Experimental investigation and validation of TASS/SMR-S code for single-phase and two-phase natural circulation tests with SMART-ITL facility
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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
Abstract
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
참고문헌 (17)
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