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Jack_O
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Few things I'm curious about regarding zirconium use in reactors. I know at high temperatures it can release hydrogen from water by forming zirconium oxide. But:
http://en.wikipedia.org/wiki/Zircaloy"
this suggests that once a surface layer is formed no more oxidation can take place, judging by the events at Fukishima there is a mechanism for oxidation to continue, otherwise there would not have been so much hydrogen released. Can anyone elaborate?
It seems oxidation becomes a serious issue around 800-1000C in a water environment, does anyone know what temperature would lead to problems for zirconium/zircaloy in a CO2 rich environment, for example in an AGR?
wiki said:Zirconium alloys readily react with oxygen, forming a nanometer-thin passivation layer.
...
A sub-micrometer thin layer of zirconium dioxide is rapidly formed in the surface and stops the further diffusion of oxygen to the bulk and the subsequent oxidation.
http://en.wikipedia.org/wiki/Zircaloy"
this suggests that once a surface layer is formed no more oxidation can take place, judging by the events at Fukishima there is a mechanism for oxidation to continue, otherwise there would not have been so much hydrogen released. Can anyone elaborate?
It seems oxidation becomes a serious issue around 800-1000C in a water environment, does anyone know what temperature would lead to problems for zirconium/zircaloy in a CO2 rich environment, for example in an AGR?
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