Local Interfacial Structure of Subcooled Boiling Flow in a Heated Annulus

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概要

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• Local measurements of flow parameters were performed for vertical upward subcooled boiling flows in an internally heated annulus. The annulus channel consisted of an inner heater rod with a diameter of 19.0 mm and an outer round tube with an inner diameter of 37.5 mm, and the hydraulic equivalent diameter was 18.5 mm. The double-sensor conductivity probe method was used for measuring the local void fraction, interfacial area concentration, bubble Sauter mean diameter and gas velocity, whereas the miniature Pitot tube was used for measuring the local liquid velocity. A total of 32 data sets were acquired consisting of various combinations of heat flux, 88.1–350.9 kW/m2, mass flux, 469.7–1061.4 kg/(m2 s) and inlet liquid temperature, 83.8–100.5°C. Six existing drift-flux models, six existing correlations of the interfacial area concentration and bubble layer thickness model were evaluated using the data obtained in the experiment.

• 社団法人 日本原子力学会の論文

著者

• HIBIKI Takashi

  School of Nuclear Engineering, Purdue University

• Hibiki Takashi

  School Of Nuclear Engineering Purdue Univ.

• YUN Byong-Jo

  Korea Atomic Energy Research Institute

• Kim Seong-o

  Fast Reactor Development Division Korea Atomic Energy Research Institute

• PARK Goon-Cherl

  Department of Nuclear Engineering, Seoul National University

• Park Goon-cherl

  Department Of Nuclear Engineering Seoul National University

• LEE Tae-Ho

  Fast Reactor Development Group, Korea Atomic Energy Research Institute

• YUN Byong-Jo

  Thermal Hydraulics Safety Research Center, Korea Atomic Energy Research Institute

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• Local Interfacial Structure of Subcooled Boiling Flow in a Heated Annulus

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