Experiments on the Heat Transfer and Natural Circulation Characteristics of the Passive Residual Heat Removal System for an Advanced Integral Type Reactor
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概要
- 論文の詳細を見る
Experiments on the heat transfer characteristics and natural circulation performance of the passive residual heat removal system (PRHRS) for the SMART-P have been performed by using the high temperature/high pressure thermal-hydraulic test facility (VISTA). The VISTA facility consists of the primary loop, the secondary loop, the PRHRS loop, and the auxiliary systems to simulate the SMART-P, a pilot plant of the SMART. The primary loop is composed of the steam generator (SG) primary side, a simulated core, a main coolant pump, and the loop piping, and the PRHRS loop consists of the SG secondary side, a PRHRS heat exchanger, and the loop piping. The natural circulation performance of the PRHRS, the heat transfer characteristics of the PRHRS heat exchangers and the emergency cooldown tank (ECT), and the thermal-hydraulic behavior of the primary loop are intensively investigated. The experimental results show that the coolant flows steadily into the PRHRS loop and that the heat transfers through the PRHRS heat exchanger and the emergency cooldown tank are sufficient enough to enable a natural circulation of the coolant. The results also show that the core decay heat can be sufficiently removed from the primary loop with an operation of the PRHRS.
- 社団法人 日本原子力学会の論文
- 2007-05-25
著者
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PARK Hyun-Sik
Korea Atomic Energy Research Institute
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CHOI Ki-Yong
Korea Atomic Energy Research Institute
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CHO Seok
Korea Atomic Energy Research Institute
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SONG Chul-Hwa
Korea Atomic Energy Research Institute
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Chung Moon-Ki
Korea Atomic Energy Research Institute
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Song Chul-hwa
Korea Atomic Energy Res. Inst.
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PARK Choon-Kyung
Korea Atomic Energy Research Institute
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YI Sung-Jae
Korea Atomic Energy Research Institute
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