Published September 2010 | Version v1
Journal article

Analysis of subcooled boiling flow with one-group interfacial area transport equation and bubble lift-off model

  • 1. Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)
  • 2. Department of Nuclear Engineering, Seoul National University, Shillim-dong, San 56-1, Kwanak-gu, Seoul, 151-742 (Korea, Republic of)

Description

To enhance the multi-dimensional analysis capability for a subcooled boiling two-phase flow, the one-group interfacial area transport equation was improved with a source term for the bubble lift-off. It included the bubble lift-off diameter model and the lift-off frequency reduction factor model. The bubble lift-off diameter model took into account the bubble's sliding on a heated wall after its departure from a nucleate site, and the lift-off frequency reduction factor was derived by considering the coalescences of the sliding bubbles. To implement the model, EAGLE (elaborated analysis of gas-liquid evolution) code was developed for a multi-dimensional analysis of two-phase flow. The developed model and EAGLE code were validated with the experimental data of SUBO (subcooled boiling) and SNU (Seoul National University) test, where the subcooled boiling phenomena in a vertical annulus channel were observed. Locally measured two-phase flow parameters included a void fraction, interfacial area concentration, and bubble velocity. The results of the computational analysis revealed that the interfacial area transport equation with the bubble lift-off model showed a good agreement with the experimental results of SUBO and SNU. It demonstrates that the source term for the wall nucleation by considering a bubble sliding and lift-off mechanism enhanced the prediction capability for the multi-dimensional behavior of void fraction or interfacial area concentration in the subcooled boiling flow. From the point of view of the bubble velocity, the modeling of an increased turbulence induced by boiling bubbles at the heated wall enhanced the prediction capability of the code.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2010.04.001

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2010.04.001;
PII
S0029-5493(10)00250-5;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
240
Journal Issue
9
Journal Page Range
p. 2281-2294
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
2. workshop on experiments and CFD code applications to nuclear reactor safety
Acronym
XCFD4NRS
Dates
10-12 Sep 2008
Place
Grenoble (France)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
42014688
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BUBBLES; COALESCENCE; EXPERIMENTAL DATA; MANY-DIMENSIONAL CALCULATIONS; NUCLEATION; SIMULATION; SUBCOOLED BOILING; TRANSPORT THEORY; TURBULENCE; TWO-PHASE FLOW; VELOCITY; VOID FRACTION
Descriptors DEC
BOILING; DATA; FLUID FLOW; INFORMATION; NUMERICAL DATA; PHASE TRANSFORMATIONS

Optional Information

Copyright
Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.