Robert J. Fetterman - Murrysville PA, US James A. Sparrow - Irmo SC, US
Assignee:
Westinghouse Electric Co LLC - Pittsburgh PA
International Classification:
G21C 7/00
US Classification:
376327, 376333, 376339
Abstract:
An advanced gray rod control assembly (GRCA) is for a nuclear reactor. The reactor has a plurality of fuel assemblies each including numerous elongated fuel rods supported in an organized array by substantially transverse support grids, and a plurality of guide thimbles disposed through the support grids and along the fuel rods. The GRCA includes a spider assembly structured to provide controlled insertion of gray rod assemblies within the thimbles of the fuel assembly, thereby controlling the rate of power produced by the reactor. Each gray rod assembly includes an elongated tubular member, a first end plug, a second end plug, a substantially pure silver neutron-absorber disposed within the tubular member, and a support tube surrounding the neutron-absorber within the tubular member to resist silver-swelling. Delta-power of the reactor is improved by minimizing the exposed surface area of the absorber and distributing it among all of the rods of the GRCA.
A pressurized water nuclear reactor fuel assembly designed to burn mixed oxide fuel that employs a fully annular fuel pellet stack in the fuel rods, and radial enrichment zoning within the assembly such that the intra-assembly rod power distribution is relatively smooth regardless of the characteristics of the adjacent assemblies.
- Cranberry Township PA, US ROBERT J. FETTERMAN - GIBSONIA PA, US JEFFREY L. BRADFUTE - IRMO SC, US
Assignee:
WESTINGHOUSE ELECTRIC COMPANY LLC - CRANBERRY TOWNSHIP PA
International Classification:
G21C 19/20 G21C 3/326 G21C 1/08
Abstract:
An advanced initial core fuel configuration is for improving the fuel management efficiency and thus economics for a nuclear reactor. The advanced initial core fuel configuration includes a plurality of fuel assemblies having different average enrichments of uranium 235 and arranging the fuel assemblies in an initial core configuration structured to emulate a known equilibrium reload cycle core at least in terms of spatial reactivity distribution. The resulting average enrichment within the initial core ranges from below about 1.0 percent weight of uranium 235 to about 5.0 percent weight of uranium 235. An advanced lattice design is also disclosed.
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