The research on reflooding heat transfer in nuclear reactor large break loss of coolant accident

Xinwei Zhang; Junbo Zhou

doi:10.1117/12.3004864

11 October 2023 The research on reflooding heat transfer in nuclear reactor large break loss of coolant accident

Xinwei Zhang, Junbo Zhou

Proceedings Volume 12800, Sixth International Conference on Computer Information Science and Application Technology (CISAT 2023); 128003H (2023) https://doi.org/10.1117/12.3004864
Event: 6th International Conference on Computer Information Science and Application Technology (CISAT 2023), 2023, Hangzhou, China

Abstract

Large break loss of coolant accident is one of the benchmark accidents in nuclear reactor design, and its reflooding process involves complex two-phase flow and heat transfer, which has been a hot spot of research in various countries. Simulating the re-flooding process by thermal hydraulic analysis procedure is of great significance to ensure reactor safety and determine the design parameters of nuclear power plants. In this paper, the FLECHT SEASET experiment is selected to perform validation calculations on the reflooding model of RELAP5 program and cosSyst program, which proves the rationality of its calculation of re-flooding heat transfer. And the effect law of coolant inlet flow rate, system pressure, coolant temperature, initial temperature of the envelope, and heating rod power on the re-flooding process was investigated by cosSyst.

(2023) Published by SPIE. Downloading of the abstract is permitted for personal use only.

Citation Download Citation

Xinwei Zhang and Junbo Zhou "The research on reflooding heat transfer in nuclear reactor large break loss of coolant accident", Proc. SPIE 12800, Sixth International Conference on Computer Information Science and Application Technology (CISAT 2023), 128003H (11 October 2023); https://doi.org/10.1117/12.3004864

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