Degradation of alloy 600 steam generator tubes in operating pressurized water reactor nuclear power plants

Corrosion

Volumn 59, Issue 9, 2003, Pages 821-827

  Hwang, S S ^a   Kim, H P ^a   Kim, J S ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

Eddy current testing; Failure analysts; Pitting; Pressurized water reactor; Steam generator; Stress corrosion cracking

Indexed keywords

LEAD COMPOUNDS; NUCLEAR POWER PLANTS; STEAM GENERATORS; THERMAL EFFECTS;

MOLAR RATIOS;

STRESS CORROSION CRACKING;

FAILURE ANALYSIS; NUCLEAR POWER PLANT; PITTING; STEAM GENERATING EQUIPMENT; STRESS CORROSION CRACKING;

EID: 0142120537     PISSN: 00109312     EISSN: None     Source Type: Journal    
DOI: 10.5006/1.3277611     Document Type: Article

References (12)

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7. G.P. Airey, Metallography 13 (1980): p. 21.
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