Published October 2019 | Version v1
Journal article

Prediction of flow distribution of vertical upward co-current adiabatic annular flow in 8 × 8 rod bundle

  • 1. School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907-1290 (United States)
  • 2. Mechanical Engineering Department, Virginia Tech, Blacksburg, VA 24061 (United States)

Description

Highlights: • A method to predict velocity profile in rod bundle has been proposed. • Gas velocity distribution can be simplified to turbulent velocity distribution. • Liquid velocity distribution can be derived by interfacial shear stress correlation. • The predictions show reasonable agreement with data. - Abstract: Annular flow in rod bundle occurs frequently in boiling water reactor (BWR) under normal operation and in pressurized water reactor (PWR) under accident conditions. When annular flow occurs, rod film thickness is one of the most important parameters for safety concern. In order to calculate rod film thickness distribution inside rod bundle, both gas and liquid velocity distribution inside rod bundle is necessary. Also, flow distribution inside rod bundle is of importance for calculation of interfacial shear stress and other parameters in each sub-channel. However, entrained droplets in gas core can sharpen the gas velocity profile while existing rods can flatten the gas velocity profile, making it different from that of single phase flow. The liquid velocity distribution inside rod bundle is hard to obtain from experiment because of the complex structure of its geometry. Due to these reasons, this paper deducts gas and liquid velocity profiles from existing adiabatic rod film thickness data. Even the gas velocity profiles for different flow conditions are different, there exists a gas velocity profile that can be applied to all current flow conditions with minimum uncertainties. Based on that gas velocity profile, liquid velocity profile can be calculated. From these flow velocity profiles, film thickness on each rod and interfacial shear stress in each sub-channel can be calculated.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2019.06.040

Additional details

Identifiers

DOI
10.1016/j.anucene.2019.06.040;
PII
S0306454919303597;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
132
Journal Page Range
p. 555-562
ISSN
0306-4549
CODEN
ANENDJ

Optional Information

Notes
© 2019 Elsevier Ltd. All rights reserved.