
The Effect of Chr ect of Chromium Coatings on Hy omium Coatings on Hydrogen Uptak ogen Uptake in Zirconium Alloy Nuclear Fuel Cladding
₩4,000
The amount of hydrogen in a nuclear reactor can have a profound impact on its performance and safety when it is absorbed into or released from fuel rods. Hydrogen pickup in modern fuel cladding materials has been minimized by alloying additions and microstructural texture engineering, but these materials are still susceptible to hydrogen release during high temperature oxidation. The nuclear accident at the Fukushima Daiichi power plant in 2011 resulted in hydrogen gas production and subsequent explosions which led the United States Department of Energy to initiate a program to develop enhanced nuclear fuel cladding materials. New cladding materials include chromium (Cr) coatings applied to the outer surface of traditional zirconium-alloy fuel cladding.





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