Effect of shot peening on primary water stress corrosion cracking of Alloy 600 steam generator tubes in an operating PWR plant

Author:

Hur Do Haeng,Choi Myung Sik,Lee Deok Hyun,Song Myung Ho,Kim Seon Jin,Han Jung Ho

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference18 articles.

1. Microstructure and microdeformation effects on IGSCC of Alloy 600 steam generator tubing;Bruemmer;Corrosion,1988

2. Cottant, F., Garriga-Majo, D., de Keroulas, F., Todeschini, P., Van Duysen, J.C., 1991. Effectiveness of 700°C thermal treatment on primary water stress corrosion sensitivity of Alloy 600 steam generator tubes: laboratory tests and in field experience. In: Proceedings of the 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, pp. 901–911.

3. EDF, 1994. Ulchin Nuclear Power Plant-Unit 1-Loop 3-Examination of Tubes L02C45 and L04C33 Pulled out in February 1994. France.

4. Operating stresses and stress corrosion cracking in steam generator transition zones (900-MWe PWR);Flesch;Int. J. Press. Ves. Piping,1993

5. Frederick, G., Hernalsteen, P., Stubbe, J., 1987a. Qualification of Remedial Methods to Prevent Primary-Side Stress Corrosion Cracking of Steam Generator Tubing, vol. 1: Shot Peening. EPRI Report, NP-5249. Palo Alto, CA, USA.

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