Skip to main content
SpringerLink
Log in

Thermal fatigue estimation due to thermal stratification in the RCS branch line using one-way FSI scheme

  • Published:
Journal of Mechanical Science and Technology Aims and scope Submit manuscript

Abstract

The scheme and procedure for thermal fatigue estimation of a thermally stratified branch line were developed. One-way FSI (fluid and structure interaction) scheme was applied to evaluate the thermal stratification piping. Thermal flow analysis, stress analysis and fatigue estimation were performed in serial order. Finally, detailed monitoring locations and mitigation scheme for the integrity maintenance of piping were recommended. All wall mesh and transient temperature distribution data obtained from the CFD (computational fluid dynamics) analysis were directly imported into the input data of stress analysis model without any calculation for heat transfer coefficients. Cumulated usage factors for fatigue effect review with nodes were calculated. A modified method that combines ASME Section III, NB-3600 with NB-3200 was used because the previous method cannot consider the thermal stratification stress intensity. As the results of evaluation, the SCS (shutdown cooling system) line, branch piping of the RCS (reactor coolant system) line, shows that the CUF (cumulative usage factor) value exceeds 1.0, ASME Code limit, in case thermal stratification load is included. The HPSI (high pressure safety injection) line, re-branch piping, shows that temperature difference between top and bottom of piping exceeds the criterion temperature, 28°C, and that the CUF value exceeds 1.0. Therefore, these branch pipings require a detailed review, monitoring or analysis. In particular, it is recommended that the HPSI piping should be shifted backward to decrease the influence of turbulent penetration intensity from the RCS piping.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Log in via an institution

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Institutional subscriptions

Similar content being viewed by others

References

  1. Boulder, Co., Nuclear Power Experience (NPE), Published by RCG/Hagler, Bailly, Inc., (1993).

  2. Framatome, RHRS Elbow Cracking at Civaux 1, Significant Event Report No. 14, (1988).

  3. Hagki Youm, et al., Numerical Analysis for Unsteady Thermal Stratified Turbulent Flow in a Horizontal Circular Cylinder, ICONE-4 Conference, (1996).

  4. Hagki Youm, et al., Development of Numerical Analysis Model for Thermal Mixing in the Reactor Pressure Vessel, ASME, PVP-2000 Conference, (2000).

  5. KEPRI & KOPEC, Pressurized Thermal Shock Evaluation for Reactor Pressure Vessel of Kori Unit 1, Technical Report-TR.96BJ12.J1999.81, (1999).

  6. EPRI, Thermal Stratification, Cycling and Striping (TASCS), TR-103581, (1994).

  7. D. H. Roarty, P. L. Strauch and J. H. Kim, Thermal Stratification, Cycling and Striping Evaluation Methodology, Changing Priorities of Codes and Standards: Failure, Fatigue, and Creep, ed. K. R. Rao and J. A. Todd, J. of ASME PVP, 286, (1994) 49–54.

  8. EPRI, Operating Experience Regarding Thermal Fatigue of Unisolable Piping Connected to PWR Reactor Coolant Systems (MPR-25), TR-1001006, (2000).

  9. NRC, Cracking in Feedwater System Piping, Bulletin No. 79-13, (1979).

  10. NRC, Thermal Stresses in Piping Connected to Reactor Coolant Systems, Bulletin 88-08, (1988).

  11. NRC, Pressurizer Surge Line Thermal Stratification, Bulletin No. 88-11, (1988).

  12. OECD NEA, Thermal Cycling in LWR components in OECD-NEA member countries, (2005).

  13. R. Magee, et al., J. M. Farley Unit 2 Engineering Evaluation of the Weld Joint Crack in the 6″ SI/RHR piping, WCAP-11789, (1988).

  14. M. Robert, Corkscrew Flow Pattern in Piping System Dead Legs, NURETH-5 Conferenc, (1992).

  15. N. Nakamori, K. Hanzawa, T. Ueno, J. Kasahara, and S. Shirahama, Research on Thermal Stratification in Un-isolable Piping of Reactor Coolant Pressure Boundary’, Experience with Thermal Fatigue in LWR Piping Caused by Mixing and Stratification, Specialist Meeting Proceedings, (1998).

