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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
open access

Three core concepts for producing uranium-233 in commercial pressurized light water reactors for possible use in water-cooled breeder reactors

Description: Selected prebreeder core concepts are described which could be backfit into a reference light water reactor similar to current commercial reactors, and produce uranium-233 for use in water-cooled breeder reactors. The prebreeder concepts were selected on the basis of minimizing fuel system development and reactor changes required to permit a backfit. The fuel assemblies for the prebreeder core concepts discussed would occupy the same space envelope as those in the reference core but contain a 1… more
Date: December 1, 1979
Creator: Conley, G. H.; Cowell, G. K.; Detrick, C. A.; Kusenko, J.; Johnson, E. G.; Dunyak, J. et al.
Partner: UNT Libraries Government Documents Department
open access

Critical heat flux tests with high pressure water in an internally heated annulus with alternating axial heat flux distribution

Description: Critical heat flux experiments were performed with an alternating heat flux profile in an internally heated annulus. The heated length was 84 inches with a square wave alternating heat flux profile over the last 12 inches having a maximum-to-average heat flux ratio of 1.76. Test data were obtained at pressures from 800 to 2000 psia, mass velocities from 0.25 x 10/sup 6/ to 2.8 x 10/sup 6/ lb/hr-ft/sup 2/ and inlet temperatures ranging from 400 to 600/sup 0/F. Two different electrically heated t… more
Date: September 1979
Creator: Beus, S. G. & Humphreys, D. A.
Partner: UNT Libraries Government Documents Department
open access

Fuel utilization potential in light water reactors with once-through fuel irradiation

Description: Current commercial light water reactor cores operate without recylce of fuel, on a once-through fuel cycle. To help conserve the limited nuclear fuel resources, there is interest in increasing the energy yield and, hence, fuel utilization from once-through fuel irradiation. This report evaluates the potential increase in fuel utilization of light water reactor cores operating on a once-through cycle assuming 0.2% enrichment plant tails assay. This evaluation is based on a large number of survey… more
Date: July 1, 1979
Creator: Rampolla, D. S.; Conley, G. H.; Candelore, N. R.; Cowell, G. K.; Estes, G. P.; Flanery, B. K. et al.
Partner: UNT Libraries Government Documents Department
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