Fuel Elements for Foreign Pool-Type Research Reactor
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
In accordance with the requests received, we submit the following comments and proposals on the current status of manufacturing methods for foreign pool-type, research-reactor fuel elements: Were it not for the specification that the uranium be limited in U-235 enrichment at 20% in foreign reactors, reliable technical information could be provided, since the fuel elements would probably be designed in accordance with MTR-type technology.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- OSTI ID:
- 1295616
- Report Number(s):
- CF--55-9-22
- Country of Publication:
- United States
- Language:
- English
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