Prediction of flow distribution of vertical upward co-current adiabatic annular flow in 8 × 8 rod bundle
Creators
- 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.2019.06.040Additional 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
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51008003
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- ACCIDENTS; BWR TYPE REACTORS; DROPLETS; FILM FLOW; FLOW RATE; FUEL ELEMENT CLUSTERS; FUEL RODS; PWR TYPE REACTORS; REACTOR SAFETY; SHEAR; STEADY-STATE CONDITIONS; STRESSES; THIN FILMS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FILMS; FLUID FLOW; FUEL ASSEMBLIES; FUEL ELEMENTS; PARTICLES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- © 2019 Elsevier Ltd. All rights reserved.