Effect of controlled potential on SCC of nuclear waste package container materials

NACE - International Corrosion Conference Series

Volumn 2000-March, Issue , 2000, Pages

  Roy, Ajit K ^a   Spragge, Maura K ^a  

^a LAWRENCE LIVERMORE NATIONAL LABORATORY   (United States)

Author keywords

And controlled potential; Hydrogen embrittlement; Slow strain rate test; Stress corrosion cracking; Titanium alloys

Indexed keywords

CRACKS; DUCTILE FRACTURE; DUCTILITY; HYDROGEN; HYDROGEN EMBRITTLEMENT; RADIOACTIVE WASTE ENCAPSULATION; RADIOACTIVE WASTE STORAGE; RADIOACTIVE WASTES; RESIDUAL STRESSES; SCANNING ELECTRON MICROSCOPY; SECONDARY ION MASS SPECTROMETRY; SODIUM CHLORIDE; STRAIN RATE; TESTING; TITANIUM ALLOYS; TITANIUM COMPOUNDS;

AND CONTROLLED POTENTIAL; APPLIED POTENTIALS; CORROSION POTENTIALS; HYDROGEN CONCENTRATION; HYDROGEN-INDUCED CRACKING; NUCLEAR WASTE PACKAGE; SLOW STRAIN RATE TESTS; SODIUM CHLORIDE (NACL);

STRESS CORROSION CRACKING;

EID: 84994393903     PISSN: 03614409     EISSN: None     Source Type: Book Series    
DOI: None     Document Type: Conference Paper

References (11)

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