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Description and Some Safeguard Aspects of Proposed Developmental Fast Neutron Breeder Reactor
Report that generally describes sodium cooled fast reactors, the features and facilities of such a reactor proposed by Atomic Power Development Associates, and then its safety and siting considerations.
Date:
July 25, 1955
Creator:
Atomic Power Development Associates
System:
The UNT Digital Library
Fast Reactor Fuel Cycle Costs and Temperature Coefficients of Reactivity for PuO2-SS and PuO2-UO2
Report comparing the fuel cycle costs and temperature coefficients of reactivity for PuO2-UO2 fuel in multiple megawatt reactors.
Date:
April 25, 1963
Creator:
Edwards, J. J.; Fischer, E. A.; Jens, W. H.; Nims, J. B.; Palmer, R. G.; Shoudy, A. A. et al.
System:
The UNT Digital Library