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Science and Technology of Nuclear Installations
Volume 2008, Article ID 153858, 13 pages
http://dx.doi.org/10.1155/2008/153858
Research Article

Thermal-Hydraulic Analysis Tasks for ANAV NPPs in Support of Plant Operation and Control

1Institute of Energy Technologies, Technical University of Catalonia (UPC), Avinguda Diagonal 647, Barcelona 08028, Spain
2Department of Physics and Nuclear Engineering, Technical University of Catalonia (UPC), Avinguda Diagonal 647, Barcelona 08028, Spain
3Asociación Nuclear Ascó-Vandellòs (ANAV), Edifici Seu, Apartat Correus 48, L'Hospitalet de l'Infant, Tarragona 43890, Spain

Received 9 May 2007; Accepted 31 August 2007

Academic Editor: Alessandro Petruzzi

Copyright © 2008 F. Reventós 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.

Citations to this Article [8 citations]

The following is the list of published articles that have cited the current article.

  • F. Reventós, C. Llopis, L. Batet, C. Pretel, and I. Sol, “Analysis of an actual reactor trip operating event due to a high variation of neutron flux occurring in the Vandellòs-II nuclear power plant,” Nuclear Engineering and Design, vol. 240, no. 10, pp. 2999–3008, 2010. View at Publisher · View at Google Scholar
  • V. Martinez-Quiroga, and F. Reventos, “The Use of System Codes in Scaling Studies: Relevant Techniques for Qualifying NPP Nodalizations for Particular Scenarios,” Science and Technology of Nuclear Installations, vol. 2014, pp. 1–13, 2014. View at Publisher · View at Google Scholar
  • V. Martinez-Quiroga, F. Reventos, and J. Freixa, “Applying UPC Scaling-Up Methodology to the LSTF-PKL Counterpart Test,” Science and Technology of Nuclear Installations, vol. 2014, pp. 1–18, 2014. View at Publisher · View at Google Scholar
  • Patricia Pla, Francesc Reventos, Miodrag Strucic, Manuel Martin Ramos, and Ismael Sol, “Simulation of steam generator plugging tubes in a PWR to analyze the operating impact,” Nuclear Engineering and Design, vol. 305, pp. 132–145, 2016. View at Publisher · View at Google Scholar
  • R. Pericas, K. Ivanov, F. Reventós, and L. Batet, “Code improvement and model validation for Ascó-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal–hydraulic code,” Annals of Nuclear Energy, vol. 87, pp. 366–374, 2016. View at Publisher · View at Google Scholar
  • Ievgeniia Kokol, “Research on manoeuvring capabilities of a nuclear power plant when switching in-use control programmes,” EasternEuropean Journal of Enterprise Technologies, vol. 2, no. 8, pp. 4–13, 2016. View at Publisher · View at Google Scholar
  • R. Pericas, K. Ivanov, F. Reventós, and L. Batet, “Comparison of Best-Estimate Plus Uncertainty and Conservative Methodologies for a PWR MSLB Analysis Using a Coupled 3-D Neutron-Kinetics/Thermal-Hydraulic Code,” Nuclear Technology, vol. 198, no. 2, pp. 193–201, 2017. View at Publisher · View at Google Scholar
  • F. Reventos, “Parameters and concepts,” Thermal-Hydraulics of Water Cooled Nuclear Reactors, pp. 89–141, 2017. View at Publisher · View at Google Scholar