International Journal of Safety

The Korean Society of Safety (한국안전학회)
권호 표지

Hydraulic and Structural Analysis for APR1400 Reactor Vessel Internals against Hydraulic Load Induced by Turbulence

  • Received : 2011.09.08
  • Accepted : 2011.12.02
  • Published : 2011.12.31
Download PDF
⟨ Previous Next ⟩

Abstract

The structural integrity assessment of APR1400 (Advanced Power Reactor 1400) reactor vessel internals has been being performed referring the US Nuclear Regulatory Commission regulatory guide 1.20 comprehensive vibration assessment program prior to commercial operation. The program is composed of a hydraulic and structural analysis, a vibration measurement, and an inspection. This paper describes the hydraulic and structural analysis on the reactor vessel internals due to hydraulic loads caused by the turbulence of reactor coolant. Three-dimensional models were built for the hydraulic and structural analysis and then hydraulic loads and structural responses were predicted for five analysis cases with CFX and ANSYS respectively. The structural responses show that the APR1400 reactor vessel internals have sufficient structural integrity in comparison with the acceptance criteria.

Keywords

References

  1. U.S. NRC, Comprehensive Vibration Assessment Program for Reactor Internals during Preoperational and Initial Startup Testing, Regulatory Guide 1.20 Rev. 3, 2007.
  2. Combustion Engineering, Inc., A Comprehensive Vibration Assessment Program for the Prototype System 80 Reactor Internals (Palo Verde Nuclear Generating Station Unit 1), CEN-202(V)-P, 1985, pp. 1-9-1-14.
  3. KEPCO, A Comprehensive Vibration Assessment Program for Yonggwang Nuclear Generating Station Unit 4, 10487-ME-TE-240-03, 1995.
  4. KOPEC, A Vibration Analysis for Ulchin Nuclear Power Plant Unit 5 Reactor Vessel Internals, KOPEC/ NED/TR/04-001, 2004.
  5. KOPEC, A Vibration Analysis for Ulchin Nuclear Power Plant Unit 6 Reactor Vessel Internals, KOPEC/ NED /TR/04-021, 2004.
  6. KOPEC, A Vibration Analysis for Shin-Kori Nuclear Power Plant Unit 1 Reactor Vessel Internals, KOPEC/ NED/ TR/10-005, 2010.
  7. K.H. Kim, D.Y. Ko and Y.S. Kim, "Hydraulic and Structural Analysis Methodology of RVI CVAP in Shin-Kori 4", Transactions of the Korean Nuclear Society Spring Meeting, pp. 1113-1114.
  8. Y.S. Kim, K.H. Kim and J.H. Lee, "Hydraulic Analysis Methodology of Reactor Vessel Internals for Comprehensive Vibration Assessment Program", Transactions of the Korean Nuclear Society Autumn Meeting, p.449-450, 2010.
  9. J.Y. Gu, K.H. Kim and Y.S. Kim, "Development and Validation of Structural Analysis Methodology for Comprehensive Vibration Assessment of Reactor Vessel Internals", Proceedings of the KSME 2010 Fall Annual Meeting, pp. 950-955, 2010.
  10. ASME B&PV Section III Division 1 Appendix N, 2010.
  11. KOPEC, Design Specification for Reactor Vessel Core Support and Internals Structures, 9-120-Z-404-001C, Rev. 02, 2008.
  12. ASME B&PV Section III Division 1 Appendix I, 2010.