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contributor authorYadav, Mahesh Kumar
contributor authorPunetha, Maneesh
contributor authorBhanawat, Abhinav
contributor authorKhandekar, Sameer
contributor authorSharma, Pavan K.
date accessioned2022-02-04T22:16:36Z
date available2022-02-04T22:16:36Z
date copyright9/4/2020 12:00:00 AM
date issued2020
identifier issn2332-8983
identifier otherners_006_04_041108.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4275241
description abstractHeat transfer coefficient (HTC) relations developed using steady-state experimental data are used for capturing the complete heat transport characteristic in a severe nuclear accident. It is important to verify the applicability of these correlation(s) at an early stage of the accident where heat transfer is transient in nature. In this paper, an experimental study is executed for this purpose. High-pressure steam (at 0.26 MPa (2.6 bar) and 0.41 MPa (4.1 bar) absolute pressure) is leaked into the closed containment initially filled with atmospheric air, and filmwise condensation is studied on an isothermally maintained vertical stainless steel test plate. During the experiment, temperature variation across the test plate at specified locations and inside the containment are recorded using the microthermocouples. The steam–air mixture composition is also examined using an online mass-spectrometry system. An inverse heat conduction (IHC) technique, validated using air-jet impingement heat transfer data, is used to estimate the time-varying condensation heat flux. It is found that the existing correlations based on the steady-state experimental data predict the transient condensation flux quite well, except in very early transient situation with a time scale of ∼20 s.
publisherThe American Society of Mechanical Engineers (ASME)
titleSteam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident
typeJournal Paper
journal volume6
journal issue4
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4046910
journal fristpage041108-1
journal lastpage041108-9
page9
treeJournal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 004
contenttypeFulltext


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