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Experiments on the Integrity and Performance of the Passive Residual Heat Removal System for SMART design Using VISTA-ITL

Experiments on the Integrity and Performance of the Passive ...

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The Fifth China-Korea Workshop on Nuclear Reactor Thermal Hydraulics

作者： Byeong-Yeon Min Hyun-Sik Park Yong-Chul Shin Sung-Jae Yi Thermal Hydraulics Safety Research Division Korea Atomic Energy Research Institute （KAERI）989-111 Daedeok-daero Yuseong-gu Daejeon 305-353 Korea

The purpose of this paper is to verify the integrity and performance of the Passive Residual Heat Removal System （PRHRS） for SMART design during the steady state condition. The system’s overall thermal hydraulic behavior during the steady-state operation of the PRHRS of the SMART reactor was simulated using the VISTA-ITL, a small-scale integral effect test loop for SMART design. SMART’s PRHRS is a final heat sink to remove the decay heat from the nuclear reactor and the stored energy contained in structures in case of accident in the SMART plant. The PRHRS is a safety system designed with devices classified into safety levels considering a single failure. The PRHRS performance test using the VISTA-ITL is to test whether the PRHRS is operated properly when the reactor is shut down considering all the operating conditions of SMART plant. The steady-state PRHRS performance tests are divided into three conditions of 100% scaled power, 20% scaled power, and hot standby condition. The steady-state conditions were well operated to satisfy the initial test conditions presented in the test requirement and also its boundary conditions were properly simulated. The PRHRS’s natural circulation .low was formed as much as 10.1%, 11.7% and 9.1% for 100% scaled power, 20% scaled power, and hot standby condition, respectively. The experimental results show that PRHRS’s integrity and performance were well confirmed for those three conditions.

关键词： VISTA-ITL PRHRS Performance natural circulation .

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