Autors: Mitkov S., Spasov, I. G., Kolev, N. P.
Title: Simulation of a hypothetical MSLB core transient in VVER-1000 with several stuck rods
Keywords: MSLB, RIA, coupled neutronic/thermal hydraulic calculation,

Abstract: A hypothetical main steam line break transient in a VVER-1000 core with multiple equipment faults was simulated with the coupled COBAYA4/CTF and COBAYA3/FLICA4 nodal core models. The objective was to test recent versions of the models developed in the EU NURISP and NURESAFE projects and to analyze the thermal-hydraulic conditions in the hot assembly at the pin-cell level. The accident scenario was specified as an aggravated variant of the OECD/NEA VVER-1000 MSLB benchmark with eight peripheral control rod clusters stuck out of the core after scram, all of them in the overcooled sector. Coarse-mesh models and a realistic cross-section library were used to compute the full-core behavior with pre-calculated MSLB boundary conditions and to identify the hot assembly. Then a sub-channel thermal-hydraulic analysis of the hot assembly was performed with the CTF code, using time-dependent assembly boundary conditions from the coarse-mesh vessel and core simulation.

References

    Issue

    Kerntechnik, vol. 83, issue 4, pp. 389-395, 2018, Germany, Carl Hanser Verlag GmbH, ISSN 0932-3902

    Copyright Carl Hanser Verlag GmbH

    Цитирания (Citation/s):
    1. Uvakin M.A., Nikolaev A.L., Antipov M.V., Makhin I.V., Artificial intelligence methods application for reactor dynamics predicting in the tasks of maneuverable modes safety assessment, 2025, Annals of Nuclear Energy, issue 0, vol. 215, DOI 10.1016/j.anucene.2025.111248, issn 03064549, eissn 18732100 - 2025 - в издания, индексирани в Scopus

    Вид: статия в списание, публикация в издание с импакт фактор, публикация в реферирано издание, индексирана в Scopus