Correlation between the stability of irradiation defects and stress corrosion cracking in high temperature water of welded AISI 304 stainless steel

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Abstract

Stainless steels are used for the fabrication of some internal components of light water cooled reactors, thus being subjected to radiation, heat, and corrosive environment. Neutron irradiation induces different types of damage in stainless steels. As a consequence, these materials may become susceptible to stress corrosion cracking in the high temperature water environment of the reactor cooling circuit. The different types of defects induced by irradiation have been characterised using transmission electron microscopy and positron annihilation. The contribution of the different types of defects (vacancy type clusters, dislocation loops and grain boundary segregation) is assessed by post irradiation annealing treatments. After different time - temperature combinations, the defects are removed, as it is monitored by microscopy and positron annihilation spectroscopy. The removal of defects is correlated to the stress corrosion cracking behaviour of the irradiated material before and after post irradiation annealing.

Details

Original languageEnglish
Title of host publicationCorrelation between the stability of irradiation defects and stress corrosion cracking in high temperature water of welded AISI 304 stainless steel
Place of PublicationBejing, China
Pages10-4
Publication statusPublished - 16 Jun 2005
EventProceedings of the 16th international corrosion conference - 2005 - ICC Congresses - International Corrosion Council, Bejing, China
Duration: 19 Sep 200524 Sep 2005

Conference

ConferenceProceedings of the 16th international corrosion conference - 2005
CountryChina
CityBejing
Period2005-09-192005-09-24

Keywords

  • stainless steel 304, boiling water reactor, post irradiation annealing, stress corrosion cracking, irradiation

ID: 321289