Investigation of corrosion resistance of alloys with potential application in supercritical water-cooled nuclear reactors

Ákos Horváth, A. Imre, György Jákli

Research output: Contribution to journalArticle

1 Citation (Scopus)

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.

Original languageEnglish
Pages (from-to)328-332
Number of pages5
JournalPeriodica Polytechnica Chemical Engineering
Volume63
Issue number2
DOIs
Publication statusPublished - Jan 1 2019

Fingerprint

Water cooled reactors
Corrosion resistance
Corrosion
Pressurized water reactors
Autoclaves
Piles
Power plants
Economics
Temperature

Keywords

  • High pressure
  • Steel corrosion
  • Supercritical water

ASJC Scopus subject areas

  • Chemical Engineering(all)

Cite this

Investigation of corrosion resistance of alloys with potential application in supercritical water-cooled nuclear reactors. / Horváth, Ákos; Imre, A.; Jákli, György.

In: Periodica Polytechnica Chemical Engineering, Vol. 63, No. 2, 01.01.2019, p. 328-332.

Research output: Contribution to journalArticle

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