This metallurgical study of Zr-barrier fuel cladding evaluates the importance of three salient attributes: (1) metallurgical bond between the zirconium liner and the Zircaloy substrate, (2) liner thickness (roughly 10% of the total cladding wall), and (3) softness (purity). The effect that each of these attributes has on the pellet-cladding interaction (PCI) resistance of the Zr-barrier fuel was studied by a combination of analytical model calculations and laboratory experiments using an expanding mandrel technique. Each of the attributes is shown to contribute to PCI resistance.
The effect of the zirconium liner on fuel behavior during off-normal events in which steam comes in contact with the zirconium surface was studied experimentally. Simulations of loss-of-coolant accident (LOCA) showed that the behavior of Zr-barrier cladding is virtually indistinguishable from that of conventional Zircaloy cladding. If steam contacts the zirconium liner surface through a cladding perforation and the fuel rod is operated under normal power conditions, the zirconium liner is oxidized more rapidly than is Zircaloy, but the oxidation rate returns to the rate of Zircaloy oxidation when the oxide phase reaches the zirconium-Zircaloy metallurgical bond.
Author Information
Rosenbaum, HS
Nuclear Energy Business Operations, General Electric Company, San Jose, CA
Rand, RA
Nuclear Energy Business Operations, General Electric Company, San Jose, CA
Tucker, RP
Nuclear Energy Business Operations, General Electric Company, Vallectios Nuclear Center, Pleasanton, CA
Cheng, B
Nuclear Energy Business Operations, General Electric Company, Vallectios Nuclear Center, Pleasanton, CA
Adamson, RB
Nuclear Energy Business Operations, General Electric Company, Vallectios Nuclear Center, Pleasanton, CA
Davies, JH
Nuclear Energy Business Operations, General Electric Company, San Jose, CA
Armijo, JS
General Electric Company, Sunnyvale, CA
Wisner, SB
Nuclear Energy Business Operations, General Electric Company, Vallectios Nuclear Center, Pleasanton, CA
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