Research Papers

Assessment of Thermal Fatigue Predictions of Pipes With Spectral Methods

[+] Author and Article Information
Oriol Costa Garrido

Reactor Engineering Division,
Jožef Stefan Institute,
Jamova cesta 39,
Ljubljana 1000, Slovenia
e-mail: Oriol.Costa@ijs.si

Samir El Shawish

Reactor Engineering Division,
Jožef Stefan Institute,
Jamova cesta 39,
Ljubljana 1000, Slovenia
e-mail: Samir.ElShawish@ijs.si

Leon Cizelj

Reactor Engineering Division,
Jožef Stefan Institute,
Jamova cesta 39,
Ljubljana 1000, Slovenia
e-mail: Leon.Cizelj@ijs.si

1Corresponding author.

Manuscript received October 17, 2016; final manuscript received May 9, 2017; published online July 31, 2017. Assoc. Editor: Asif Arastu.

ASME J of Nuclear Rad Sci 3(4), 041001 (Jul 31, 2017) (8 pages) Paper No: NERS-16-1142; doi: 10.1115/1.4036736 History: Received October 17, 2016; Revised May 09, 2017

Large sets of fluid temperature histories and a recently proposed thermal fatigue assessment procedure are employed in this paper to deliver more accurate statistics of predicted lives of pipes and their uncertainties under turbulent fluid mixing circumstances. The wide variety of synthetic fluid temperatures, generated with an improved spectral method, results in a set of estimated distributions of fatigue lives through linear one-dimensional (1D) heat diffusion, thermal stress estimates, and fatigue assessment codified rules. The results of the fatigue analysis indicate that, in order to avoid the inherent uncertainties due to comparatively short fluid temperature histories to the estimated fatigue lives, a conservative safe design against thermal fatigue could be attempted with the lower bounds of the predicted life distributions, such as the 5% probability life (5% of samples fail). The impact of the convection heat transfer coefficient on the predictions is also studied in a sensitivity analysis. This represents a detailed attempt to correlate the uncertainties in the physical fluid mixing conditions and heat transfer to the estimated fatigue life using spectral methods.

