Published January 2019 | Version v1
Journal article

Flow visualization experiment in a two-side wall heated rectangular duct for turbulence model assessment in natural convection heat transfer

  • 1. Department of Energy System Engineering, Seoul National University, 1 Gwanak-ro, Gwannk-gu, Seoul (Korea, Republic of)
  • 2. Nuclear Hydrogen Reactor Technology Division, Korea Atomic Energy Research Institute, 111 Daedeok-daero 989 Beon-gil, Yuseong-gu, Daejeon (Korea, Republic of)

Description

Highlights: • Flow visualization methodology and wall temperature measurement strategy were established. • Velocity distribution and turbulence quantities were measured in a heated rectangular duct. • Secondary flows were observed at the corner of the rectangular test section. • RANS turbulence models have limitations in predicting the flow behaviors. - Abstract: Reactor Cavity Cooling System (RCCS) is one of the passive safety systems in Very High Temperature gas-cooled Reactor (VHTR). RCCS incorporates riser channels connected with a chimney to remove the residual heat emitted from the reactor vessel using natural circulation, and therefore, heat transfer phenomena in the RCCS riser duct is of great importance to ensure the safety of the VHTR. To enhance the understanding of heat transfer mechanism in a heated riser duct with rectangular shape, visualization of the local flow structure was conducted with an experimental facility for the natural convection heat transfer applying the Particle Image Velocimetry (PIV) method. With measured thermal boundary conditions by IR thermometry, CFD analysis was performed for the test facility using two different turbulence models. By comparing local flow structure from the experimental data and CFD calculation results, turbulence model assessment was conducted to confirm the prediction capability of the models. Experimental data show the magnitudes and locations of maximum velocity peak which is induced by buoyancy force and the anisotropic behaviors of velocity fluctuations near wall region. CFD calculations overestimate the maximum velocity near the wall compared with experimental data, and they seem to have limitations in reproducing the secondary flow observed at the corner of the test section in the experiment. The established methodology for flow visualization and the measurement strategy for thermal boundary conditions could contribute to obtain extensive experimental data and turbulence model assessment results, which would improve the understanding of the heat transfer mechanism to enhance the performance prediction capability for the passive heat removal system of the VHTR.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2018.11.012

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2018.11.012;
PII
S0029549318308306;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
341
Journal Page Range
p. 284-296
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
51056448
Subject category
S42: ENGINEERING;
Descriptors DEI
BOUNDARY CONDITIONS; DUCTS; FLOW VISUALIZATION; FORECASTING; NATURAL CONVECTION; REACTOR COOLING SYSTEMS; REACTOR VESSELS; TEMPERATURE MEASUREMENT; TEST FACILITIES; TURBULENCE; WALLS
Descriptors DEC
CONTAINERS; CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; HEAT TRANSFER; MASS TRANSFER; REACTOR COMPONENTS

Optional Information

Notes
© 2018 Elsevier B.V. All rights reserved.