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Model to predict swelling, gas release, and densification in oxide fuels

Description: A model was developed to predict in-pile fission gas swelling, gas release, and densification in oxide fuels. This model considers fission gas behavior at the grain interior, on the grain boundaries, and at grain boundary edges under conditions of total gas bubble destruction by fission fragments and partial gas bubble destruction. When gas bubble swelling on grain edges reaches 5 percent, it is assumed that gas tunnels form along the edges. Gas release takes place by migration of the gas in th… more
Date: June 1, 1978
Creator: Dollins, C. C.
Partner: UNT Libraries Government Documents Department
open access

Integral testing of thorium and U233 data for thermal reactors

Description: A survey is made of integral experiments useful for testing thorium and /sup 233/U nuclear data in thermal reactor applications. Emphasis is on homogeneous /sup 233/U--H/sub 2/O criticals and simple, water-moderated /sup 233/U--thorium and /sup 235/U--thorium lattice experiments. Thorium--/sup 233/U-graphite experiments are also discussed briefly. Although the available experiments provide a fairly consistent test of important nuclear data, their accuracy and scope leave much to be desired. In … more
Date: June 1, 1979
Creator: Hardy, J., Jr.; Ullo, J.J. & Steen, N.M.
Partner: UNT Libraries Government Documents Department
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