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

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

OSTI ID:5334530

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

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 Co., San Diego, CA (USA)
• DOE Contract Number: AT03-76SF70046
• OSTI ID: 5334530
• Report Number(s): GA-A-16716; CONF-820814-13; ON: DE82016248
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
210900* -- Nuclear Power Plants-- Process Heat Reactors-- (-1987)
COGENERATION
DEUS
ENERGY SYSTEMS
FEASIBILITY STUDIES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
POWER GENERATION
PROCESS HEAT REACTORS
REACTORS
SPECIFICATIONS
STEAM GENERATION