Table of Contents Author Guidelines Submit a Manuscript
Science and Technology of Nuclear Installations
Volume 2013, Article ID 128305, 11 pages
Research Article

Qualification of TRACE V5.0 Code against Fast Cooldown Transient in the PKL-III Integral Test Facility

1University of Pisa San Piero a Grado Nuclear Research Group (GRNSPG), Italy
2ENEA “Brasimone” Research Center, 40032 Camugnano, Italy

Received 4 March 2013; Accepted 14 June 2013

Academic Editor: Keith E. Holbert

Copyright © 2013 Eugenio Coscarelli et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. A. Annunziato, H. Glaeser, J. Lillington, P. Marsili, C. Renault, and A. Sjöberg, “CSNI integral test facility validation matrix for the assessment of thermal-hydraulic codes for LWR,” NEA/CSNI/R 96, 1996. View at Google Scholar
  2. IAEA, “Accident analysis for nuclear power plants,” Safety Reports Series 23, IAEA, Vienna, Austria, 2002. View at Google Scholar
  3. H. Kremin, H. Limprecht, R. Guneysu, and K. Umminger, “Description of the PKL III test facility,” FANP NT31/01/e30, Technical Centre of Framatome ANP, Erlangen, Germany, 2001. View at Google Scholar
  4. A. del Nevo, M. Adorni, F. D’Auria, and G. M. Galassi, “Capability of CATHARE2 V2. 5 code in simulating boron dilution following a SB-LOCA. comparison with PKL III results,” DIMNP NT 634 (08) Rev1, University of Pisa, 2009. View at Google Scholar
  5. M. Bonuccelli, F. D'Auria, N. Debrecin, and G. M. Galassi, “A Methodology for the qualification of thermalhydraulic code nodalizations,” in Proceedings of of Nuclear Reactor Thermal-hydraulics Conference (NURETH' 6), Grenoble, France, October 1993.
  6. F. D’Auria, A. Bousbia-Salah, A. Petruzzi, and A. del Nevo, “State of the art in using best estimate calculation tools in nuclear technology,” Nuclear Engineering and Technology, vol. 38, no. 1, pp. 11–32, 2006. View at Google Scholar
  7. United States Nuclear Regulatory Commission, TRACE V5.0 Theory Manual Field Equations, Solution Methods, and Physical Models, 2007.
  8. R. Bovalini, F. D’Auria, and M. Leonardi, “Qualification of the fast fourier transform based methodology for the quantification of thermalhydraulic code accuracy,” DCMN Report, NT 194 (92), University of Pisa, Pisa, Italy, 1992. View at Google Scholar
  9. A. Prošek, F. D'Auria, and B. Mavko, “Review of quantitative accuracy assessments with fast Fourier transform based method (FFTBM),” Nuclear Engineering and Design, vol. 217, no. 1-2, pp. 179–206, 2002. View at Publisher · View at Google Scholar · View at Scopus