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논문 기본 정보

자료유형
학술저널
저자정보
Gao Pengcheng (Xi'an Jiaotong University) Zhang Bin (Xi'an Jiaotong University) Li Jishen (Xi'an Jiaotong University) Miao Fan (Xi'an Jiaotong University) Tang Shaowei (Xi'an Jiaotong University) Cao Sheng (Xi'an Jiaotong University) Yang Hao (Xi'an Jiaotong University) Shan Jianqiang (Xi'an Jiaotong University)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제55권 제3호
발행연도
2023.3
수록면
999 - 1,008 (10page)
DOI
10.1016/j.net.2022.11.023

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Deformed fuel rods can cause a partial blockage of the flow area in a subchannel. Such flow blockage will influence the core coolant flow and further the core heat transfer during the reflooding phase and subsequent severe accidents. Nevertheless, most of the system analysis codes simulate the accident process based on the assumed flow blockage ratio, resulting in inconsistencies between simulated results and actual conditions. This paper aims to study the influence of flow blockage in severe accident scenario of the CAP1400 reactor. First, the flow blockage model of ISAA code is improved based on the FRTMB module. Then, the ISAA-FRTMB coupling system is adopted to model and calculate the QUENCH-LOCA- 0 experiment. The correctness and validity of the flow blockage model are verified by comparing the peak cladding temperature. Finally, the DVI Line-SBLOCA accident is induced to analyze the influence of flow blockage on subsequent CAP1400 reactor core heat transfer and core degradation. From the results of the DVI Line-SBLOCA accident analysis, it can be concluded that the blockage ratio is in the range of 40%e60%, and the position of severe blockage is the same as that of cladding rupture. The blockage reduces the circulation area of the core coolant, which in turn impacts the heat exchange between the core and the coolant, leading to the early failure and collapse of some core assemblies and accelerating the core degradation process.

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