Polycrystalline Diamond Coating Protects Zr Cladding Surface Against Corrosion in Water-Cooled Nuclear Reactors: Nuclear Fuel Durability Enhancement
Author:
Affiliation:
1. Institute of Physics of the Czech Academy of Sciences; Prague Czech Republic
2. Czech Technical University; Prague Czech Republic
Publisher
John Wiley & Sons, Inc.
Link
http://onlinelibrary.wiley.com/wol1/doi/10.1002/9781119407652.ch5/fullpdf
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