HYFIRE II: fusion/high-temperature electrolysis conceptual-design study. Annual report

Technical Report · Mon Aug 01 00:00:00 EDT 1983

DOI:https://doi.org/10.2172/5530758· OSTI ID:5530758

Fillo, J A ^[1]

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1. ed.

As in the previous HYFIRE design study, the current study focuses on coupling a Tokamak fusion reactor with a high-temperature blanket to a High-Temperature Electrolyzer (HTE) process to produce hydrogen and oxygen. Scaling of the STARFIRE reactor to allow a blanket power to 6000 MW(th) is also assumed. The primary difference between the two studies is the maximum inlet steam temperature to the electrolyzer. This temperature is decreased from approx. 1300/sup 0/ to approx. 1150/sup 0/C, which is closer to the maximum projected temperature of the Westinghouse fuel cell design. The process flow conditions change but the basic design philosophy and approaches to process design remain the same as before. Westinghouse assisted in the study in the areas of systems design integration, plasma engineering, balance-of-plant design, and electrolyzer technology.

• Research Organization: Brookhaven National Lab. (BNL), Upton, NY (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5530758
• Report Number(s): BNL-33701; ON: DE84001475
• Resource Relation: Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
08 HYDROGEN
TOKAMAK TYPE REACTORS
DESIGN
HYDROGEN PRODUCTION
BREEDING BLANKETS
ELECTROLYSIS
OXYGEN
VERY HIGH TEMPERATURE
ELEMENTS
LYSIS
NONMETALS
REACTOR COMPONENTS
THERMONUCLEAR REACTORS
700200* - Fusion Energy- Fusion Power Plant Technology
080101 - Hydrogen- Production- Electrolysis