Nuclear Superheat Project. Internal Steam Separation Development of Radial Vane Steam Separators (open access)

Nuclear Superheat Project. Internal Steam Separation Development of Radial Vane Steam Separators

This technical report describes the development, design, operation, and performance of a full-circle, radial-vane steam separator for the boiling water section of a nuclear superheat reactor. Steam-water tests of this model have demonstrated that is has vane capacity in excess of that required for the 300-Mx(e) separate superheat reactor and for the 300-Mw mixed spectrum superheat reactor. It is proposed that the vane capacity requirement of the 600 Mw(e) separate superheat reactor may be attained by increasing the nozzle length.
Date: May 31, 1963
Creator: Moen, R. H.
System: The UNT Digital Library
EVESR Nuclear Superheat Fuel Development Project: First Quarterly Report, May 4-August 31, 1962 (open access)

EVESR Nuclear Superheat Fuel Development Project: First Quarterly Report, May 4-August 31, 1962

Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.
Date: January 31, 1963
Creator: Pennington, R. T.
System: The UNT Digital Library
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962 (open access)

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962

Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: January 31, 1963
Creator: Leitz, F. J.
System: The UNT Digital Library