Screening method for piping wall loss by flow accelerated corrosion

Nuclear Engineering and Design

Volumn 238, Issue 12, 2008, Pages 3263-3268

  Ryu, Kyung Ha ^a   Hwang, Il Soon ^a   Lee, Na Young ^b   Oh, Young Jin ^c   Kim, Ji Hyun ^d   Park, Jin Ho ^e   Sohn, Chang Ho ^f  

^a Seoul National University   (South Korea)

^b Korea Institute of Nuclear Nonproliferation and Control   (South Korea)

^c Korea Power Engineering Company   (South Korea)

^d MASSACHUSETTS INSTITUTE OF TECHNOLOGY   (United States)

^e Korea Atomic Electric Research Institute   (South Korea)

^f Samchang Co Ltd   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

COOLING WATER; CORROSION; DROPS; FATIGUE CRACK PROPAGATION; LEAKAGE CURRENTS; LOCATION; NETWORK PROTOCOLS; OFFSHORE OIL WELL PRODUCTION; PRESSURIZED WATER REACTORS; SENSOR NETWORKS; ULTRASONIC APPLICATIONS; WATER COOLING SYSTEMS;

ACCELERATED CORROSIONS; CLOSED-FORM; CONTROL METHODS; DIRECT CURRENT POTENTIAL DROPT; FINITE-ELEMENT ANALYSES; MANAGEMENT EFFORTS; MODEL PREDICTIONS; ON-LINE; OPERATION CONDITIONS; PERSONNEL SAFETIES; PIPING NETWORKS; PLANT RELIABILITIES; RESISTANCE MODELS; SCREENING APPROACHES; SCREENING METHODS; SECONDARY COOLING; THINNING; WALL LOSSES; WALL THINNING;

FINITE ELEMENT METHOD;

EID: 54949136072     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2008.07.006     Document Type: Article

References (7)

1. American Society for Testing and Materials, Standard Test Method for Measurement of Fracture Toughness, ASTM Method E1820-01, Annual Book of ASTM Standards, vol. 03.01.
2. Bae, B.-K., Seok, C.-S., 2000. A study on detecting flows using DC potential drop method. Journal of the Korean Society of Mechanical Engineering A 24-4 (99), 874-880.
3. Chexal, B., et al., 1996. Flow-Accelerated Corrosion in Power Plants, EPRI TR-106611, Electric Power Research Institute.
4. Lee N.Y., Lee S.G., Ryu K.H., and Hwang I.S. On-line monitoring system development for single-phase flow accelerated corrosion. Nuclear Engineering and Design 237 (2007) 761-767
5. Machiles, A., 2006. Recommendations for an effective Flow-Accelerated Corrosion Program (NSAC-202L-R3), EPRI TR-1011838, Electric Power Research Institute.
6. Ryu, K.H., Lee, N.Y., Hwang, I.S., 2007. A study on the equipotent switching direct current potential drop method for the monitoring of piping thinning. Key Engineering Materials, 345-346.
7. The Nuclear and Industrial Safety Agency, May 14, 2005. Secondary Piping Rupture Accident at Mihama Power Station, Unit 3 of the Kansai Electric Power Co., Inc. (Final Report), Revision 1 (translated by Japan Nuclear Energy Safety Organization (JNES)).