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Extra info for Waterside Corrosion of Zr Alloys in Nuclear Powerplants (IAEA TECDOC-996)
Sample text
5%Nb. 7000' ison iDUo 3000 1000 5000 BDOO 7000 Exposure Time, hours FIG. 18. Corrosion of zirconium alloy with 1% niobium in water and superheated steam at various temperatures [68]. 8000 CORROSION OF H E A T - T R E A T E D Z r - 2 5%Nb(Bg) IN 200-300'C ( 4 7 3 - 5 7 3 K ) WATER 200 QUENCH * 24h/500°c ANNEAL 100 - ___ QUENCH + 30%CW + 24h/500°C ANNEAL 09bO°C(1233K) Q] POINTS MARK >ONSET OF O X I D E D860°C(1133K) QJspflLL|NG UHEN CLOSED Z r - 2 . 5 w t . 0 JL 10 100 1000 TIME (days) FIG. 19. 5%Nb (batch Bg) in 200-300° C (473-573K) water [70].
Ellingham diagram of thermodynamics ofZr/O and other relevant systems [44]. , H kg/mm1 o 1000 o 400 hours at 850°C + 450 hours at 750°C u •go> •f. 00 o <& 3 500 s <5 +o 200 400 600 « Xmicrons FIG. 2. Variation in the microhardness as a function of depth of penetration of oxygen in zirconium (50 g. load) [26]. 38 3 20 c< Atoms/cm x 10 •(29Ar %) 150 o> o to •c 3). The fraction of the oxygen that dissolves depends upon a balance between the kinetics of oxide growth and the kinetics of oxygen diffusion into the metal. Since dissolution in the metal seems to vary much less from alloy to alloy than the oxide growth kinetics, rapidly oxidising alloys should have shallower diffusion profiles than more slowly oxidising alloys at all temperatures. At temperatures close to reactor operating temperatures, however, the ability to measure these diffusion profiles is very limited.