Development of an in-core stress corrosion cracking test method and preliminary test results

Corrosion

Volumn 55, Issue 2, 1999, Pages 166-172

  Mayuzumi, M ^c   Hide, K ^c   Onchi, T ^a   Karlsen, T M ^c   Vitanza, C ^b  

^a CENTRAL RESEARCH INSTITUTE OF ELECTRIC POWER INDUSTRY   (Japan)

^b OECD HALDEN REACTOR PROJECT   (Norway)

^c NONE

Author keywords

High temperature water; In core testing; Irradiation; Nuclear environments; Sensitization; Stress corrosion cracking; Type 304 stainless steel; Welds

Indexed keywords

EID: 0000314107     PISSN: 00109312     EISSN: None     Source Type: Journal    
DOI: 10.5006/1.3283977     Document Type: Article

References (12)

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