Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Development of Piping Analysis Procedure of a PWR Surge Line for Stratified Flow

  • Y. J. Yu (Korea Atomic Energy Research Institute) ;
  • J. H. Jheon (Korea Atomic Energy Research Institute) ;
  • K. S. Yoon (Korea Atomic Energy Research Institute) ;
  • Park, S. H. (Korea Atomic Energy Research Institute) ;
  • Kim, D. H.
  • Published : 1996.08.01
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Abstract

Piping Systems are usually designed for thermal expansion loads based on uniform temperatures at each cross section. However, in lines with low flow rates such as surge lines and spray lines, large transverse temperature gradients have been observed, resulting in too types of additional thermal stresses : (1) local thermal gradient stresses which are independent of routing and supports and (2) gross bending stresses due to induced pipe curvature which are routing and support system dependent. This paper presents a simplified method for analyzing a PER surge line for stratified flow.

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References

  1. INPO SER 25-87(Safety Evaluation Report) Surge Line Stratifications
  2. NRC Bulletin 88-08 Thermal Stratification of Piping Connected to Reactor Coolant System NRC
  3. NRC Bulletin 88-11 Pressurizer Surge Line Thermal Stratification NRC
  4. ASME PVP Conference Thermal Stratification of Surge Line in PWR Nuclear Power Plant Y. J. YU(et al.)
  5. SMiRT 13 Evaluation of Surge Line Thermal Stratification and Implementation to Piting Design Y. J. Yu(et al.)
  6. Presented at International Symposium on Pressure Vessel Technology and Nuclear Codes & Standards G. A. Pierfedeici;w. J. Bak;Y. J. Yu
  7. Heat Transfer J. P. Hollamm