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Operation of the Sodium Technology Loop for Contamination Meter Evaluations
Report issued by the APDA over studies conducted on the Sodium Technology Loop. Methods, equipment, and results of the studies are presented and discussed. This report includes tables, illustrations, and photographs.
Date:
March 25, 1964
Creator:
unknown
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
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