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Technical Paper

Evolution of Design Methodologies for Next Generation of Reactor Pressure Vessels and Extensive Role of Thermal-Hydraulic Numerical Tools

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Pages 196-209 | Published online: 10 Apr 2017

References

  • S. BELLET, A. CARUSO, and A. MARTIN, “EDF’s R&D Project on Thermal Hydraulics Behavior of PWR’s Vessel in Normal Conditions,” Proc. ASME/JSME Pressure Vessels and Piping Division Conf. (PVP 2000), Seattle, Washington, July 2000.
  • F. TERNON-MORIN, A. MARTIN, S. BELLET, P. HAUSSAIRE, and G. BEZDIKIAN, “Assessment of French Reactor Vessel Integrity,” Proc. 8th Int. Conf. Nuclear Engineering (ICONE-8), Baltimore, Maryland, April 2–6, 2000.
  • G. BAROIS, N. GOREAUD, and N. NICAISE, “Hydraulics in the RPV Lower Plenum of EPR,” Proc. 9th Int. Conf. Nuclear Engineering (ICONE-9), Nice, France, April 8–12, 2001.
  • A. CARUSO, S. BELLET, and E. MARTINO, “Thermal Hydraulic Behavior Inside the Upper Plenum and the Hot Legs of a 1300-MWe PWR Qualification on BANQUISE Mock-Up,” Proc. ASME/JSME Pressure Vessels and Piping Division Conf. (PVP 2001), Atlanta, Georgia, 2001.
  • I. RUPP and C. PENIGUEL, Internal Study on Heavy Reflector, Electricité de France (2000).
  • S. BELLET, A. MARTIN, S. LAURENT, and P. DOLLEANS, “CFD Tools for Thermal Hydraulics PTS Analysis,” Proc. ASME/JSME Pressure Vessels and Piping Division Conf. (PVP 2001), Atlanta, Georgia, 2001.

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