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Sensitivity Analysis of CFD Two-Phase Flow in a BWR Fuel Bundle
KTH, School of Engineering Sciences (SCI), Physics, Reactor Technology.
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
KTH, School of Engineering Sciences (SCI), Physics, Reactor Technology.ORCID iD: 0000-0001-5595-1952
2010 (English)Conference paper, Published paper (Refereed)
Abstract [en]

The goal of this work was to perform an investigation of the sensitivities of the average outlet void fraction and flow pattern prediction in the fuel assembly on important model parameters. The model sensitivities were examined on the following groups of parameters: numerical parameters (e.g. mesh discretization), operating conditions (input power, outlet pressure, mass flow rate and inlet temperature) and closure models for the interphase momentum (e.g. drag, virtual mass, lift, turbulent dispersion, wall lubrication). The average outlet void fraction was evaluated by the CFD code for the steady-state and model sensitivities were identified.

A significant sensitivity was recognized especially for changes of inlet temperature of coolant and system pressure. Moreover, the turbulent dispersion force and the wall lubrication force had a significant influence on vapor and liquid velocity profiles and also on the distribution of void at the outlet of the fuel assembly.

Place, publisher, year, edition, pages
2010. 1-15 p.
Keyword [en]
Two-phase flow, Boiling Water Reactor, CFD, Sensitivity analysis
National Category
Energy Engineering
Identifiers
URN: urn:nbn:se:kth:diva-81334OAI: oai:DiVA.org:kth-81334DiVA: diva2:497341
Conference
The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8)Shanghai, China, October 10-14, 2010
Note
QC 20120213Available from: 2012-02-13 Created: 2012-02-10 Last updated: 2012-03-20Bibliographically approved

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Anglart, Henryk

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