2019 Fall Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 304-1 Thermal Hydraulics, Energy Conversion, Energy Transfer, Energy Storage

[2F10-14] Fast Reactor Thermal Hydraulics 2

Thu. Sep 12, 2019 2:45 PM - 4:10 PM Room F (Common Education Bildg. 2F C21)

Chair:Yoichi Utanohara(INSS)

3:30 PM - 3:45 PM

[2F13] Study on coolant behavior in damaged core of sodium-cooled fast reactor

(5)Effect of pipe and particle sizes on pressure drop in simulated debris bed

*Akinari Ishikuro1, Daisuke Ito1, Kei Ito1, Yasushi Saito1, Yuya Imaizumi2, Kenichi Matsuba2, Kenji Kamiyama2 (1. Kyoto Univ., 2. JAEA)

Keywords:porosity, simulated debris bed, sodium-cooled fast reactor, air-water two-phase flow, core disruptive accident

In a core damage accident of a sodium-cooled fast reactor, two-phase flow is generated by evaporation of sodium coolant due to direct contact with high temperature debris. Such two-phase flow characteristics is an important factor to evaluate the cooling characteristics of the debris. In this study, to evaluate two-phase flow pressure drop in the debris, experiments were conducted using a test section simulating debris bed. The test section consists of circular pipe, in which glass beads of uniform particle size are packed. The local porosity is not uniform due to the point contact between packed particle and wall. The effect of non-uniformity in the porosity distribution on the pressure drop was investigated by changing the pipe diameter and particle diameter.