The Development of Interactive Information System for Flaw Evaluation in Recirculation Piping of BWR Nuclear Power Plant

Abstract:

This study was base on the welding stress of recirculation pipe at Taiwan Power Company (TPC) which was the first nuclear power station (Chin-Shan) in Taiwan. Technicians or field engineers needed to understand the basic concepts of welding. When using internet processing system, the calculation time for obtaining the required data from the analysis of weld overlay stress had been reduced. Through the connection of internet and server the users entered the welding data from tables to the system, the analysis reports of the weld overlay stress were obtained in a few minutes. Moreover, the reliability in the analysis reports of the weld stress was examined and verified. Therefore, in the study the analysis process and programs developed were able to provide an accurate, simple, and fast analysis results and reports to users. Also, the weld analysis in a recirculation piping system was able to be used in the environmental evaluations.

• Periodical: Advanced Materials Research (Volume 739)
• Pages: 616-623
• DOI: https://doi.org/10.4028/www.scientific.net/AMR.739.616
• Online since: August 2013
• Authors: Kuen Tasnn Chen, Ku En Ting, Yu Yawn Chen, Ling Chun Lee, Kuen Chang Hsieh
• Keywords: Finite Element Analysis (FEA), Nuclear Power Station, Recirculation Pipe, Web Server, Weld Overlay Stress Analysis

References

[1] NSNRC. Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping, NUREG-0313, Revision 2, (1988).

DOI: 10.2172/5708682

[2] Code Case 504-1, ASME Code, (1992).

[3] USNRC Generic Letter 88-01, NRC Position on IGSCC in BWR in Austenitic Stainless Steel Piping", January 1988, with Supplement 1, (1992).

[4] Structural Integrity Associates, Weld Overlay Implementation Safety Evaluation Report, Revision 1, Report No. SIR-98-054, (1998).

[5] MPR-2086, Safety Evaluation Report, Weld Overlay Repair Loop A Recirculation System Piping Weld N1A-J7, Chin Shan Nuclear Power Plant Unit 1 End-of-Cycle 17 Refueling Outage, Revision 0, (1999).

[6] F.P. Hsieh, G. Q Tu. Generic Letter 88-01, Supplement 1 weld overlay shrinkage effect assessment report for first nuclear power station (Chin-Shan ) unit 1 -1999 Outage, Institute of Nuclear Energy Research R.O.C. AEC (1999).