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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2022.2
- 수록면
- 554 - 564 (11page)
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초록· 키워드
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The natural circulation phenomena occurring in fully integrated nuclear reactors are associated with aunique formation mechanism. The phenomenon results from a structural feature of these reactorsinvolving upward flow from the core, located in the central-bottom region of a single vessel, anddownward flow to the steam generator in the annulus region. In this study, to understand the naturalcirculation in a single vessel involving a multi-layered flow path, single-phase and two-phase naturalcirculation tests were performed using the SMART-ITL facility, and validation analysis of the TASS/SMR-Scode was performed by comparing the corresponding test results. Three single-phase natural circulationtests were sequentially conducted at 15%, 10%, and 5% of full-scaled core-power without RCP operation,following which a two-phase natural circulation test was successively conducted with an artificialdischarge of coolant inventory. The simulation capability of the TASS/SMR-S code with respect to thenatural circulation phenomena was validated against the test results, and somewhat conservative butreasonably comparative results in terms of overall thermalhydraulic behavior were shown
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