Nuclear heat source design for an advanced HTGR process heat plant

Conference · Fri Apr 01 00:00:00 EST 1983

OSTI ID:6119093

McDonald, C F; O'Hanlon, T W

A high-temperature gas-cooled reactor (HTGR) coupled with a chemical process facility could produce synthetic fuels (i.e., oil, gasoline, aviation fuel, methanol, hydrogen, etc.) in the long term using low-grade carbon sources (e.g., coal, oil shale, etc.). The ultimate high-temperature capability of an advanced HTGR variant is being studied for nuclear process heat. This paper discusses a process heat plant with a 2240-MW(t) nuclear heat source, a reactor outlet temperature of 950/sup 0/C, and a direct reforming process. The nuclear heat source outputs principally hydrogen-rich synthesis gas that can be used as a feedstock for synthetic fuel production. This paper emphasizes the design of the nuclear heat source and discusses the major components and a deployment strategy to realize an advanced HTGR process heat plant concept.

• Research Organization: GA Technologies, Inc., San Diego, CA (USA)
• DOE Contract Number: AT03-76SF70046
• OSTI ID: 6119093
• Report Number(s): GA-A-17068; CONF-830812-6; ON: DE83012124
• Resource Relation: Conference: 18. intersociety energy conversion engineering conference, Orlando, FL, USA, 21 Aug 1983; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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SPECIFICATIONS
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