Characterisation of stress corrosion cracking and microstructure of a welded light water reactor thermal shield after 25 years of service

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Abstract

Irradiation assisted stress corrosion cracking is a major concern for ageing of light water cooled nuclear reactors. In many industrial cases, welded structures are prone to cracking at relatively early stages in life. A welded thermal shield, extracted from a decommissioned experimental PWR, was selected as a relevant case study for cracking of boiling water reactor core shrouds, having similar dimensions, production methods and operating conditions. The material was characterised in terms of microstructure and mechanical properties, for irradiation dose levels ranging from 10-5 dpa up to 0.35 dpa. Both base metal and heat affected zone were characterised, correlating the microstructural damage to the irradiation induced hardening of the material. The susceptibility of the material to stress corrosion cracking was determined by slow strain rate testing in simulated boiling water reactor environment

Details

Original languageEnglish
Title of host publicationCharacterisation of stress corrosion cracking and microstructure of a welded light water reactor thermal shield after 25 years of service
Place of PublicationBeijing, China
Pages10-21
Publication statusPublished - 16 Jun 2005
EventProc. 16th international corrosion conference - 2005 - ICC Congresses - International Corrosion Council, Beijing, China
Duration: 19 Sep 200524 Sep 2005

Conference

ConferenceProc. 16th international corrosion conference - 2005
CountryChina
CityBeijing
Period2005-09-192005-09-24

Keywords

  • high temperature water, stress corrosion cracking, stainless steel, weld, irradiation

ID: 337232