Stress corrosion cracking of stabilized austenitic stainless steels in various types of nuclear power plants

Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -

Volumn , Issue , 1999, Pages 325-329

  Speidel, Markus O ^a   Magdowski, Ruth ^a  

^a ETH ZURICH   (Switzerland)

Author keywords

[No Author keywords available]

Indexed keywords

AUSTENITE; BOILING WATER REACTORS; COLD WORKING; CRACK PROPAGATION; ELECTROCHEMISTRY; LIGHT WATER REACTORS; MICROSTRUCTURE; NUCLEAR POWER PLANTS; STAINLESS STEEL; STRESS INTENSITY FACTORS; TITANIUM; WELDS;

AUSTENITIC STAINLESS STEEL; CRACK GROWTH RATE; INTERGRANULAR STRESS CORROSION CRACKING;

STRESS CORROSION CRACKING;

EID: 0033489127     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1002/9781118787618.ch33     Document Type: Conference Paper

References (4)

1. M. O. Speidel and R. Magdowski, "Stress Corrosion Cracking of Ti- and Nb-stabilized Austenitic Stainless Steels in 288°C Water", CORROSION '94, Paper 132, NACE, 1994.
2. Ruth Magdowski and Markus O. Speidel, "Effect of cold work on the growth rates of stress corrosion cracks in structural materials of nuclear systems", CORROSION '96, Paper 112, NACE, 1996.
3. Markus O. Speidel and Ruth Magdowski, "Correlation of laboratory and field stress corrosion results in the power generation industry", CORROSION 99, Paper 146, NACE, 1999.
4. Markus O. Speidel and Ruth Magdowski, "Environmental degradation and life prediction of nuclear piping made of stabilized austenitic stainless steels", Proceedings of International Symposium on Plant Aging and Life Predictions of Corrodible Structures, May 15-18, 1995, Sapporo, Japan, pp. 951-956.