Table of Contents Author Guidelines Submit a Manuscript
Science and Technology of Nuclear Installations
Volume 2012, Article ID 646327, 25 pages
Research Article

Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM

1Innovative Systems Software, 1242 South Woodruff Avenue, Idaho Falls, ID 83404, USA
2ENCONET, Miramarska 20, 10000 Zagreb, Croatia
3ETSEIB, Universitat Politècnica de Catalunya, Avenida Diagonal 647, 08028 Barcelona, Spain
4Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Cuarto piso, Colonia Vertiz Narvarte, Delegacion Benito Juarez, 03020 Ciudad de México, DF, Mexico

Received 11 January 2012; Accepted 6 March 2012

Academic Editor: Alejandro Nuñez-Carrera

Copyright © 2012 C. M. Allison 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. C. M. Allison and J. K. Hohorst, “SDTP—developing technology for the nuclear industry,” in Proceedings of the 13th International Conference on Nuclear Engineering (ICONE13-50979), Beijing, China, May 2005.
  3. C. M. Allison and J. K. Hohorst, “Role of RELAP/SCDAPSIM in nuclear safety,” Science and Technology of Nuclear Installations, vol. 2010, Article ID 425658, 2010. View at Publisher · View at Google Scholar · View at Scopus
  4. C. M. Allison, R. J. Wagner, L. J Siefken, and J. K. Hohorst, “The development of RELAP5/SCDAPSIM/MOD4.0 for reactor system analysis and simulation,” in Proceedings of the 7th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids, Dubrovnik, Croatia, May 2008.
  6. S. Hagen, P. Hofmann, V. Noack, G. Schanz, G. Schumacher, and L. Sepold, “The CORA-program: out-of-pile experiments on severe fuel damage,” in Proceedings of the 5th International Topic Meeting on Nuclear Thermal Hydraulics, Operations, and Safety, Beijing, China, April 1997.
  7. D. J. Osetek, “Results of the four PBF severe fuel damage tests,” in Proceedings of the 15th Water Reactor Safety Information Meeting (NUREG/CP-0090), Gaithersburg, Md, USA, October 1987.
  8. E. W. Coryell, “Summary of Important Results and SCDAP/RELAP5 Analysis for OECD LOFT Experiment LP-FP-2,” Tech. Rep. NUREG/CR/6160, EGG-2721, Nuclear Energy Agency-Committee on the Safety of Nuclear Installations-R, 1994. View at Google Scholar
  9. RELAP5 Code Development Team, “RELAP5/MOD 3.3 code manual, Vol. 1–8,” NUREG/CR-5535/Rev1, December 2001.
  10. SCDAP/RELAP5 Development Team, “SCDAP/RELAP5/MOD3.2 code manual, Vol. 1–5,” NUREG/CR-6150, INEL-96/0422, July 1998.
  11. B. Tóth, A. Bieliauskas, G. Bandini et al., “Benchmark study on fuel bundle degradation in the phebus FPT2 test using state-of-the-art severe accident analysis codes,” Nuclear Technology, vol. 169, no. 2, pp. 81–96, 2010. View at Google Scholar · View at Scopus
  12. C. M. Allison and J. K. Hohorst, “An assessment of RELAP/SCDAPSIM/MOD3.4 using the phebus FPT-2 bundle heating and melting experiment,” in Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP '05), pp. 3284–3293, American Nuclear Society, Seoul, Republic of Korea, May 2005. View at Scopus
  13. J. H. Spencer et al., “Assessment of new modeling in RELAP/SCDAPSIM using experimental results from the Quench program,” in Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP '11), Nice, France, May 2011.
  14. C. M. Allison, “Recent improvements in RELAP/SCDAPSIM/MOD3.4 resulting from QUENCH and PARAMETER bundle heating and quenching experiments,” in Proceedings of the 8th International Conference of Nuclear Options in Countries with Small and Medium Electricity Grids, Dubrovnik, Croatia, 2010.
  15. S. Hagen, P. Hofmann, V. Noack, L. Sepold, G. Schanz, and G. Schumacher, Large Bundle PWR Test CORA-18: Test Results, Forschungszentrum Karlsruhe—FZKA-6031, 1998,
  16. P. Hofmann, “Metallographic examination of the severe fuel damage scoping test (SFD-ST) fuel rod bundle cross sections,” NUREG/CR-5119, EGG-2537, 1988.
  17. A. Stefanova et al., “SARNET benchmark on QUENCH-11—final report,” Forschungszentrum Karlsruhe—FZKA 7368, 2008,