Investigation of the corrosion resistance of fuel micropellet cladding made of silicon carbide and pyrolytic carbon for the operating conditions of light-water reactors in nuclear power plants

The results of experimental and theoretical investigations of the corrosion of outer protective coatings, made of silicon carbide and pyrolytic carbon, of fuel microspherules in high-pressure water and water vapor in the range 350–950°C are presented. The tests lasted for times ranging from 300 to 11800 h were conducted for the operating conditions of light-water reactors.