Susceptibility of Sensitized Type 304 Stainless Steel to Intergranular Stress Corrosion Cracking in Simulated Boiling-Water Reactor Environments

Corrosion (Houston)

Volumn 53, Issue 7, 1997, Pages 537-545

  Saito, N ^a   Kikuchi, E ^b   Sakamoto, H ^a   Kuniya, J ^b   Suzuki, S ^c  

^a TOSHIBA CORPORATION   (Japan)

^b HITACHI LTD   (Japan)

^c Pwr Eng R and D Center   (Japan)

Author keywords

Boiling water reactor; Corrosion potential; Hydrogen water chemistry; Intergranular stress corrosion cracking; Radiolysis; Slow strain rate test; Type 304 stainless steel; UNS S30400; radiation

Indexed keywords

EID: 0000487213     PISSN: 00109312     EISSN: None     Source Type: Journal    
DOI: 10.5006/1.3290285     Document Type: Article

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