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Technical Paper

Simulation of Two Loss-of-Flow Transients in a VVER-1000 Nuclear Power Plant with RELAP5/MOD3.2 System Code

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Pages 82-92 | Published online: 13 May 2017

References

  • N. CERULLO, M. FROGHERI, F. D’AURIA, and I. HINOVSKY, “Data Base for Transient Analyses in WWER-1000 Nuclear Plants,” Proc. 4th Int. Conf. Nuclear Engineering, ICONE-4, New Orleans, Louisiana, March 10–14, 1996, American Society of Mechanical Engineers.
  • F. D’AURIA, G. M. GALASSI, and L. MASTRANTONIO, “Accident Management Studies in the WWER-1000 Plant,” Proc. 5th Int. Conf. Nuclear Engineering, ICONE-5, Nice, France, May 26–30, 1997, American Society of Mechanical Engineers.
  • P. GROUDEV, P. KONSTANTINOV, W. SHIER, and G. SLOVIK, “Validation of a RELAP5 Computer Model for a WWER-1000 Nuclear Power Plant,” Proc. 8th Int. Topl. Mtg. Nuclear Thermal-Hydraulics, NURETH-8, Kyoto, Japan, October 1–4, 1997.
  • RELAP5 DEVELOPMENT TEAM, “RELAP5/MOD3 Code Manual,” NUREG/CR-5535, Idaho National Engineering and Environmental Laboratory (1995).
  • M. BONUCCELLI, F. D’AURIA, N. DEBRECIN, and G. M. GALASSI, “A Methodology for the Qualification of Thermal-hydraulic Codes Nodalizations,” Proc. 6th Int. Topl. Mtg. Nuclear Thermal-Hydraulics, NURETH-6, Grenoble, France, October 5–8, 1993.
  • F. D’AURIA and A. B. WAHBA, “More Than 30 Years of Reactor Thermal Hydraulics,” Kerntechnik, 63, 1 (1998).

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