
doi: 10.2172/10136824
The projects undertaken were to address two areas of concern for metal-fueled fast reactors: metallurgical compatibility of fuel and its fission products with the stainless steel cladding, and effects of porosity development in the fuel on fuel/cladding interactions and on sodium penetration in fuel. The following studies are reported on extensively in appendices: hot isostatic pressing of U-10Zr by coupled boundary diffusion/power law creep cavitation, liquid Na intrusion into porous U-10Zr fuel alloy by differential capillarity, interdiffusion between U-Zr fuel and selected Fe-Ni-Cr alloys, interdiffusion between U-Zr fuel vs selected cladding steels, and interdiffusion of Ce in Fe-base alloys with Ni or Cr.
Progress Report, Grain Boundaries, Ifr Reactor, Sodium Cooled Reactors, Uranium Base Alloys, Porous Materials, Breeding, 21 Specific Nuclear Reactors And Associated Plants, Diffusion, Power Reactors, Hot Pressing, Fission Products, Alloy Nuclear Fuels, Liquid Metals, Zirconium Alloys, Sodium 210500, Fuel-Cladding Interactions
Progress Report, Grain Boundaries, Ifr Reactor, Sodium Cooled Reactors, Uranium Base Alloys, Porous Materials, Breeding, 21 Specific Nuclear Reactors And Associated Plants, Diffusion, Power Reactors, Hot Pressing, Fission Products, Alloy Nuclear Fuels, Liquid Metals, Zirconium Alloys, Sodium 210500, Fuel-Cladding Interactions
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