Assessment of very high-temperature reactors in process application. Appendix I. Evaluation of the reactor system

Technical Report · Wed Dec 01 04:00:00 EST 1976

DOI:https://doi.org/10.2172/7231328· OSTI ID:7231328

Jones, Jr., J. E.; Spiewak, I.

In April 1974, the U.S. Atomic Energy Commission (now the Energy Research and Development Administration (ERDA)) authorized General Atomic Company, General Electric Company, and Westinghouse Electric Corp., Astronuclear Laboratory, to assess the available technology for producing heat using very high-temperature nuclear reactors. An evaulation of these studies and of the technical and economic potential of very high-temperature reactors (VHTR) is presented. The VHTR is a helium-cooled graphite-moderated reactor. The concepts and technology are evaluated for producing process stream temperatures of 649, 760, 871, 982, and 1093/sup 0/C (1200, 1400, 1600, 1800, and 2000/sup 0/F). There are a number of large industrial process heat applications that could utilize the VHTR.

• Research Organization: Oak Ridge National Lab., Tenn. (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 7231328
• Report Number(s): ORNL/TM-5409
• 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)
COST
FEASIBILITY STUDIES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
PROCESS HEAT REACTORS
REACTORS
RECOMMENDATIONS