Open Access
EPJ Nuclear Sci. Technol.
Volume 3, 2017
Article Number 20
Number of page(s) 9
Published online 23 June 2017
  1. T.G. Theofanous, C. Liu, S. Addition, S. Angelini, O. Kymalainen, T. Salimassi, In-vessel coolability and retention of a core melt, Nucl. Eng. Des. 169, 1 (1997) [CrossRef]
  2. M. Fischer, P. Levi, G. Langrock, A.A. Sulatsky, E.V. Krushinov, The impact of thermal chemical phenomena on the heat fluxes into the RPV during in-vessel melt retention, in Proceedings of Int. Congress on Advances in Nuclear Power Plants ICAPP 2011, Nice, France (2011)
  3. D.F. Tsurikov, V.F. Strizhov, S.V. Bechta, V.N. Zagriazkin, N.P. Kiselev, Main results of MASCA1 and 2 projects Tech. rep., RRC Kurchatov Institute, 2007
  4. J.M. Bonnet, J.M. Seiler, In-vessel corium pool thermal-hydraulics for bounding cases, in Proceedings of salt test expert group meeting RASPLAV seminar, Munich, Germany (2000)
  5. J.M. Seiler, B. Tourniaire, A phenomenological analysis of melt progression in the lower head of a pressurized water reactor, Nucl. Eng. Des. 268, 87 (2014) [CrossRef]
  6. H. Esmali, M. Khatib-Rahbar, Analysis of likelihood of lower head failure and ex-vessel fuel coolant interaction energetics for AP1000, Nucl. Eng. Des. 235, 1583 (2005) [CrossRef]
  7. J.L. Rempe, D.L. Knudson, C.M. Allison, G.L. Thinnes, C.L. Atwood, M.J. Cebull, Potential for AP600 in-vessel retention through ex-vessel flooding, Tech. Report, INNEL/EXT-97-00779, 1997
  8. Fauske Associates Inc., MAAP4 - modular accident analysis program for LWR power plants: Code structure and theory (Electric Power Research Institute, 1994), Vol. 2, Chap. 1
  9. R.O. Gauntt, J.E. Cash, R.K. Cole, C.M. Erickson, L.L. Humphries, S.B. Rodriguez, M.F. Young, MELCOR computer code manual, NUREG/CR-6119, Rev. 3 (2 vols), 2005
  10. T. Haste, M. Steinbruck, M. Barrachin, O. de Luze, M. Grosse, J. Stuckert, A comparison of core degradation phenomena in the CORA, QUENCH, Phébus SFD and Phébus FP experiments, Nucl. Eng. Des. 283, 1 (2015) [CrossRef]
  11. B.R. Sehgal et al., in Nuclear safety in light water reactors (Academic Press, Boston, 2012), pp. 89–183
  12. T.J. Haste, B. Adroguer, U. Brockmeier, P. Hofmann, K. Muller, M. Pezzilli, In-vessel core degradation in LWR severe accidents ECSC-EC-EAEC (European Commission, Brussels, 1996)
  13. J.-P. van Dorsselaere, C. Seropian, P. Chatelard, F. Jacq, J. Fleurot, P. Giordano, N. Reinke, B. Schwinges, H.-J. Allelein, W. Luther, The ASTEC integral code for severe accident simulation, Nucl. Technol. 165, 293 (2009) [CrossRef]
  14. B. Tourniaire, B. Spindler, G. Ratel, J.M. Seiler, M. Iooss, B. Marqes, F. Gaudier, G. Greffier, The LEONAR code: a new tool for PSA level 2 analyses, in Proceedings of Joint OECD/NEA - EC/SARNET2 Workshop on In-Vessel Coolability, Paris, France (2009), Vol. NEA/CSNI/R(2010)11, pp. 105–121
  15. F. Gaudier, URANIE: the CEA/DEN uncertainty and sensitivity platform, Proc. Soc. Behav. Sci. 2, 7660 (2010) [CrossRef]
  16. J.M. Broughton, P. Kuan, D.A. Petti, E.L. Tolman, A scenario of the Three Mile Island unit 2 accident, Nucl. Technol. 87, 34 (1989) [CrossRef]
  17. R. Le Tellier, L. Saas, S. Bajard, Transient stratification modelling of a corium pool in a LWR vessel lower head, Nucl. Eng. Des. 287, 1 (2014)
  18. M. Salay, F. Fichot, Modelling of metal-oxide corium stratification in the lower plenum of a reactor vessel, in Proceedings of Int. Topical Meeting on Nuclear Thermal-Hydraulics (NURETH-11), Avignon, France (2005)
  19. C. Villermaux, Modélisation physique et numérique de la convection naturelle dans une couche de fluide de faible rapport d’aspect dans le cadre des études d’accidents graves de réacteurs à eau sous pression, Ph.D. Thesis, Institut National Polytechnique de Grenoble, 1999

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