Table of Contents Author Guidelines Submit a Manuscript
Science and Technology of Nuclear Installations
Volume 2010, Article ID 163279, 11 pages
Research Article

Influence of Modelling Options in RELAP5/SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity

1Faculty of Electrical Engineering and Computing, University of Zagreb, Unska 3, 10000 Zagreb, Croatia
2ENCONET d.o.o., Miramarska 20, 10000 Zagreb, Croatia
3NPP Krško, Engineering Department, Vrbina 12, 8270 Krško, Slovenia

Received 30 April 2009; Accepted 29 August 2009

Academic Editor: Alessandro Petruzzi

Copyright © 2010 Siniša Šadek 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. SCDAP/RELAP5 Development Team, “SCDAP/RELAP5/MOD3.2 Code Manuals, Vols. 1 to 5, NUREG/CR-6150, INEL-96/0422, Rev. 1,” INEEL, Idaho Falls, Idaho, USA, 1997.
  2. Fauske and Associates, Inc., “MAAP4—Modular Accident Analysis Program for LWR Power Plants, Vols. 1 to 3,” prepared for Electric Power Research Institute, 1994.
  3. K. Vierow, Y. Liao, J. Johnson, M. Kenton, and R. Gauntt, “Severe accident analysis of a PWR station blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 codes,” Nuclear Engineering and Design, vol. 234, no. 1–3, pp. 129–145, 2004. View at Publisher · View at Google Scholar · View at Scopus
  4. D. Grgic et al., “NEK RELAP5/MOD3.3 Nodalization Notebook (2000 MWt and new SGs),” NEK ESD TR 09/03, 2003.
  5. T. Bajs, V. Benčik, and S. Šadek, “NEK RELAP5/MOD3.3 Steady-State and On-Transient Qualification Report (Based on NEK ESD TR09/03),” NEK ESD TR 10/03, 2003.
  6. T. Bilić-Zabric and B. Glaser, “Krško MAAP Nodalization Notebook,” NEK ESD TR02/00, 2000.
  7. WOG Program MUHP-2310, “Severe Accident Management Guidance,” Westinghouse Electric Corporation, 1994.
  8. “Krško Individual Plant Examination Level 2,” WENX-95-24, Westinghouse Electric Corporation, 1995.
  9. T. Bilić-Zabric and I. Bašić, “NEK Plant Specific SAMG Strategies,” NEK ESD TR22/00, Rev. 1, 2002.
  10. T. Bilić-Zabric and I. Bašić, “Krško Severe Accident Management—Setpoint Calculation,” NEK ESD TR23/00, Rev. 1, 2002.
  11. T. Bilić-Zabric, I. Bašić, and J. Špiler, “Hydrogen behaviour in PWR containment evaluated with MAAP4.0.5,” in Proceedings of the 5th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids, pp. S4-4.1–S4-4.10, Dubrovnik, Croatia, 2004.
  12. NEK EOP-3.5, ECA-0.0, “Loss of all AC Power, Rev. 11,” 2002. View at Google Scholar
  13. “WOG 2000 Reactor Coolant Pump Seal Leakage Model for Westinghouse PWRs,” WCAP-15603, Rev. 1-A, 2003.
  14. “Natural Circulation in Water Cooled Nuclear Power Plants, Phenomena, Models and Methodology for System Reliability Assessments,” IAEA-TECDOC-1474, 2005.
  15. F. R. Larson and J. Miller, “A time temperature relationship for rupture and creep stress,” Transactions of the ASME, pp. 765–775, 1952. View at Google Scholar
  16. K.-I. Ahn and D.-H. Kim, “A state-of-the-art review of the reactor lower head models employed in three representative U.S. severe accident codes,” Progress in Nuclear Energy, vol. 42, no. 3, pp. 361–382, 2003. View at Publisher · View at Google Scholar · View at Scopus