Nuclear heat source component design considerations for HTGR process heat reactor plant concept

Conference · Sun Aug 01 04:00:00 EDT 1982 · Proc., Intersoc. Energy Convers. Eng. Conf.; (United States)

OSTI ID:5281964

McDonald, C F; Kapich, D; King, J H; Venkatesh, M C

Using alternate energy sources abundant in the U.S.A. to help curb foreign oil imports is vitally important from both national security and economic standpoints. Perhaps the most forwardlooking opportunity to realize national energy goals involves the integrated use of two energy sources that have an established technology base in the U.S.A., namely nuclear energy and coal. The coupling of a high-temperature gas-cooled reactor (HTGR) and a chemical process facility has the potential for long-term synthetic fuel production (i.e., oil, gasoline, aviation fuel, hydrogen, etc.) using coal as the carbon source. Studies are in progress to exploit the high-temperature capability of an advanced HTGR variant for nuclear process heat. The process heat plant discussed in this paper has a 1170-MW(t) reactor as the heat source and the concept is based on indirect reforming, i.e., the high-temperature nuclear thermal energy is transported (via an intermediate heat exchanger (IHX)) to the externally located process plant by a secondary helium transport loop. Emphasis is placed on design considerations for the major nuclear heat source (NHS) components, and discussions are presented for the reactor core, prestressed concrete reactor vessel (PCRV), rotating machinery, and heat exchangers.

• Research Organization: General Atomic Company, San Diego, CA
• DOE Contract Number: AT03-76SF70046
• OSTI ID: 5281964
• Report Number(s): CONF-820814-
• Conference Information: Journal Name: Proc., Intersoc. Energy Convers. Eng. Conf.; (United States) Journal Volume: 1
• Country of Publication: United States
• Language: English

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