Structural aspects of the environmentally assisted cracking of WWER 440 dissimilar weld joints

International Journal of Pressure Vessels and Piping

Volumn 68, Issue 1, 1996, Pages 23-37

  Ruscak M ^a   Keilova E ^a   Kocik J ^a   Burda, J ^a   Chvatal P ^a  

^a NUCLEAR RESEARCH INSTITUTE   (Czech Republic)

Author keywords

[No Author keywords available]

Indexed keywords

CORROSION FATIGUE; CRACK INITIATION; DISSIMILAR MATERIALS; FATIGUE TESTING; HIGH TEMPERATURE TESTING; METALLOGRAPHIC MICROSTRUCTURE; NUCLEAR REACTORS; STRESS CORROSION CRACKING; WELDS;

DISSIMILAR WELD JOINTS; ENVIRONMENTALLY ASSISTED CRACKING;

PRESSURE VESSELS;

EID: 0030214558     PISSN: 03080161     EISSN: None     Source Type: Journal    
DOI: 10.1016/0308-0161(95)00035-6     Document Type: Article

References (5)

1. Ignatov, V. A., Karzov, G. P., Timofeev, B. T. & Fedorova, V. A., The particularities of fatigue failure development close to the fusion boundaries of heterogenous materials, 11th Int. Conf. on Structural Mechanics in Reactor Technology, Tokyo 1991, Vol. G, 259-264.
2. Kočík, J., Šplíchal, K., Keilová, E., Ruščák, M., Chvátal, P., Burda, J. & Otruba, J., Microstructural and corrosion characteristics of primary piping materials of VVER-440 type reactors, Nucléon, 1, NRI Řež, 1993, 11-18.
3. X-ray Powder File, ASTM 31-403.
4. Ford, F. P. & Andresen, P. L., Stress corrosion cracking of low-alloy pressure vessel steels in 288°C water, Proceedings of the Third International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth, NUREG/CP-0112, ANL-90/22, Vol. 2, USNRC, Washington DC, 1990.
5. Ruščák, M., Kárník, D., Keilová, E., Chvátal, P., Burda, J., Kaplan, J. & Šplíchal, K., Corrosion-mechanical damage assessment of NPP V213č primary piping materials under operating condition, Report UJV-10042 M, Nuclear Research Institute, Řež 1993 (in Czech).