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- W3143770144 abstract "Nowadays, nuclear reactor safety simulations of real nuclear plants are still performed using approximated system codes which rely on one-dimensional lumped-parameters or subchannel methods. Many of these one-dimensional codes are not able to fully simulate intrinsic multi-dimensional effects that occur within a nuclear reactor. On the other hand, Computational Fluid Dynamics (CFD) codes, thanks to the recent advances in computer technology, are now capable of tackling complex multi-dimensional fluid-dynamics problems for a large variety of nuclear and non-nuclear applications. The neutronics code Point Kinetics Multi-Purpose Online Neutronic code (PoKiMON), has been developed in order to provide realistic 1-D neutronics feedbacks to the CFD one. The goal of this work is then to extend the range of applications of coupled neutronics/CFD simulations towards boron ingress shutdown scenarios in light water small modular reactors. The coupled system was also verified considering two fuel assembly-level calculations against the code SUBCHANFLOW, a heat decay calculation against classic decay heat equation and was validated considering the IFA-507 experiment performed at the Halden reactor facility." @default.
- W3143770144 created "2021-04-13" @default.
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- W3143770144 date "2021-08-01" @default.
- W3143770144 modified "2023-09-27" @default.
- W3143770144 title "Development and coupling of the 1-D neutronics code PoKiMON with ANSYS CFX for reactor shutdown simulations" @default.
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- W3143770144 doi "https://doi.org/10.1016/j.nucengdes.2021.111174" @default.
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