HTGR nuclear heat source component design and experience

Conference · Sat May 01 00:00:00 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; TRN: 82-018773
• Resource Relation: Conference: BNES international conference on gas cooled reactors today, Bristol, UK, 20 Sep 1982; Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR INTERNALS
SPECIFICATIONS
PROCESS HEAT REACTORS
COGENERATION
REACTOR COMPONENTS
COOLING SYSTEMS
DEUS
ENERGY SYSTEMS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
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