  16. R. M. Roidt and J. H. Kim, Analytical and Experimental Studies of a Stratified Flow in a Pipe, NURETH-6 Conference, France, October 5–8, I, (1993) 541–547.

    Google Scholar 

  17. J. H. Kim, R. M. Roidt and A. F. Deardorff, Thermal Stratification and Reactor Piping Integrity, Nuclear Engineering and Design, 139, No. 1, (1993) 83–96.

    Article  Google Scholar 

  18. S. N. Kim, S. H. Hwang and K. H. Yoon, Journal of Mechanical Science and Technology, 9, No. 5, (2005) 1206–1215.

    Article  Google Scholar 

  19. EPRI, EDF Thermal Fatigue Monitoring Experience on Reactor Coolant System Auxiliary Piping (MRP-69), TR-1003082, (2001).

  20. FLUENT User’s Guide, Fluent Inc., (1998).

  21. ABAQUS Standard User’s Manual, Hibbitt, Karlsson & Sorensen, Inc.: Pawtucket, (1998).

  22. S&L, Integrated Piping Analysis System, S&L Program No. 303.7.026-2.2, (1995).

  23. S. V. Partankar, Numerical Heat Transfer and Fluid Flow, McGraw-Hill Book Company, (1980).

  24. M. H. Park and K. C. Kim, Thermal stratification phenomenon and evaluation in piping, Piping Journal, 18, No. 6, (2004) 188–191.

    Google Scholar 

  25. M. H. Park and K. C. Kim, Thermal stratification phenomenon and evaluation in piping, Piping Journal, 18, No. 7, (2004) 206–209.

    Google Scholar 

Download references

Author information

Authors and Affiliations

  1. Korea Power Engineering Company, Inc., Yongin, Gyeonggi, Republic of Korea

    Kwang-Chu Kim

  2. Department of Mechanical & Automovtive Engineering, Kyungwon University, Seongnam, Gyeonggi, Republic of Korea

    Jong-Han Lim & Jun-Kyu Yoon

Authors
  1. Kwang-Chu Kim
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Jong-Han Lim
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Jun-Kyu Yoon
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to Jun-Kyu Yoon.

Additional information

This paper was recommended for publication in revised form by Associate Editor Jae Young Lee

Kwang-Chu Kim received his B.S., M.S. and Ph.D degrees from department of mechanical engineering, Kyunghee University in 1993, 1995 and 2000, respectively. He has worked for Korea Power Engineering Company since 1995 and he is now a senior researcher. Dr. Kim’s research area includes CFD analysis, flow control, plant design and simulator.

Jong-Han Lim received his B.S. degree from department of mechanical engineering, Chosun University in 1981, M.S. and Ph.D degrees from department of mechanical engineering, Kyunghee University in 1986 and 1992, respectively. He worked for Hyundai Motors Company during 1986-95. He is now a professor in department of mechanical & automotive engineering, Kyungwon University. Dr. Lim’s research interests are in the area of thermal flow, internal combustion and liquid atomization.

Jun-Kyu Yoon received his B.S. degree from department of mechanical engineering, Chosun University in 1981, M.S. degree from department of mechanical engineering, Kyunghee University in 1987 and Ph.D degree from department of mechanical engineering, Myongji University in 2001. He worked for Hyundai Motors Company and Asia Motors Company during 1985–96. He is now a professor in department of mechanical & automotive engineering, Kyungwon University. Dr. Yoon’s research interests are in the area of flow control, heat transfer, liquid atomization, spray and combustion.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Kim, KC., Lim, JH. & Yoon, JK. Thermal fatigue estimation due to thermal stratification in the RCS branch line using one-way FSI scheme. J Mech Sci Technol 22, 2218–2227 (2008). https://doi.org/10.1007/s12206-008-0912-9

Download citation

  • Received:

  • Revised:

  • Accepted:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s12206-008-0912-9

Keywords

Search

Navigation