Mitigation effect of hydrogen water chemistry on stress corrosion and low-frequency corrosion fatigue crack growth in low-alloy steels

Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Volumn , Issue , 2005, Pages 485-494

  Seifert, Hans Peter ^a   Ritter, Stefan ^a  

^a PAUL SCHERRER INSTITUTE   (Switzerland)

Author keywords

Boiling Water Reactor; Corrosion Fatigue; Hydrogen Water Chemistry; Low Alloy Steel; Stress Corrosion Cracking

Indexed keywords

BOILING WATER REACTORS; CORROSION FATIGUE; CRACK PROPAGATION; FRACTURE MECHANICS; HEAT AFFECTED ZONE; HIGH TEMPERATURE EFFECTS; HYDROGEN; PRESSURE VESSELS; STEEL;

BOILING WATER REACTOR; CRACK GROWTH CURVE; HYDROGEN WATER CHEMISTRY; LOW-ALLOY STEEL;

STRESS CORROSION CRACKING;

EID: 33745220515     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (13)

1. H.P. Seifert, S. Ritter, J. Hickling, "Research and Service Experience with Environmentally Assisted Cracking of Low-Alloy Steel Pressure-Boundary Components under LWR Conditions," Power Plant Chemistry, 6 (2) (2004), 111-123.
2. H.P. Seifert, S. Ritter, "Corrosion Fatigue Crack Growth Behaviour of Low-Alloy RPV and Piping Steels under BWR Conditions," Proceedings of the 3 International Conference on Fatigue of Reactor Components, Session 3: Environmental Effects, CD-ROM, Seville, Spain, October 3 -6, 2004.
3. P. Scott, D. Tice, "Stress Corrosion in Low-Alloy Steels," Nuclear Engineering and Design, 119 (1990), 399-413.
4. Y.S. Garud et al., "Corrosion Fatigue of Water-Touched Pressure Retaining Components in Power Plants," (EPRI TR-106696, Final Report, November 1997).
5. S. Ritter, H.P. Seifert, "Strain-Induced Corrosion Cracking of Low-Alloy RPV Steels under BWR Conditions," Power Plant Chemistry, 5 (1) (2003), 17-29.
6. J. Heldt, H.P. Seifert, "Stress Corrosion Cracking of Low-Alloy Reactor Pressure Vessel Steels in Oxygenated High-Temperature Water," Nuclear Engineering and Design, 206 (2001), 57-89.
7. th Int. Conf. on Env. Degr.of Mat. in Nucl. Power Systems - Water Reactors, CD-ROM, Paper No.70247, ANS/TMS/NACE, Skamania Lodge, Stevenson, WA, USA, August 10-14, 2003.
8. S. Ritter, H.P. Seifert, "The Effect of Chloride and Sulfate transients on the Stress Corrosion Cracking Behavior of Low-Alloy Reactor Pressure Vessel Steels under Simulated BWR Environment," Power Plant Chemistry, 6 (12) (2004), 748-760.
9. th Int. Conf. on Env. Degr. of Mat. in Nucl. Power Systems - Water Reactors, 2, pp. 924-931, ANS/TMS/NACE, Amelia Island, USA, 1997.
10. P. L. Andresen, L. M. Young, "Crack Tip Microsampling and Growth Rate Measurements in Low-Alloy Steel in High-Temperature Water," Corrosion, 51 (1995), 223-233.
11. P. L. Andresen, T. M. Angeliu, "The Effect of In-Situ Noble Metal Chemical Addition on Crack Growth Rate Behaviour of Structural Materials in 288 °C Water," Paper No.969084, NACE Corrosion 96, NACE, Houston, Texas, USA, 1996.
12. rd Int. IAEA Specialist's Meeting on Sub-critical Crack Growth, Vol. 1, pp. 105-124, W. Cullen, Ed., NUREG/CP-0112, Moscow, USSR, May 14-17, 1990.
13. H.P. Seifert, S. Ritter, U. Ineichen, U. Tschanz, B. Gerodetti, "Risskorrosion in druckführenden Komponenten des Primä rkreislaufes von SWR," (BFE Annual Report 2004, PSI, Switzerland, November 2004).