Abstract
Nodular corrosion on the surface of Zircaloy-2 fuel cladding tubes was investigated and the effects of irradiation time, linear heat rate, and fast neutron flux on the nucleation and growth of nodules were statistically studied. The nucleation and growth rate of nodules were found to decrease with irradiation time. Then, the nodular corrosion resistance of neutron irradiated Zircaloy-2 was examined in an out-of-pile corrosion test, and neutron irradiation was seemed to improve the Zircaloy-2 nodular corrosion resistance. Finally, microstructural evolution of Zircaloy-2 during neutron irradiation was investigated and radiation-induced dissolution of inter-metallic precipitates was confirmed. It was proposed that an increase of the dissolved alloying element concentration should improve the nodular corrosion resistance of Zircaloy-2 and re- strain the nucleation and growth of nodules on Zircaloy-2 fuel cladding tubes during irradiation in BWRs.
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