High-temperature process heat applications with an HTGR

Conference · Tue Apr 01 00:00:00 EST 1980

OSTI ID:5225705

Quade, R. N.; Vrable, D. L.

An 842-MW(t) HTGR-process heat (HTGR-PH) design and several synfuels and energy transport processes to which it could be coupled are described. As in other HTGR designs, the HTGR-PH has its entire primary coolant system contained in a prestressed concrete reactor vessel (PCRV) which provides the necessary biological shielding and pressure containment. The high-temperature nuclear thermal energy is transported to the externally located process plant by a secondary helium transport loop. With a capability to produce hot helium in the secondary loop at 800/sup 0/C (1472/sup 0/F) with current designs and 900/sup 0/C (1652/sup 0/F) with advanced designs, a large number of process heat applications are potentially available. Studies have been performed for coal liquefaction and gasification using nuclear heat.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• DOE Contract Number: AT03-76SF71061
• OSTI ID: 5225705
• Report Number(s): GA-A-15868; CONF-800578-1; TRN: 80-013529
• Resource Relation: Conference: Conference on the utilization of small and medium size power reactors in Latin America, Montevideo, Uruguay, 12 May 1980
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
THERMOCHEMICAL PROCESSES
PROCESS HEAT REACTORS
FEASIBILITY STUDIES
CHEMICAL INDUSTRY
COAL GASIFICATION
HYDROGEN PRODUCTION
OIL SHALE PROCESSING PLANTS
PROCESS HEAT
SPECIFICATIONS
ENERGY
GAS COOLED REACTORS
GASIFICATION
GRAPHITE MODERATED REACTORS
HEAT
INDUSTRIAL PLANTS
INDUSTRY
REACTORS
210900* - Nuclear Power Plants- Process Heat Reactors- (-1987)
210300 - Power Reactors
Nonbreeding
Graphite Moderated