contributor author | Kinoshita, Ikuo | |
contributor author | Torige, Toshihide | |
contributor author | Yamada, Minoru | |
date accessioned | 2017-05-09T01:32:11Z | |
date available | 2017-05-09T01:32:11Z | |
date issued | 2016 | |
identifier issn | 2332-8983 | |
identifier other | NERS_2_2_021003.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/162194 | |
description abstract | Interfacial 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. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry | |
type | Journal Paper | |
journal volume | 2 | |
journal issue | 2 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4031377 | |
journal fristpage | 21003 | |
journal lastpage | 21003 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 002 | |
contenttype | Fulltext | |