Abstract
The Supercritical Water Cooled Reactor (SCWR) is one of the Generation IV reactor types, which has improved safety and economics, compared to the present fleet of pressurized water reactors. For nuclear applications, most of the traditional materials used for power plants are not applicable, therefore new types of materials have to be developed. For this purpose corrosion tests were designed and performed in a supercritical pressure autoclave in order to get data for the design of an in-pile high temperature and high-pressure corrosion loop. Here, we are presenting some results, related to corrosion resistance of some potential structural and fuel cladding materials.
Highlights
The Supercritical Water Cooled Reactor (SCWR) is one of the Generation IV reactor types, selected by Generation IV International Forum (GIF) for its improved safety and economics
Most of the traditional materials used for power plants are not applicable, new types of materials have to be developed
For this purpose corrosion tests were designed and performed in a supercritical pressure autoclave in order to get data for the design of an in-pile high temperature and high-pressure corrosion loop
Summary
The Supercritical Water Cooled Reactor (SCWR) is one of the Generation IV reactor types, selected by Generation IV International Forum (GIF) for its improved safety and economics. For this purpose corrosion tests were designed and performed in a supercritical pressure autoclave in order to get data for the design of an in-pile high temperature and high-pressure corrosion loop. We are presenting some results, related to corrosion resistance of some potential structural and fuel cladding materials.
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