Autors: Spasov, I. G., Mitkov, S., Kolev, N.P., Sanchez-Cervera, S., Garcia-Herranz, N., Sabater, A., Cuervo, D., Jimenez, J., Sanchez, V.H., Vyskocil, L.
Title: Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
Keywords: VVER, MSLB, Core boundary condition problem, Nodal methods,

Abstract: This paper summarizes the nodal level results from the VVER MSLB core simulation in the NURESAFE EU project. The main objective is to implement and verify new developments in the models and couplings of 3D core simulators for cores with hexagonal fuel assemblies. Recent versions of the COBAYA and DYN3D core physics codes, and the FLICA4 and CTF thermal-hydraulic codes were tested standalone and coupled through standardized coupling functions in the Salome platform. The MSLB core transient was analyzed in coupled code simulation of a core boundary condition problem derived from the OECD VVER MSLB benchmark. The impact of node sub-division and different core mixing models, as well as the effects of CFD computed core inlet thermal-hydraulic boundary conditions on the core dynamics were explored.

References

    Issue

    Nuclear Engineering and Design, vol. 321, pp. 26-37, 2017, Netherlands, Elsevier B.V., ISBN 0029–5493

    Copyright Elsevier B.V.

    Цитирания (Citation/s):
    1. Yuliia Filonova, Vladislav Filonov, Yaroslav Dubyk "Reactor Baffle Cooling CFD Framework for Swelling Assessment" 26th International Conference on Nuclear Engineering, London, England, July 22–26, 2018, ISBN: 978-0-7918-5153-1, ASME, doi:10.1115/ICONE26-82365 - 2018 - в издания, индексирани в Scopus или Web of Science
    2. V.Filonov, Y.Filonova, Y.Dubyk, A.Bohdan" CALCULATION OF VVER-1000 CORE BAFFLE TEMPERATURE DISTRIBUTION FOR IT'S SWELLING ASSESSMENT" Proceedings of Odessa Polytechnic University, Issue 1(60), 2020, ISSN 2076-2429 (print), ISSN 2223-3814 (online), DOI:10.15276/opu.1.60.2020.04 - 2020 - от чужди автори в чужди издания, неиндексирани в Scopus или Web of Science
    3. Yuliia Filonova, Yaroslav Dubyk, Vladislav Filonov, Vadym Kondratjuk "Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment" Journal of Nuclear Engineering and Radiation Science, ASME, Volume 7, Issue 1, January 2021, Published Online: June 12, 2020, ISSN 2332-8983, https://doi.org/10.1115/1.4047495 - 2021 - в издания, индексирани в Scopus или Web of Science
    4. Guan-Hua Qian, Ren Li, Tao Yang, Xu Wang, Peng-Cheng Zhao, Ya-Nan Zhao, Tao Yu “Platform development for multi-physics coupling and uncertainty analysis based on a unified framework” Nuclear Engineering and Technology, Korean Nuclear Society, 2023, ISSN 1738-5733, https://doi.org/10.1016/j.net.2023.02.010 - 2023 - в издания, индексирани в Scopus или Web of Science

    Вид: статия в списание, публикация в издание с импакт фактор, публикация в реферирано издание, индексирана в Scopus и Web of Science