2017 Fall Meeting

Presentation information

Oral presentation

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

[2E10-14] Thermal Hydraulics in Fast Reactor 1

Thu. Sep 14, 2017 2:45 PM - 4:05 PM Room E (B32 - B3 Block)

Chair:Yoshihisa Nishi (CRIEPI)

3:45 PM - 4:00 PM

[2E14] Study on coolant behavior in damaged core of sodium-cooled fast reactor

(1)Measurement of gas-liquid two-phase flow in a simulated debris bed

*Daisuke Ito1, Milka Rivera Nava1, Kei Ito1, Yasushi Saito1, Mitsuhiro Aoyagi2, Kenichi Matsuba2, Kenji Kamiyama2 (1. KURRI, 2. JAEA)

Keywords:gas-liquid two-phase flow, packed bed of spheres, pressure drop, void fraction

Two-phase flow through porous media should be well understood to develop a severe accident analysis code not only for light water reactor but also sodium-cooled fast reactor (SFR). When a core disruptive accident occurs in SFR, the fuel inside the core become melted and interacts with the coolant. As a result, gas-liquid two-phase flow will be formed in the debris bed, which may have porous nature depending on the cooling process. In the present study, the characteristics of pressure drop and void fraction in two-phase flows in different porous media conditions are measured and experimental database is constructed.