State-of-the-art and review of condensation heat transfer for small modular reactor passive safety: Experimental studies

被引:20
作者
Bhowmik, Palash K. [1 ,2 ]
Schlegel, Joshua P. [1 ]
Revankar, Shripad [3 ]
机构
[1] Dept Nucl Engn & Radiat Sci, Missouri S&T, 1201 N State St, Rolla, MO 65409 USA
[2] Dept Irradiat Expt Thermal Anal, Idaho Natl Lab, 1955 N Fremont Ave, Idaho Falls, ID 83415 USA
[3] Purdue Univ Sch Nucl Engn, 400 Cent Dr, W Lafayette, IN 47907 USA
关键词
Condensation; Heat transfer; Experiment; Small modular reactor; Safety; CONTAINMENT COOLING SYSTEM; STEAM CONDENSATION; FILM CONDENSATION; VERTICAL TUBE; NONCONDENSABLE GASES; TRANSFER COEFFICIENT; VAPOR CONDENSATION; MASS-TRANSFER; PLANT SAFETY; CFD;
D O I
10.1016/j.ijheatmasstransfer.2022.122936
中图分类号
O414.1 [热力学];
学科分类号
摘要
This study focused on state-of-the-art and review of condensation heat transfer for small modular reactors (SMR). Nuclear reactors adopt passive containment cooling systems (PCCS) for accident mitigation, containment integrity, and primarily to maintain the last barrier for radioactive particle release to the environment during and beyond design-basis accidents. However, improving the effectiveness of the PCCS is more critical for the SMR than for commercial reactors to ensure higher safety margins and compactness. In the PCCS of SMR, due to its smaller size containment, the filmwise condensation (FWC) is dominant. Therefore, this study emphasized the FWC. Earlier condensation studies for the PCCS did not make SMR the primary focus, so a critical review for formulating the state-of-the-art was necessary. Part-1 of this study covered the review of physics phenomena, previous experimental studies with a brief overview of associated test facilities and empirical correlations. This study identified a research gap with the condensation test data scaling relations by using the information and findings of the previous PCCS studies and applied them to the SMR system.(c) 2022 Elsevier Ltd. All rights reserved.
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页数:21
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