Assessment of reactor vessel integrity (ARVI)

B.R. Sehgal (Corresponding Author), A. Theerthan, A. Giri, A. Karbojian, H.G. Willschütz, O. Kymäläinen, S. Vandroux, J.M. Bonnet, J.M. Seiler, Kari Ikonen, Risto Sairanen, S. Bhandari, M. Bürger, M. Buck, W. Widmann, J. Dienstbier, Z. Techy, P. Kostka, R. Taubner, T. TheofanousT.N. Dinh

    Research output: Contribution to journalArticleScientificpeer-review

    53 Citations (Scopus)

    Abstract

    The cost-shared project ARVI (assessment of reactor vessel integrity) involves a total of nine organisations from Europe and USA. The objective of the ARVI Project is to resolve the safety issues that remain unresolved for the melt vessel interaction phase of the in-vessel progression of a severe accident. The work consists of experiments and analysis development. Four tests were performed in the EC-FOREVER Programme, in which failure was achieved in-vessels employing the French pressure vessel steel. The tests were analysed with the commercial code ANSYS-Multiphysics, and the codes SYSTUS+ and PASULA, and quite good agreement was achieved for the failure location. Natural convection experiments in stratified pools have been performed in the SIMECO and the COPO facilities, which showed that much greater heat is transferred downwards for immiscible layers or before layers mix. A model for gap cooling and a set of simplified models for the system codes have been developed. MVITA code calculations have been performed for the Czech and Hungarian VVERs, towards evaluation of the in-vessel melt retention accident management scheme.

    Tests have been performed at the ULPU facility with organised flow for vessel external cooling. Considerable enhancement of the critical heat flux (CHF) was obtained. The ARVI Project has reached the halfway stage. This paper presents the results obtained thus far from the project.
    Original languageEnglish
    Pages (from-to)23-53
    Number of pages31
    JournalNuclear Engineering and Design
    Volume221
    Issue number1-3
    DOIs
    Publication statusPublished - 2003
    MoE publication typeA1 Journal article-refereed
    EventFISA 2001 - EU Research in Reactor Safety: mid-term symposium on shared-cost and concerted actions - , Luxembourg
    Duration: 12 Nov 200114 Nov 2001

    Keywords

    • critical heat flux
    • nuclear reactor accidents
    • nuclear reactor safety
    • nuclear reactors

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  • Cite this

    Sehgal, B. R., Theerthan, A., Giri, A., Karbojian, A., Willschütz, H. G., Kymäläinen, O., Vandroux, S., Bonnet, J. M., Seiler, J. M., Ikonen, K., Sairanen, R., Bhandari, S., Bürger, M., Buck, M., Widmann, W., Dienstbier, J., Techy, Z., Kostka, P., Taubner, R., ... Dinh, T. N. (2003). Assessment of reactor vessel integrity (ARVI). Nuclear Engineering and Design, 221(1-3), 23-53. https://doi.org/10.1016/S0029-5493(02)00343-6