Investigation of Corrosion Resistance of Alloys with Potential Application in Supercritical Water-cooled Nuclear Reactors

Authors

  • Ákos Horváth
    Affiliation

    Institute for Atomic Energy Research, MTA Centre for Energy Research, Hungarian Academy of Sciences, H-1525 Budapest, POB 49, Hungary

  • Attila R. Imre
    Affiliation

    Institute for Atomic Energy Research, MTA Centre for Energy Research, Hungarian Academy of Sciences, H-1525 Budapest, POB 49, Hungary; Department of Energy Engineering, Faculty of Mechanical Engineering, Budapest University of Technology and Economics, H-1111 Budapest, Műegyetem rkp. 3., Hungary

  • György Jákli
    Affiliation

    Department of Energy Engineering, Faculty of Mechanical Engineering, Budapest University of Technology and Economics, H-1111 Budapest, Műegyetem rkp. 3., Hungary

https://doi.org/10.3311/PPch.12923

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.

Keywords:

high pressure, steel corrosion, supercritical water

Published Online

2019-02-25

How to Cite

Horváth, Ákos, Imre, A. R., Jákli, G. “Investigation of Corrosion Resistance of Alloys with Potential Application in Supercritical Water-cooled Nuclear Reactors”, Periodica Polytechnica Chemical Engineering, 63(2), pp. 328–332, 2019. https://doi.org/10.3311/PPch.12923

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Section

Articles