Thermal Fatigue Cracking due to Intermittently Flowing Drain Water in Steam Piping

Author(s):  
Saito Koki ◽  
Watanabe Tomohiro

Abstract In a petrochemical plant, a steam leak incident happened due to a through-wall crack, which was found around the branch connection between the superheated steam pipe header and the branch pipe for the safety valve. Similar cracks had been observed in the Normally No Flow (NNF) line pipes sometimes. We decided to investigate the cause of these cracks. The crack was found along the circumferential welding line of the branch connection. According to the microfractography, the origin of the crack was internal surface of the pipe and it propagated through the thickness of the wall. Striations were observed on the fracture surface, and it showed the fatigue effect. All the NNF line pipes where the leak incidents occurred were installed upward and then connected to the horizontal pipe toward the safety valve. Infrared thermographic testing revealed that the steam drain pooled in the horizontal pipes was flowing intermittently toward the superheated steam pipe header. Cyclic thermal stress was sure to occur in the damaged area with calculation by FEM, and the cause was assumed to be thermal fatigue cracking due to intermittent dripping of drain water condensed in the NNF pipe. We decided to correct the slope of the horizontal pipe so that the drain was not pooled. Also, we checked all other NNF line pipes upwards and confirmed that there was no possibility of a similar incident due to drain in the horizontal pipe.

2018 ◽  
Vol 96 ◽  
pp. 128-136 ◽  
Author(s):  
Zhiyuan Lu ◽  
Zhaoming Meng ◽  
Ningxin Gu ◽  
Jinpu Wang ◽  
Feifei Nian ◽  
...  

Author(s):  
Yue Zou ◽  
Brian Derreberry

Abstract Thermal cycling induced fatigue is widely recognized as one of the major contributors to the damage of nuclear plant piping systems, especially at locations where turbulent mixing of flows with different temperature occurs. Thermal fatigue caused by swirl penetration interaction with normally stagnant water layers has been identified as a mechanism that can lead to cracking in dead-ended branch lines attached to pressurized water reactor (PWR) primary coolant system. EPRI has developed screening methods, derived from extensive testing and analysis, to determine which lines are potentially affected as well as evaluation methods to perform evaluations of this thermal fatigue mechanism for the U.S. PWR plants. However, recent industry operating experience (OE) indicate that the model used to predict thermal fatigue due to swirl penetration is not fully understood. In addition, cumulative effects from other thermal transients, such as outflow activities, may also contribute to the failure of the RCS branch lines. In this paper, we report direct OE from one of our PWR units where thermal fatigue cracking is observed at the RCS loop drain line close to the welded region of the elbow. A conservative analytical approach that takes into account the influence of thermal stratification, in accordance with ASME Class 1 piping stress method, is also proposed to evaluate the severity of fatigue damage to the RCS drain line, as a result of transients from outflow activities. Finally, recommendations are made for future operation and inspection based on results of the evaluation.


2021 ◽  
Author(s):  
Yuxiang Zhang ◽  
Ryan J. Buntain ◽  
Jacob D. Edwards ◽  
Boian Alexandrov ◽  
Jorge Penso

2019 ◽  
Vol 105 ◽  
pp. 766-780 ◽  
Author(s):  
Elham kamouri Yousefabad ◽  
Saeed Asadi ◽  
Payam Savadkouhi ◽  
Omid Sedaghat ◽  
Ali Bakhshi

Author(s):  
T. M. Damiani ◽  
J. E. Holliday ◽  
M. J. Zechmeister ◽  
R. D. Reinheimer ◽  
D. P. Jones

Thermal fatigue cracking has been observed for thick perforated spacer rings used as part of a thermal fatigue test loop operating at Bechtel Bettis, Inc. The perforated rings are used for instrumentation access to the fluid flow at the test specimen inlet and outlet, and are subject to alternating hot and cold forced flow, low oxygenated water every three minutes so that rapid changes in water temperature impart a thermal shock event to the inner wall of the rings. Thermal and structural three dimensional elastic and elastic-plastic finite element analyses (FEA) were conducted for the ring and the results used to predict fatigue crack initiation using strain-based fatigue-life algorithms. Predicted cycles-to-crack initiation agreed well with the observed cracking when alternating shear strain intensity analogous to the Tresca stress was used. This analysis qualifies the use of FEA for thermal fatigue assessments of complicated three-dimensional components.


Author(s):  
Guy DeBoo ◽  
Kevin Ramsden ◽  
Roman Gesior ◽  
Brian Strub

The Quad Cities Nuclear Power Station, Units 1 and 2, have a history of steam line vibration issues. The implementation of an Extended Power Uprate resulted in significant increases in steam line vibration as well as acoustic loading of the steam dryers, which led to equipment failures and fatigue cracking of the dryers. This paper discusses the extensive data collection on the Quad Cities Unit 2 replacement dryer and the Main Steam Lines. This data was taken with the intent of identifying acoustic sources in the steam system. Review of the data confirmed that vortex shedding coupled column resonance in the relief and safety valve standpipes were the principal sources of large magnitude acoustic loads in the main steam system. Modifications were developed in subscale testing to alter the acoustic properties of the valve standpipes and add acoustic damping to the system. The modifications developed and installed consisted of acoustic side branches that were attached to the Electromatic Relief Valve (ERV) and Main Steam Safety Valve (MSSV) attachment pipes. Subsequent post-modification testing was performed in plant to confirm the effectiveness of the modifications. The modifications have demonstrated a reduction in the acoustic pressure loads at full Extended Power Uprate (EPU) conditions to levels below those at Original Licensed Thermal Power (OLTP).


2004 ◽  
Vol 16 (1) ◽  
pp. 48-52 ◽  
Author(s):  
Zhimin Mo ◽  
Zonghe Lai ◽  
Shiming Li ◽  
Johan Liu

1986 ◽  
Vol 29 (5) ◽  
pp. 420-425
Author(s):  
V. S. Ermakov ◽  
R. A. Kal'ko ◽  
S. V. Burdykin ◽  
I. G. Rogachev
Keyword(s):  

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