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LWBR Development Program
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LWBR Development Program
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1980-1989
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LWBR Development Program
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Cladding corrosion and hydriding in irradiated defected zircaloy fuel rods
Determination of statistically based design limits associated with engineering models.
Model for incorporating fuel swelling and clad shrinkage effects in diffusion theory calculations
Design features of the Light Water Breeder Reactor (LWBR) which improve fuel utilization in light water reactors
Out-of-pile hydriding and thermal relaxation of reactor fasteners using Zircaloy components: the REM-120 test.
Shippingport operations with the Light Water Breeder Reactor core.
Internal hydriding in irradiated defected Zircaloy fuel rods: A review
Installation of the Light-Water Breeder Reactor at the Shippingport Atomic Power Station
End-of-life destructive examination of light water breeder reactor fuel rods
Summary of the hydraulic evaluation of LWBR
Water cooled breeder program summary report
Forces in bolted joints: analysis methods and test results utilized for nuclear core applications
Uranium-233 purification and conversion to stabilized ceramic grade urania for LWBR fuel fabrication
Development and control of the process for the manufacture of zircaloy-4 tubing for LWBR fuel rods
Nuclear analysis and performance of the Light Water Breeder Reactor (LWBR) core power operation at Shippingport
Summary of the thermal evaluation of LWBR
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