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contributor authorSomers-Neal, Shawn
contributor authorNguyen, Vien
contributor authorMatida, Edgar
contributor authorTang, Vinh
contributor authorKaya, Tarik
date accessioned2022-02-04T22:59:37Z
date available2022-02-04T22:59:37Z
date copyright1/1/2020 12:00:00 AM
date issued2020
identifier issn2332-8983
identifier otherners_006_01_011110.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4275864
description abstractIn a reactor core meltdown under postulated severe accidents, the molten material called corium could be ejected or relocated through existing vessel penetrations. There exists, however, a potential for plugging of melt flow due to its complete solidification providing the availability of an adequate heat sink. Simulations of the melt flow in a horizontal tube were carried out to conduct a sensitivity study on the effect of key parameters on the melt penetration distance and bulk temperature distribution of the corium. The Reynolds number was varied from 10,000 to 20,000, inlet temperature was varied from 2600 K to 3000 K, the corium thermal conductivity was varied from 10 W/m·K to 20 W/m·K, and the pipe diameter was varied from 0.0095 m to 0.019 m. In addition, a comparison was made with an analytical model based on a modified Epstein's model and a previous numerical model. The study provided insight into the lower bound, which was found to be 98 mm, and the upper bound was 258 mm when predicting the potential penetration length of corium in horizontal pipes.
publisherThe American Society of Mechanical Engineers (ASME)
titleSensitivity Analysis of Unsteady Corium Solidification in an Initially Emptied Horizontal Turbulent Pipe Flow
typeJournal Paper
journal volume6
journal issue1
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4044747
journal fristpage011110-1
journal lastpage011110-9
page9
treeJournal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 001
contenttypeFulltext


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