Safety Evaluation of Socket Weld Integrity in Nuclear Piping


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Key Engineering Materials (Volumes 270-273)

Edited by:

Seung-Seok Lee, Dong-Jin Yoon, Joon-Hyun Lee and Sekyung Lee




Y. H. Choi et al., "Safety Evaluation of Socket Weld Integrity in Nuclear Piping", Key Engineering Materials, Vols. 270-273, pp. 1725-1730, 2004

Online since:

August 2004




[1] ASME, Class 1 Components, ASME Boiler and Pressure Vessel Code Sec. III NB (2001).

[2] OPDE Database(rev. 0. a), OECD Piping Failure Data Exchange Project, OECD/NEA (2002).

[3] EPRI, Nuclear Reactor Piping Failures at US Commercial LWRs : 1961 - 1997, EPRI TR-110102 (1998).

[4] USNRC, Rate of Initiating Events at U.S. Nuclear Power Plants : 1987 - 1995 NUREG/CR-5250 (1998).

[5] S. Y. Choi and Y. H. Choi, Piping Failure Analysis for the Korean Nuclear Power Piping including the Effect of In-Service Inspection, APCNDT 2003, Jeju (2003).

[6] USNRC, Pipe Cracking Experience in LWR, NUREG-0679 (1980).

[7] USNRC, Investigation and Evaluation of Cracking Incidents in Piping in PWR, NUREG-0691 (1980).

[8] USNRC, Erosion/Corrosion-Induced Pipe Wall Thinning in US NPPs, NUREG-1344 (1989).

[9] ASME Code OM, Requirements for Pre-operational and Initial Start-Up Vibration Testing of Nuclear Power Plants, ASME Boiler and Pressure Vessel Code Operation and Maintenance(OM) Part 3 (2001).

[10] Operation Procedure for Primary Sampling System, Yong-Kwang Unit 3&4 (1995).

[11] American Society of Mechanical Engineer, ASME Boiler and Pressure Vessel Code Sec. XI, Rules for In-Service Inspection of Nuclear Power Plant Components (1998).