Design study for a graphite-moderated gas-cooled reactor using partially enriched uranium
Conference
·
OSTI ID:4294847
Prepared for the Second U. N. International Conference on the Peaceful Uses of Atomic Energy, 1958. A summary is presented of the research and development aspects of the U. S. program for graphite-moderated, gas-cooled reactors using partially enriched uranium. The availability of helium and enriched uranium in the United States presents a large degree of design freedom. On the basis of the study, it is concluded that such a reactor will produce power cheaper than a reactor using natural uranium. At the present time gas-cooled reactors are technologically and economically competitive with the best available pressurized-water reactors. (J.S.R.)
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- NSA Number:
- NSA-13-005932
- OSTI ID:
- 4294847
- Report Number(s):
- A/CONF.15/P/450
- Country of Publication:
- United States
- Language:
- English
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