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Critical experiments and nuclear safety at Oak Ridge National Laboratory

A study of problems associated with release of fission products from ceramic fuels in gas-cooled reactors

Operational safety of the ORNL graphite reactor using enriched-uranium fuel

Published Year

• 1950-1959 (2)
• 1960-1969 (1)

Subject

• Nuclear fuel elements (3) *
• Nuclear reactors--Safety measures (3) *
• Diffusion (1)
• Fission products (1)
• Gas cooled reactors (1)
• Nuclear reactors--Reactivity (1)
• Radioactive decontamination (1)
• Reactor fuel reprocessing--Safety measures (1)
• Uranium (1)

Author

• Callihan, A. D. (1)
• Jaye, S. (1)
• Kasten, P. R. (1)
• Lane, J. A. (1)
• Lietzke, M. P. (1)

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