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Fatigue Effect of RCS Branch Line by Thermal Stratification

[+] Author Affiliations
Hag-Ki Youm, Kwang-Chu Kim, Man-Heung Park, Tea-Eun Jin

Korea Power Engineering Company, Inc., Yongin-Shi, Kyeonggi-Do, Korea

Sun-Ki Lee, Tae-Ryong Kim

Korea Electric Power Research Institute, Daejon, Korea

Jong Hyun Kim

Korea Advanced Institute of Science and Technology, Daejon, Korea

Paper No. PVP2003-1817, pp. 61-67; 7 pages
doi:10.1115/PVP2003-1817
From:
  • ASME 2003 Pressure Vessels and Piping Conference
  • Problems Involving Thermal Hydraulics, Liquid Sloshing, and Extreme Loads on Structures
  • Cleveland, Ohio, USA, July 20–24, 2003
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-1695-8
  • Copyright © 2003 by ASME

abstract

Recent events reported at a number of nuclear power plants worldwide have shown that thermal stratification, cycling, and striping in piping can cause excessive thermal stress and fatigue on the piping material. These phenomena are diverse and complicated because of the wide variety of geometry and thermal hydraulic conditions encountered in reactor coolant system. Thermal stratification effect of re-branched lines is not yet considered in the fatigue evaluation. To evaluate the thermal load due to turbulent penetration, this paper presents a fatigue evaluation methodology for a branch line of reactor coolant system with the re-branch line. The locations of fatigue monitoring and supplemented inspections are discussed as a result of fatigue evaluations by Interim Fatigue Management Guideline (ITFMG) and detail finite element analysis. Although the revised CUF was increased less than 50 %, the CUF values for some locations was greater than the ASME Code limits.

Copyright © 2003 by ASME

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