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Analysis of Tube Support Plate Reinforcement Effects on Burst Pressure of Steam Generator Tubes with Axial Cracks
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 Title & Authors
Analysis of Tube Support Plate Reinforcement Effects on Burst Pressure of Steam Generator Tubes with Axial Cracks
Kang, Yong Seok; Lee, Kuk Hee; Kim, Hong Deok; Park, Jai Hak;
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 Abstract
A steam generator tubing is one of the main pressure boundary of the reactor coolant system in the nuclear power plants. Structural integrity refers to maintaining adequate margins against failure of the tubing. Burst pressure of a tube at tube support plate can be higher than that for a free-span tube because failure behaviors could be interfered from the tube support plate. Alternative repair criteria for out-diameter stress corrosion cracking indications in tubes to the drilled type tube support plate were developed, however, there are very limited information to the eggcrate type tube support plate. This paper discussed reinforcement effect of steam generator tube burst pressure with axial out-diameter stress corrosion cracking within an eggcrate type tube support plate. A series of tube burst tests were performed under the room temperature and it was found out that there is no significant but marginal effects.
 Keywords
tube support plate;out-diameter stress corrosion cracking;alternative repair criteria;burst pressure;
 Language
Korean
 Cited by
 References
1.
I. C. Kim and M. W. Nam, "Automated Analysis Technique Developed for Detection of ODSCC on the Tubes of OPR1000 Steam Generator", Journal of the Korean Society for Nondestructive Testing, Vol. 33, No. 6, PP. 519-523, 2014

2.
Y. S. Kang, K. Y. Cheon, M. W. Nam and J. H. Park, "An Effect on the Strutural Integrity Assessemtn of Steam Generator Tubes with Resolution of Rotating Pancake Coils for Multiple Cracks", Journal of the Korean Society for Nondestructive Testing, Vol. 34, No. 5, pp. 356-361, 2014. crossref(new window)

3.
Y. S. Kang, M. W. Nam and J. H. Park, "Verification of Integrity of Steam Generator Tubes by Pressure Testing", Journal of Energy and Power Engineering, Vol. 7, No. 12, pp. 2249-2255, 2013.

4.
USNRC Regulatory Guide, "Reg. Guide 1.121 Bases for Plugging Degraded PWR Steam Generator Tubes", United States Nuclear Regulatory Commision, pp. 1.121.2-5, 1976.

5.
H. Cothron, "Stean Generator Management Program: Steam Generator Degradation Specific Management Flaw Handbook Revision 1 1019037", Electric Power Resarch Institute, Palo Alto CA, pp. 5-1-32, 2009.

6.
T. A. Pitterle, R. F. Keating and V. Srinivas, "Steam Generator Tubing Outside Diameter Stress Corrosion Cracking at Tube Support Plates Database for Alternate Repair Limits NP 7480-L Addendum 2", Westinghouse Electric Company Nuclear Service Division, Madison PA, pp. 1-2, 1998.

7.
T. A. Pitterle and R. F. Keating, "Steam Generator Tubing Outside Diameter Stress Corrosion Cracking at Tube Support Plates Database for Alternate Repair Limits: Update 2004 1011456 ", Electric Power Resarch Institute, Palo Alto CA, pp. 2.1-4, 2005.

8.
H. Cothron, "Steam Generator Tubing Outside Diameter Stress Corrosion Cracking at Tube Support Plates Database for Alternative Repair Limits: Addendum 7 1018047", Electric Power Resarch Institute, Palo Alto CA, pp. 1.1-2, 2008.

9.
C. L. Williams, "PWR Steam Generator Tube Repair Limits: Technical Support Document for ODSCC Cracking at Tube Support Plates 100407", Electric Power Resarch Institute, Palo Alto CA, pp. 1.10-12, 1992.

10.
H. Cothron, "Steam Generator Management Program : Steam Generator Engineering Training Course 1 Module 4 1018640", Electric Power Resarch Institute, Palo Alto CA, pp. 45, 2009.

11.
A. Mcllree, "Steam Generator Tubing Burst Testing and Leak Rate Testing Guidelines 1006783", Electric Power Resarch Institute, Palo Alto CA, pp. 2-11, 2002.