Analysis of Local Wall Thinning around the Extraction Steam Entrance for the 6th Feedwater Heater Shell in the Nuclear Power Plants

2009 ◽  
Vol 12 (4) ◽  
pp. 54-62
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Wall Thinning ◽  
Local Wall Thinning

Application of Laser-Generated Ultrasound for Evaluation of Thickness Reduction in Carbon Steel Pipes

2006 ◽  
Vol 321-323 ◽  
pp. 743-746 ◽  
Author(s):  
Jong Ho Park ◽  
Joon Hyun Lee ◽  
Gyeong Chul Seo ◽  
Sang Woo Choi
Keyword(s):  
Carbon Steel ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Guided Wave ◽  
Thickness Reduction ◽  
Steel Pipes ◽  
Time Frequency ◽  
Wall Thinning ◽  
Local Wall Thinning

In carbon steel pipes of nuclear power plants, local wall thinning may result from erosion-corrosion or flow-accelerated corrosion(FAC) damage. Local wall thinning is one of the major causes for the structural fracture of these pipes. Therefore, assessment of local wall thinning due to corrosion is an important issue in nondestructive evaluation for the integrity of nuclear power plants. In this study, laser-generated ultrasound technique was employed to evaluate local wall thinning due to corrosion. Guided waves were generated in the thermoelastic regime using a Q-switched pulsed Nd:YAG laser with a linear slit array. . In this paper, time-frequency analysis of ultrasonic waveforms using wavelet transform allowed the identification of generated guided wave modes by comparison with the theoretical dispersion curves. Modes conversion and group velocity were employed to detect thickness reduction.

Evaluation of Wall-Thinning in Pipes Using Laser-Generated Guided Waves

2006 ◽  
Vol 326-328 ◽  
pp. 705-708
Author(s):  
Jong Ho Park ◽  
Joon Hyun Lee ◽  
Min Rae Lee
Keyword(s):  
Carbon Steel ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Guided Waves ◽  
Single Mode ◽  
Steel Pipe ◽  
Wall Thinning ◽  
Structural Fracture ◽  
Local Wall Thinning

Local wall thinning is one of the major causes for the structural fracture of pipes of nuclear power plants. Therefore, assessment of local wall thinning due to corrosion is an important issue in nondestructive evaluation for the integrity of nuclear power plants. In this study, lasergenerated guided waves were used for pipe inspection, where a laser beam illuminated through linear slit array was used as the transmitter and the air-coupled transducer was used as the receiver. Slits was used in order to enhance the mode-selectivity of guided waves, since the space of slits is equal to the wavelength of the generated wave. The air-coupled transducer detected the selected single mode by turning its detection angle that was calculated from the relations between the wave propagation velocity in air and the phase velocity in dispersion curves. Experimental results for a 4- mm thick carbon steel pipe showed that the detection of the specific mode was useful in the distinction of the wall-thinning thickness in the carbon steel pipe.

309 High Temperature Impact-Fretting Wear Experiments for Evaluation of Pipe Wall Thinning Phenomena in Nuclear Power Plants

2013 ◽  
Vol 2013.49 (0) ◽  
pp. 87-88
Author(s):  
Yoshiki SATO ◽  
Akira IWABUCHI ◽  
Michimasa UCHIDATE ◽  
Hitoshi YASHIRO ◽  
Akito OYAKAMA ◽  
...  
Keyword(s):  
High Temperature ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Pipe Wall ◽  
Fretting Wear ◽  
Wall Thinning ◽  
Temperature Impact

Wall Thinning Analyses for Secondary Side Piping of Korean NPPS Using CHECWORKS Code

2002 ◽  
Author(s):  
K. M. Hwang ◽  
T. E. Jin ◽  
S. H. Lee ◽  
S. C. Jeon
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Operating Time ◽  
Accelerated Corrosion ◽  
Wear Rates ◽  
Wall Thinning ◽  
Management Technology ◽  
Reactor Types ◽  
Secondary Side

Since the mid-1990s, nuclear power plants in Korea have experienced wall thinning, leaks, and ruptures of secondary side piping caused by flow-accelerated corrosion (FAC). The pipe failures have increased as operating time progresses. In order to prevent FAC-induced pipe failures and to develop an effective FAC management strategy, KEPRI and KOPEC, along with KHNP’s support, have conducted a study for developing a systematic FAC management technology for all domestic nuclear power plants. As part of the study, FAC analyses were performed using CHECWORKS code. The analysis results were used to select components for inspection on each nuclear power plant. The site application feasibility of the analysis results was proven by comparisons of predicted and measured wear rates. This paper focuses on the introduction of the FAC analysis results for secondary side piping associated with three types of domestic nuclear power plants and the comparisons of predicted and measured wear rates. This paper also represents the comparisons of analysis results according to reactor types, power rates, and systems to facilitate the development of FAC management technology.

scholarly journals Development of ToSPACE for Pipe Wall Thinning Management in Nuclear Power Plants

2019 ◽  
Vol 09 (01) ◽  
pp. 1-15
Author(s):  
Kyeong Mo Hwang ◽  
Hun Yun ◽  
Hyeok Ki Seo ◽  
Geun Young Lee ◽  
Kyung Woo Kim
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Pipe Wall ◽  
Wall Thinning

scholarly journals A non-contact ultrasonic sensor for pipe-wall thinning inspection of nuclear power plants

2019 ◽  
Author(s):  
A. Tamura ◽  
M. Endo ◽  
N. Kono ◽  
H. Okazawa ◽  
S. Okido ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Pipe Wall ◽  
Ultrasonic Sensor ◽  
Wall Thinning

The Comprehensive Discussion of the Pipe Wall Thinning of Secondary System in BWR and PWR Nuclear Power Plants

2006 ◽  
Author(s):  
Taku Ohira ◽  
Tomohiko Hoshino
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Single Phase ◽  
Pipe Wall ◽  
Secondary System ◽  
Power Company ◽  
Wall Thinning ◽  
Secondary Systems ◽  
Pipe Bending

The behaviors of pipe wall thinning of secondary systems in The Japan Atomic Power Company (JAPC)’s BWR and PWR nuclear power plants were compared in this paper, to discuss the effects of respective factors contributing to corrosion protection of pipe. The rates of pipe wall thinning in single-phase flow environment, in both BWR and PWR, depend on temperature. Nevertheless, the rate of pipe wall thinning in PWR is more than that in BWR. The rates of pipe wall thinning at elbow of pipe, bending of pipe, straight run of pipe and reducer areas are mutually different, although they are located in the same line. Especially, the rates of pipe wall thinning at elbows of pipes, bendings of pipes, straight runs of pipes and reducers, which are located closely downstreams of the pumps discharge nozzles, elbows, orifices or bent pipes, depend on not the temperature but the pipe configuration.

scholarly journals Effects of alloys and flow velocity on welded pipeline wall thinning in simulated secondary environment for nuclear power plants

2016 ◽  
Vol 15 (5) ◽  
pp. 245-252
Author(s):  
Kyung Mo Kim ◽  
Yong-Moo Choeng ◽  
Eun Hee Lee ◽  
Jong Yeon Lee ◽  
Se-Beom Oh ◽  
...  
Keyword(s):  
Flow Velocity ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Wall Thinning ◽  
Pipeline Wall
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