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NTIS 바로가기비파괴검사학회지 = Journal of the Korean Society for Nondestructive Testing, v.28 no.2 = no.106, 2008년, pp.191 - 198
류경하 (서울대학교 핵재료연구실) , 황일순 (서울대학교 핵재료연구실) , 김지현
Flow accelerated corrosion (FAC) phenomenon of low alloy carbon steels in nuclear power plant has been known as one of major degradation mechanisms. It has a potential to cause nuclear pipe rupture accident which may directly impact on the plant reliability and safety. Recently, the equipotential sw...
J. Ducreux, 'Theoretical and experimental investigation of effect of chemical compo- sition of steel on their erosion-corrosion resistance,' Paper 19 presented to the Specialists Meeting on 'Corrosion-Erosion of Steels in High Temperature Water and Wet Steam,' (1982)
A. Machiels, Recommendations for an Effective Flow-Accelerated Corrosion Program (NSAC-202L-R3), EPRI 1011838 Final Report, Electric Power Research Institute, (2006)
Kyung Ha Ryu, Na Young Lee and Il Soon Hwang, 'A study on the equipotent switching direct current potential drop method for the monitoring of piping thinning,' Key Engineering Materials, Vols. pp. 345-346, (2007)
Kyung Ha Ryu, Il Soon Hwang, Na Young Lee, Young Jin Oh, Jin Ho Park and Chang Ho Sohn, 'Screening method for pipe wall loss by flow accelerated corrosion,' Paper 89 presented on '13th International Conference on Environmental Degradation in Nuclear Power Systems,' (2007)
American Society for Testing and Materials, Standard Test Method for Measurement of Fracture Toughness, ASTM Method E1820-01, Annual Book of ASTM Standards, Document Number E1820-01, (2003)
H. H. Johnson, 'Calibrating the electric potential method for studying slow crack growth,' Materials Research and Standards, Vol. 5, No. 9. pp. 442-445, (1965)
U. S. N. R. C. An Evaluation of J-R Curve Testing of Nuclear Piping Materials Using the Direct Current Potential Drop Technique, NUREG/CR-4540 Report, (1986)
G. M. Wilkowski and J. O. Wambaugh, 'Single-specimen J-resistance curve evalua- tions using the direct current potential method and a computerized data acquisition system,' Fracture Mechanics: Fifteenth Symposium, ASTM STP 883, R. J. Sanford, American Society for Testing and Materials, pp. 553-576 (1984)
Kyung Ha Ryu, Na Young Lee and Il Soon Hwang, 'Development of a piping thickness monitoring system using equipotential switching direct current potential drop method', Paper 7226 presented on 'International Congress on Advances in Nuclear Power Plants' (2007)
Kyung Ha Ryu, Il Soon Hwang, Na Young Lee, Ji Hyun Kim, Jin Ho Park and Chang Ho Sohn, 'Online monitoring method using equipotential switching direct current potential drop for piping wall loss by flow accelerated corrosion', Paper presented on 'International Conference on Flow Accelerated Corrosion,' Vol. 1-3, pp. 132-144, (2008)
Bindi Chexal, Jeffrey Horowitz, Robin Jones, Barry dooley, Chris Wood, Michel Bouchacourt, Francois Remy, Francis Nordmann and Pierre St. Paul, Flow- Accelerated Corrosion in Power Plants, EPRI 106611 Technical Report, Electric Power Research Institute, (1996)
R. B. Doolwy, R. M. Tilley, V. K. Chexal, J. S. Horowitz and D. P. Munson, Guidelines for Controlling Flow-Accelerated Corrosion in Fossil Plants, EPRI 108895 Final Report, Electric Power Research Institute, (1997)
A. Machiels, Guideline for Plant Modeling and Evaluation of Component Inspection Data, EPRI 1009599 Final Report, Electric Power Research Institute, (2004)
Secondary Piping Rupture Accident at Mihama Power Station, Unit 3, of Kansai Electric Power Co. Inc. Final Report,' The Nuclear and Industrial Safety Agency, (2005)
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