Published January 2018 | Version v1
Journal article

CFD prediction of critical heat flux in vertical heated tubes with uniform and non-uniform heat flux

  • 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213 (China)
  • 2. Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695 (United States)
  • 3. Department of Engineering Physics, Tsinghua University, Beijing 100084 (China)

Description

Highlights: • Eulerian two-fluid model coupled with extended wall boiling model within a CFD code. • Simulation of DNB in vertical heated tubes under high pressures with STAR-CCM+ 10.04. • New methods developed to predict CHF in both uniform and non-uniform heated tubes. • The results showed some differences between uniform and non-uniform heated cases. - Abstract: In this paper, Eulerian Two-fluid model coupled with extended wall boiling model was used to simulate the departure from nucleate boiling (DNB) in vertical heated tubes under high pressures by using STAR-CCM+ 10.04. Based on CFD approach, new methods were developed to predict the critical heat flux (CHF) in both uniform and non-uniform heated tubes. The results showed some differences between the uniform and non-uniform heated cases. The transition in boiling curves was used as the criterion of DNB for uniform heat flux while the peaks of wall temperature and near wall void fraction were used for non-uniform cases. Good agreement was obtained between the predictions and experimental data, including both the values of critical heat flux and their locations. For uniform heat flux, sensitivity analysis for pressure, local quality and mass flow rate were performed, and the results showed that the new prediction method could work well under a wide range of conditions except under the high local quality and low mass flow rate conditions. The mechanism of this prediction method was discussed as well.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2017.11.009

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2017.11.009;
PII
S0029549317305137;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
326
Journal Page Range
p. 403-412
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
50070958
Subject category
S42: ENGINEERING; S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
CRITICAL HEAT FLUX; DEPARTURE NUCLEATE BOILING; EXPERIMENTAL DATA; FLOW RATE; FORECASTING; MATHEMATICAL MODELS; PRESSURE RANGE MEGA PA 10-100; SENSITIVITY ANALYSIS; SIMULATION; SUBCOOLED BOILING; TUBES; VOID FRACTION
Descriptors DEC
BOILING; DATA; HEAT FLUX; INFORMATION; NUCLEATE BOILING; NUMERICAL DATA; PHASE TRANSFORMATIONS; PRESSURE RANGE; PRESSURE RANGE MEGA PA

Optional Information

Copyright
Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.