Technology assessment of the Gas-Turbine-High Temperature Gas-Cooled (helium) Reactor. Interim report
This report, which examines the Gas Turbine-High Temperature Gas-Cooled Reactor (GT-HTGR), derives from related technology assessments initiated in 1976. Those EPRI assessments, which were intended as companions to government-funded reactor commercialization studies, addressed the technical adequacy of a specific steam-cycle HTGR design. The same approach has been utilized herein except as limited by the more conceptual nature of the GT-HTGR. The GT-HTGR has historically been viewed as an international program deriving from U.S. graphite-helium reactor technology and European closed cycle turbomachinery development. In concept the program has been remarkably stable, but schedules and specific designs have been subject to continuing modification largely as a result of changes in national energy policies. The specific purposes of this report are (a) to provide a brief review of the recent international background of the project and (b) to discuss the open issues and technical risks which appeared evident in the technical literature available through 1977. The chronology of GT-HTGR development in both the United States and Europe through 1977 is summarized. A detailed reporting of technical evaluations and verification analyses performed is included.
- Research Organization:
- NUS Corp., Rockville, MD (USA)
- OSTI ID:
- 6669988
- Report Number(s):
- EPRI-NP-805; TRN: 78-018706
- Country of Publication:
- United States
- Language:
- English
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