Abstract
This paper deals with the assessment of the fully integrated three-dimensional thermal–hydraulic and neutron kinetic modeling capability of the Relap5-3D system code. The interest in integrated system codes is growing in the field of safety analyses, where coupled three-dimensional simulations can significantly improve the level of understanding of spatial core phenomena in accident conditions. For this purpose, an asymmetric design basis accident, namely a main steam line break, has been simulated for a commercial 1200-MWe pressurized water reactor. The simulation has been performed with a one-dimensional plant model, including all the major primary, secondary and safety systems included in advanced PWR designs, upgraded with a three-dimensional thermal–hydraulic representation of the reactor vessel and a three-dimensional neutron kinetic core model. The analysis demonstrated the code capability to capture 3D core phenomena, not achievable with 1D plant model based on point kinetic.
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Notes
For TH analysis, it is not necessary simulating each fuel assembly individually and it is convenient to group them by TH similarity, in collapsed equivalent assemblies. If a higher level of detail is locally required, the detailed simulation of the fuel assembly of interest should be performed. This is out of the scope of the present work and could be considered as a next step of the 3D code assessment activity.
Please note that the predicted core behavior is based on the conservative assumptions made to highlight local phenomena as well as on the application of physical properties derived from a different reactor. This is consistent with the purpose of the activity, that is to show 3D TH–NK-coupled calculation capability through the analysis of a commercial size PWR transient. The results here presented shall not be considered applicable to the AP1000™ reactor, for which the safety demonstration publicly available applies.
References
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G. Saiu, F. D’Auria, A. Lo Nigro, A. Spadoni, MSLB coupled 3D neutronics-thermal hydraulics analysis of a large PWR using RELAP5-3D, in Acts of International Conference Nuclear Energy for Central Europe (Portoroz, Slovenia, 2001)
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Disclaimer: "The Westinghouse AP1000™ has been considered as reference plant, while core neutron kinetic parameters have been derived from available literature data on Three Miles Island NPP (TMI-1). It shall be clarified that the purpose of this report is limited to show 3D TH–NK coupled calculation capabilities under commercial size PWRs representative operating and design conditions, as well as under conservative assumptions made to highlight local phenomena. The results here presented shall not be considered in any way applicable or associated to the AP1000™ plant, for which the safety demonstration publicly available applies.
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Palmero, M. Coupled 3D thermal–hydraulic and neutron kinetic Relap5 model for transient analysis of a 1200-MWe nuclear PWR plant. Eur. Phys. J. Plus 135, 725 (2020). https://doi.org/10.1140/epjp/s13360-020-00628-w
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DOI: https://doi.org/10.1140/epjp/s13360-020-00628-w