Published September 2021 | Version v1
Journal article

Measurement of forced convection subcooled boiling flow and rod surface temperature distribution

  • 1. Nuclear Reactor Technology Laboratory, Central Research Institute of Electric Power Industry, 1-6-1 Otemachi, Chiyoda-ku, Tokyo 100-8126 (Japan)

Description

Highlights: • High resolution temperature distribution along with a heated rod surface was measured. • Bubble transport behavior was three-dimensionally reconstructed, and turbulence velocity was obtained. • Void fraction and interfacial area transport, etc. for radial direction were measured with an optical double probe. • Forced convection subcooled boiling flow was measured simultaneously with the three measurement techniques and CFD-grade two-phase flow parameters were obtained. In order to obtain high-resolution data for modelling of boiling two-phase flow and its validation, we designed and constructed a test loop with a vertical annulus flow path and conducted subcooled boiling experiments to investigate subcooled bubble incipience and its development process under atmospheric condition. Three kinds of the state-of-the art measurement techniques were applied to quantify key parameters such as radial and vertical distributions of void fraction, bubble velocity, interfacial area concentration (IAC), Sauter mean diameters, high-resolution temperature distribution on rod surface, bubble transport behavior, and turbulent velocity components as well as onset of nucleate boiling (ONB), and onset of significant void (OSV).

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2021.111323

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2021.111323;
PII
S0029549321002752;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
381
Journal Page Range
vp.
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2021 The Author(s). Published by Elsevier B.V.