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Trend Analysis for Basic Design of a Plate and Shell Heat Exchanger

판형쉘열교환기 기본설계를 위한 경향성 분석

  • 최동현 (경희대학교 원자력공학과) ;
  • 장윤석 (경희대학교 원자력공학과) ;
  • 강선예 (한국전력기술(주) 원자로설계개발단)
  • Received : 2022.11.19
  • Accepted : 2022.12.22
  • Published : 2022.12.30

Abstract

In order to prepare for a future nuclear market, research for developing floating small modular reactor has been initiated with the aim of differentiating it from large nuclear power plants such as distributed power, heat supply to remote communities and sea water desalination. Depending on the characteristics of the small modular reactor, it is necessary to design a plate and shell heat exchanger that can be manufactured smaller than the U-tube recirculation method. In this study, 12 cases are selected by changing the diameter of the heat plate, the thickness of the device body and the size of the stiffener. Finite element analysis is performed by setting the stress classification lines for the point at which deformation is expected under external pressure conditions for these analysis cases. For the basic design of the plate and shell heat exchanger, the optimal conditions are derived by analyzing the tendency of stress change in the device body and stiffener.

Keywords

References

  1. Kim, I. H., Kim, G. S., Chung, C. K., Choi, H. R., Seo, J. T., and Lee, S. K., 2020, "Development of Floating Nuclear Power Plant BANDI-60s," Korean Society for Fluid Machinery: Proceedings of the KFMA Annual Meeting, Pyeongchang, August 24-26, pp. 203-204. 
  2. Kim, I. H., Won, J. S., Bae, T. H., Yi, K. W., Choi, H. R., Kim, G. S., Lee, S. K., Kim, S. J., Chung, C. K., Kim, B. G., Seo, J. T., and Lee, B. J., 2019, "Development of BANDI-60S for a Floating Nuclear Power Plant," Transaction of the Korean Nuclear Society, Vol. 35, pp. 24-26. 
  3. Kwak, D. H., Chang, Y. S., and Yoon, H. S., 2022, "Preliminary Structural Analyses for Design of Plate and Shell Heat Exchanger in BANDI-60," KSME Annual Meeting, JeJu, Nov. 09-12, pp. 1405-1407. 
  4. Choi, W. S., Kim, T. W., and Seo, K. S., 2008, "Shape Optimization of Perforated Reactor Head Considering a Stress Linearization," Trans. of the KPVP, Vol. 4, No. 1, pp. 22-29. 
  5. ANSYS. Inc, 2020, "ANSYS Mechanical and Workbench," 2020 R1. 
  6. ASME BPVC Sec.III, 2010, "Rules of Construction of Nuclear Facility Components," Division 1, Subsection NB, "Class 1 Components," American Society of Mechanical Engineers, NY. 
  7. ASME BPVC Sec.II, 2010, "Materials," Part D, "Properties," American Society of Mechanical Engineers, NY. 
  8. ASME BPVC Sec.III, 2010, "Rules of Construction of Nuclear Facility Components," Division 1, Appendices, American Society of Mechanical Engineers, NY. 
  9. ASME BPVC Section.VIII, 2010, "Rules for Construction of Pressure Vessels," Division 2, "Alternative Rules," American Society of Mechanical Engineers, NY. 
  10. Chang, Y. S., Jhung, M. J., Lee, B. S., Kim, H. S., and Huh, N. S., 2013, Structural Integrity of Nuclear Components, Hans House, Seoul.