Hardness measurements are potentially valuable for a quantitative discussion of embrittlement in the inner portions of fuel cladding tubes. The size of the indentation, however, is not negligible compared to the measuring region, even when a micro Vickers hardness tester is employed. This limits the measuring technique, and very little has been studied about degradation phenomena in the inner portion of the tubes.A hardness measurement system, equipped with a depth-sensing indentation instrument, and the necessary post irradiation examination technique for specimens with high radioactivity were successfully developed and the following observations were obtained from the system's application example. The diffusion coefficient of oxygen obtained from the hardness of an unirradiated zirconium lined cladding with simulated oxidation in the fuel rod showed good agreement with literature data. The calculated diffusion coefficient from hardness in the inner portion of irradiated Zircaloy-2 fuel rods was almost the same value as that of unirradiated zirconium, which implied that neither neutron irradiation nor fission fragment bombardment enhanced the oxygen diffusion in the inner portion of cladding tube.
For improved Zircaloy-2 cladding tubes used in Japanese BWRs, α+β heat treatment is used on the outer surface of the tubeshell to suppress nodular corrosion. This treatment also provides superior uniform corrosion behavior up to 40 GWd/t. To investigate the effect of α+β heat treatment on corrosion behavior, the size distributions of second-phase particles in improved Zircaloy-2 cladding tubes and their changes during irradiation were observed and measured using an analytical transmission electron microscope. These cladding tubes were found to have smaller particles than previous ones. The dissolution rate of iron and nickel (Fe and Ni) was calculated as a function of particle size, chemical compositions of cladding tubes, and fast neutron flux. The relationship between corrosion behavior and the dissolution rate of Fe and Ni is described. Nodular corrosion occurred when the dissolution rate of Fe and Ni was slow.
Hardness measurements are potentially valuable for a quantitative discussion of embrittlement in the inner portions of fuel cladding tubes. The size of the indentation, however, is not negligible compared to the measuring region, even when a micro Vickers hardness tester is employed. This limits the measuring technique, and very little has been studied about degradation phenomena in the inner portion of the tubes. A hardness measurement system, equipped with a depth-sensing indentation instrument, and the necessary post irradiation examination technique for specimens with high radioactivity were successfully developed and the following observations were obtained from the system's application example. The diffusion coefficient of oxygen obtained from the hardness of an unirradiated zirconium lined cladding with simulated oxidation in the fuel rod showed good agreement with literature data. The calculated diffusion coefficient from hardness in the inner portion of irradiated Zircaloy-2 fuel rods was almost the same value as that of unirradiated zirconium, which implied that neither neutron irradiation nor fission fragment bombardment enhanced the oxygen diffusion in the inner portion of cladding tube.
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