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논문 기본 정보

자료유형
학술저널
저자정보
김문수 (한국과학기술원) 정용훈 (한국과학기술원)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제12호
발행연도
2020.12
수록면
2,743 - 2,759 (17page)
DOI
https://doi.org/10.1016/j.net.2020.05.014

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초록· 키워드

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A detailed computational fluid dynamics (CFD) simulation analysis model was developed using ANSYSCFX 16.1 and analyzed to simulate the basic design and internal flow characteristics of a 180 MW smallmodular reactor (SMR) with a natural circulation flow system. To analyze the natural circulation phenomena without a pump for the initial flow generation inside the reactor, the flow characteristics wereevaluated for each output assuming various initial powers relative to the critical condition. The eddyphenomenon and the flow imbalance phenomenon at each output were confirmed, and a flow levelingstructure under the core was proposed for an optimization of the internal natural circulation flow. In thesteady-state analysis, the temperature distribution and heat transfer speed at each position consideringan increase in the output power of the core were calculated, and the conceptual design of the SMR had asufficient thermal margin (31.4 K). A transient model with the output ranging from 0% to 100% wasanalyzed, and the obtained values were close to the Thot and Tcold temperature difference value estimatedin the conceptual design of the SMR. The K-factor was calculated from the flow analysis data of the CFXmodel and applied to an analysis model in RELAP5/MOD3.3, the optimal analysis system code for nuclearpower plants. The CFX analysis results and RELAP analysis results were evaluated in terms of the internalflow characteristics per core output. The two codes, which model the same nuclear power plant, havedifferent flow analysis schemes but can be used complementarily. In particular, it will be useful to carryout detailed studies of the timing of the steam generator intervention when an SMR is activated. Thethermal and hydraulic characteristics of the models that applied porous media to the core & steamgenerators and the models that embodied the entire detail shape were compared and analyzed. Althoughthere were differences in the ability to analyze detailed flow characteristics at some low powers, it wasconfirmed that there was no significant difference in the thermal hydraulic characteristics' analysis of theSMR system's conceptual design

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