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contributor authorBhowmik, Palash K.
contributor authorSchlegel, J. P.
contributor authorKalra, V.
contributor authorMills, C.
contributor authorUsman, S.
date accessioned2022-02-05T21:53:58Z
date available2022-02-05T21:53:58Z
date copyright4/16/2021 12:00:00 AM
date issued2021
identifier issn2332-8983
identifier otherners_007_03_031406.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4276539
description abstractDesigning a novel scaled modular test facility as a part of an experiment for condensation heat transfer (CHT) in small modular reactors (SMRs) is the main focus of this study. This facility will provide data to evaluate models' scalability for predicting heat transfer in the passive containment cooling system (PCCS) of SMR. The nuclear industry recognizes SMRs as future candidates for clean, economic, and safe energy generation. However, licensing requires proper evaluation of the safety systems such as PCCS. The knowledge gap from the literature review showed a lack of high-resolution experimental data for scaling of PCCS and validation of computational fluid dynamics tools. In addition, the presently available test data are inconsistent due to unscaled geometric and varying physics conditions. These inconsistencies lead to inadequate test data benchmarking. To fill this research gap, this study developed three scaled (different diameters) condensing test sections with annular cooling for scale testing and analysis. This facility considered saturated steam as the working fluid with noncondensable gases like nitrogen and helium in different mass fractions. This facility also used a precooler unit for inlet steam conditioning and a postcooler unit for condensate cooling. The high fidelity sensors, instruments, and data acquisition systems are installed and calibrated. Finally, facility safety analysis and shakedown tests are performed.
publisherThe American Society of Mechanical Engineers (ASME)
titleDesign of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis
typeJournal Paper
journal volume7
journal issue3
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4050211
journal fristpage031406-1
journal lastpage031406-11
page11
treeJournal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 003
contenttypeFulltext


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