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Chapuliot, S. , Gourdin, C. , Payen, T. , Magnaud, J. P. , and Monavon, A. , 2005, “ Hydro-Thermal-Mechanical Analysis of Thermal Fatigue in a Mixing Tee,” Nucl. Eng. Des., 235(5), pp. 575–596. [CrossRef]
NEA/CSNI, 2005, “ Thermal Cycling in LWR Components in OECD-NEA Member Countries,” Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI), Paris, France, Report No. NEA/CSNI/R(2005)8. https://www.oecd-nea.org/nsd/docs/2005/csni-r2005-8.pdf
Dahlberg, M. , Nilsson, K. F. , Taylor, N. , Faidy, C. , Wilke, U. , Chapuliot, S. , Kalkhof, D. , and Bretherton, I. , 2007, “ Development of a European Procedure for Assessment of High Cycle Thermal Fatigue in Light Water Reactors: Final Report of the NESC-Thermal Fatigue Project,” J. R. C. European Commission, Institute for Energy, Petten, The Netherlands.
Paffumi, E. , Radu, V. , and Nilsson, K. F. , 2013, “ Thermal Fatigue Striping Damage Assessment From Simple Screening Criterion to Spectrum Loading Approach,” Int. J. Fatigue, 53, pp. 92–104. [CrossRef]
Hannink, M. H. C. , and Timperi, A. , 2011, “ Simplified Methods to Assess Thermal Fatigue Due to Turbulent Mixing,” 19th International Conference on Nuclear Engineering (ICONE19), Osaka, Japan, Oct. 24–25, Paper No. ICONE19-43297. https://inis.iaea.org/search/searchsinglerecord.aspx?recordsFor=SingleRecord&RN=44076739
Shibamoto, H. , Kasahara, N. , Morishita, M. , Inoue, K. , and Jimbo, M. , 2008, “ Research and Developments of Guidelines for Thermal Load Modeling,” Nucl. Eng. Des., 238(2), pp. 299–309. [CrossRef]
Clayton, A. M. , and Irvine, N. M. , 1987, “ Structural Assessment Techniques for Thermal Striping,” ASME J. Pressure Vessel Technol., 109(3), pp. 305–309. [CrossRef]
Miyoshi, K. , Kamaya, M. , Utanohara, Y. , and Nakamura, A. , 2016, “ An Investigation of Thermal Stress Characteristics by Wall Temperature Measurements at a Mixing Tee,” Nucl. Eng. Des., 298, pp. 109–120. [CrossRef]
Beaufils, R. , and Courtin, S. , 2011, “ Analysis of the FATHER Experiment With an Engineering Method Devoted to High Cycle Thermal Fatigue,” ASME Paper No. PVP2011-57630.
Kamaya, M. , and Nakamura, A. , 2011, “ Thermal Stress Analysis for Fatigue Damage Evaluation at a Mixing Tee,” Nucl. Eng. Des., 241(8), pp. 2674–2687. [CrossRef]
Timperi, A. , 2014, “ Conjugate Heat Transfer LES of Thermal Mixing in a T-Junction,” Nucl. Eng. Des., 273, pp. 483–496. [CrossRef]
Costa Garrido, O. , El Shawish, S. , and Cizelj, L. , 2016, “ Uncertainties in the Thermal Fatigue Assessment of Pipes Under Turbulent Fluid Mixing Using an Improved Spectral Loading Approach,” Int. J. Fatigue, 82(Pt. 3), pp. 550–560. [CrossRef]
Costa Garrido, O. , El Shawish, S. , and Cizelj, L. , 2014, “ A Novel Approach to Generate Random Surface Thermal Loads in Piping,” Nucl. Eng. Des., 273, pp. 98–109. [CrossRef]
Costa Garrido, O. , and Cizelj, L. , 2016, “ Probabilistic Prediction of Fatigue Life of Pipes Under Turbulent Fluid Mixing,” ASME Paper No. ICONE24-60194.
Kasahara, N. , Takasho, H. , and Yacumpai, A. , 2002, “ Structural Response Function Approach for Evaluation of Thermal Striping Phenomena,” Nucl. Eng. Des., 212(1–3), pp. 281–292. [CrossRef]
Shinozuka, M. , and Deodatis, G. , 1991, “ Simulation of Stochastic Processes by Spectral Representation,” ASME Appl. Mech. Rev., 44(4), pp. 191–204. [CrossRef]
Hinze, J. O. , 1975, “ The Spectral Distribution of a Scalar Quantity,” Turbulence, 2nd ed., McGraw-Hill, New York, pp. 283–300.
Press, W. H. , Teukolsky, S. A. , Vetterling, W. T. , and Flannery, B. P. , 1997, Numerical Recipes in C: The Art of Scientific Computing, 2nd ed., Cambridge University Press, Cambridge, UK.
Hu, L.-W. , and Kazimi, M. S. , 2006, “ LES Benchmark Study of High Cycle Temperature Fluctuations Caused by Thermal Striping in a Mixing Tee,” Int. J. Heat Fluid Flow, 27(1), pp. 54–64. [CrossRef]
Westin, J. , Veber, P. , Andersson, L. , Mannetje, C. T. , Andersson, U. , Eriksson, J. , Henriksson, M. E. , Alavyoon, F. , and Andersson, C. , 2008, “ High-Cycle Thermal Fatigue in Mixing Tees: Large-Eddy Simulations Compared to a New Validation Experiment,” ASME Paper No. ICONE16-48731.
Costa Garrido, O. , El Shawish, S. , and Cizelj, L. , 2015, “ Stress Assessment in Piping Under Synthetic Thermal Loads Emulating Turbulent Fluid Mixing,” Nucl. Eng. Des., 283, pp. 114–130. [CrossRef]
Costa Garrido, O. , Cizelj, L. , and El Shawish, S. , 2013, “ The Role of the Axial Heat Fluxes in the Thermal Fatigue Assessment of Piping,” Nucl. Eng. Des., 261, pp. 382–393. [CrossRef]
Noda, N. , Hetnarski, R. B. , and Tanigawa, Y. , 2003, Thermal Stresses, 2nd ed., Taylor & Francis, New York. [PubMed] [PubMed]
ASME, 1989, “ Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plant Components,” American Society of Mechanical Engineers, New York.
Chopra, O. K. , and Shack, W. J. , 2007, “ Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials,” Argonne National Laboratory, Lemont, IL, Report No. NUREG/CR-6909. https://www.nrc.gov/docs/ML0706/ML070660620.pdf
Nieslony, A. , 2003, “ Rainflow Counting Algorithm,” MATLAB Central, Natick, MA. https://in.mathworks.com/company/aboutus/contact_us.html?s_tid=gn_cntus
Incropera, F. P. , and DeWitt, D. P. , 1996, Fundamentals of Heat and Mass Transfer, 4th ed., Wiley, Hoboken, NJ.
Kimura, N. , Ono, A. , Miyakoshi, H. , and Kamide, H. , 2009, “ Experimental Study on High Cycle Thermal Fatigue in T-Junction—Effect of Local Flow Velocity on Transfer of Temperature Fluctuation From Fluid to Structure,” 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13), Kanazawa, Japan, Sept. 27–Oct. 2, Paper No. N13P1169.
Hannink, M. H. C. , and Blom, F. J. , 2011, “ Numerical Methods for the Prediction of Thermal Fatigue Due to Turbulent Mixing,” Nucl. Eng. Des., 241(3), pp. 681–687. [CrossRef]


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Fig. 1

Sketch of the error function evaluation in the time domain (top) and in the distribution of fluid temperatures (bottom). Tf using random (full line) and optimal (dashed line) set of phases φj.

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Fig. 2

Temperature variation space limited by the upper bound (Max_01) and PSD constrained (Max_PSD) curves. Experimental data points in circles [19,20] and fatigue assessment points in labeled squares.

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Fig. 3

Fatigue design curve for austenitic stainless steel in air proposed in NUREG/CR-6909 [25] and adopted by ASME

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Fig. 4

Examples of fluid and pipe surface temperatures and stress distributions for selected assessment points in Fig. 2, such as: (a) point A, (b) point E, (c) point C, and (d) point SIN. For a ΔT  = 160 °C, σ̃  = 0.5 corresponds to σ  ≈ 330 MPa (Eq. (10) and Table 1).

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Fig. 5

Distributions of fatigue lives (boxes and bars), average fatigue lives (black squares), and 5–95% probabilities predicted for fluid temperature histories characteristic of the assessment points in Fig. 2. The dashed lines mark the Civaux leakage initiation time.

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Fig. 6

Influence of signal time-length on the scatter of fatigue life predictions. The dashed line in (a) marks the Civaux leakage initiation time.

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Fig. 7

Comparison of the presented fatigue assessment results with the SIN method

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Fig. 8

Heat transfer coefficient and fluid temperature difference effects on fatigue life predictions

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Fig. 9

Average fatigue life predictions for different levels of temperature fluctuations and heat transfer coefficients assuming ΔT  = 160 °C




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