Assessment of very high-temperature reactors in process application. Appendix I. Evaluation of the reactor system [electronic resource].
- Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1976. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 164 : digital, PDF file
- Additional Creators:
- Oak Ridge National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- 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.
- Published through SciTech Connect., 12/01/1976., "ornl/tm-5409", and Spiewak, I.; Jones, J.E. Jr.
- Funding Information:
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