE Contract Number: EG-77-C-02-4544
• OSTI ID: 5810770
• Report Number(s): WFPS-TME-106; TRN: 79-021219
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
DESIGN
HYBRID REACTORS
TOKAMAK TYPE REACTORS
BOILING
COOLANTS
COOLING SYSTEMS
CORROSION
CORROSIVE EFFECTS
HEAT TRANSFER
MECHANICAL VIBRATIONS
PERFORMANCE TESTING
STEAM
THERMAL CYCLING
THORIUM OXIDES
WATER
ACTINIDE COMPOUNDS
CHALCOGENIDES
CHEMICAL REACTIONS
ENERGY TRANSFER
HYDROGEN COMPOUNDS
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
REACTOR COMPONENTS
TESTING
THERMONUCLEAR REACTORS
THORIUM COMPOUNDS
700201* - Fusion Power Plant Technology- Blanket Engineering