Comparative Study of PuC-UC and PuO₂-UO₂ as Fast Reactor Fuel (open access)

Comparative Study of PuC-UC and PuO₂-UO₂ as Fast Reactor Fuel

From abstract: "This section, Part II, extends the comparison of two ceramic fuel systems to include the fuel cycle cost comparison in greater detail particularly with respect to fabrication and reprocessing unit costs."
Date: November 15, 1962
Creator: Collins, G. D.
System: The UNT Digital Library
Experimental Studies of Transient Effects in Fast Reactor Fuels (open access)

Experimental Studies of Transient Effects in Fast Reactor Fuels

An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO₂ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel.
Date: November 15, 1962
Creator: Field, J. H.
System: The UNT Digital Library