Show simple item record

contributor authorKinoshita, Ikuo
contributor authorTorige, Toshihide
contributor authorYamada, Minoru
date accessioned2017-05-09T01:32:11Z
date available2017-05-09T01:32:11Z
date issued2016
identifier issn2332-8983
identifier otherNERS_2_2_021003.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/162194
description abstractInterfacial friction in the core affects the twophase mixture level and the distribution of the dispersed gas phase during a smallbreak lossofcoolant accident (LOCA). The RELAP5/MOD3.2 code uses the drift flux model to describe the interfacial friction force in vertical dispersed flow, and the Chexal–Lellouche drift flux correlation is used for the rod bundle geometry. In the present study, the RELAP5 model uncertainty was quantified for the bubbly–slug interfacial friction model in the rod bundle geometry by conducting numerical analyses of void profile tests in the Thermal Hydraulic Test Facility (THTF) of the Oak Ridge National Laboratory (ORNL). The model uncertainty parameter was defined as a multiplier for the interfacial friction coefficient. Numerical analyses were performed by adjusting the multiplier so that the predicted void fractions agreed with the measured test data. The resultant distribution of the multipliers represented the interfacial friction model uncertainty.
publisherThe American Society of Mechanical Engineers (ASME)
titleUncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry
typeJournal Paper
journal volume2
journal issue2
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4031377
journal fristpage21003
journal lastpage21003
treeJournal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 002
contenttypeFulltext


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record