HTGR nuclear heat source component design and experience

Conference · Sat May 01 04:00:00 EDT 1982

OSTI ID:5061063

Peinado, C. O.; Wunderlich, R. G.; Simon, W. A.

The high-temperature gas-cooled reactor (HTGR) nuclear heat source components have been under design and development since the mid-1950's. Two power plants have been designed, constructed, and operated: the Peach Bottom Atomic Power Station and the Fort St. Vrain Nuclear Generating Station. Recently, development has focused on the primary system components for a 2240-MW(t) steam cycle HTGR capable of generating about 900 MW(e) electric power or alternately producing high-grade steam and cogenerating electric power. These components include the steam generators, core auxiliary heat exchangers, primary and auxiliary circulators, reactor internals, and thermal barrier system. A discussion of the design and operating experience of these components is included.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• DOE Contract Number: AT03-76SF70046
• OSTI ID: 5061063
• Report Number(s): GA-A-16746; CONF-820915-2; ON: DE82016250
• Country of Publication: United States
• Language: English

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