STUDIES OF METHODS FOR SEALING ENDS OF REACTOR FUEL RODS FOR PWR
As part of the Westinghouse Atomic Power Division program for developing fuel rods for Pressurized Water Reactor, methods for sealing the ends of Zircaloy- 2-clad uranium-12 wt.% molybdenum-cored fuel rods made by coextrusion were investigated. Attempts were made to join Zircaloy-2 end plugs to the rod by means of pressure bonding, resistance welding, and fusion welding. Exploratory tests indicated that resistance upset welding was promising. Tension-test fractures occurred in the Zircaloy-2 end caps away from the weld joint when materials were vacuum-treated prior to upset welding. Percussion welding and flash welding were eliminated from extensive consideration because molten-core alloy was extruded out along the cladding-to-end-cap bond line when these processes were used. Attempts to fusion weld an overlay on the ends of the fuel rods resulted in end seals that had uranium at the surface and also contained gas porosity. (auth)
- Research Organization:
- Battelle Memorial Inst., Columbus, Ohio
- NSA Number:
- NSA-14-025910
- OSTI ID:
- 4126427
- Journal Information:
- Welding J.(N.Y.), Journal Name: Welding J.(N.Y.) Vol. Vol: 39
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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