The sodium hydroxide reactor :effect of reactor variables on criticality and fuel-element temperature requirements for subsonic and supersonic aircraft nuclear propulsion

Bogart, Donald., Valerino, Michael F.
naca-rm-e52i19
1953


Results are presented of two-group criticality calculations made for sodium-hydroxide-cooled, moderated, and reflected reactors for various concentrations and compositions of reactor fuel-element structural material. These specific criticality results are presented in a generalized manner to permit rapid evaluation of the criticality requirements for a wide range of other structural material compositions and concentrations which may be of interest from considerations of corrosion, strength, and heat-transfer-surface requirements.

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