Published May 2015 | Version v1
Miscellaneous

CFD modeling of supercritical water heat transfer in a vertical bare tube upward flow

  • 1. Applied Computational Fluid Dynamics Analysis, Thornhill, Ontario (Canada)
  • 2. Concentration, Heat and Momentum Limited, Wimbledon, London (United Kingdom)
  • 3. University of Ontario Institute of Technology, Oshawa, Ontario (Canada)
  • 4. National Research Tomsk Polytechnic University, Tomsk (Russian Federation)

Description

A customized Computational Fluid Dynamics (CFD) model of supercritical water (SCW) heat transfer in a vertical tube upward flow is developed and partially validated using experimental data obtained under the operating conditions typical for SCW cooled reactors (SCWRs): at a pressure of 24 MPa, an inner tube diameter of 10 mm, an inlet temperature of 320 or 350degC and a heated tube length of 4 m. The three values of mass flux (500, 1000 and 1500 kg/m2s) and various values of wall heat flux (from 141 to 729 kW/m2) are considered. Physical properties of SCW are calculated by using the REFPROP software from National Institute of Standards and Technology (NIST). The model has been incorporated into the commercial general-purpose CFD software, PHOENICS. Various turbulence models and numerical grid settings are tested. The study has demonstrated a good agreement between the CFD predictions and the experimental data on the inside tube wall temperature and heat transfer coefficient with use of a two-layer low-Reynolds-number k-ε turbulence model. However, a further model development is required under the conditions of significant effects of buoyancy force on heat transfer characteristics (the conditions of low values of mass flux and high values of wall heat flux). Practical recommendations are made regarding potential model applications in 3D analyses of SCWRs. (author)

Part of:
Proceedings of the 23th international conference on nuclear engineering (ICONE-23)

Additional details

Publishing Information

Imprint Title
Proceedings of the 23th international conference on nuclear engineering (ICONE-23)
Imprint Pagination
[3737 p.]
Journal Page Range
[11 p.]

Conference

Title
23. international conference on nuclear engineering
Acronym
ICONE-23
Dates
17-21 May 2015
Place
Chiba (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
48046457
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; FLUID FLOW; FLUID MECHANICS; HEAT TRANSFER; PHYSICAL PROPERTIES; REYNOLDS NUMBER; SUPERCRITICAL STATE; TUBES; WATER; WATER COOLED REACTORS
Descriptors DEC
DIMENSIONLESS NUMBERS; ENERGY TRANSFER; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; REACTORS; SIMULATION

Optional Information

Notes
Available as DVD-ROM Data in PDF format. Folder Name: FullPaper; Paper ID: ICONE23-1163.pdf; 23 refs., 11 figs., 1 tab.