Protective layers of zirconium alloys used for claddings to improve the corrosion resistance

Author:

Sartowska Bożena1ORCID,Starosta Wojciech1ORCID,Sokołowski Paweł2,Wawszczak Danuta1,Smolik Jerzy3ORCID

Affiliation:

1. Institute of Nuclear Chemistry and Technology , Dorodna 16 St. , Warsaw , Poland

2. Wrocław University of Science and Technology , Wrocław , Poland

3. Łukasiewicz Research Network – The Institute for Sustainable Technologies , Radom , Poland

Abstract

Abstract Zirconium alloys are used as a cladding material for fuel elements in nuclear reactors. In the case of severe accident conditions, the possible rapid oxidation of zirconium in steam or/and air may result in intense hydrogen generation and hydrogen–oxide mixture explosion. Advanced technologies for increasing the corrosion resistance of claddings are being investigated in two directions: (a) protective coatings on Zr alloys and (b) the use of new materials for claddings. Coatings with silicon may provide a more protective barrier than the ZrO2 films formed on an alloy cladding during nuclear plant operations. These coatings may also serve as a protective barrier during high-temperature accidents. The current work aimed at developing protective coatings with silicon on zirconium alloys. Multielemental Zr–Si–Cr coatings were formed on Zry-2 alloy using the physical vapor deposition (PVD) method. Long-term oxidation tests were carried out under the following conditions: 360°C/195 bar/63 days/water-simulating PWR water. Obtained results show the protective character of formed layers. The material in the form of silicon carbide grains covered with yttrium–aluminum garnet (SiC + YAG) was prepared using the sol–gel method. The formed powder is the main component for coating formation on Zr–1Nb alloy using the method of suspension plasma spraying (SPS).

Publisher

Walter de Gruyter GmbH

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