2022 Annual Meeting

Presentation information

Oral presentation

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

[2E09-14] Fast Reactor Thermal Hydraulics

Thu. Mar 17, 2022 2:45 PM - 4:30 PM Room E

Chair: Akifumi Yamaji (Waseda Univ.)

3:15 PM - 3:30 PM

[2E11] Study on coolant behavior in damaged core of sodium-cooled fast reactor

(6)Local void fraction measurement by using X-ray imaging in simulated debris bed

*Noriaki Yasugi1, Naoya Odaira1, Daisuke Ito1, Kei Ito1, Yasushi Saito1, Yuya Imaizumi2, Kenichi Matsuba2, Kenji Kamiyama2 (1. Kyoto Univ., 2. JAEA)

Keywords:debris bed, packed bed of spheres, sodium-cooled fast reactor, air-water two-phase flow, void fraction, X-ray imaging

In case of a severe accident in a sodium-cooled fast reactor, the fuel debris formed in the core should be cooled stably and in-vessel retention of the damaged core material is important. It is considered that a gas-liquid two-phase flow is generated by boiling of the sodium inside the high-temperature debris bed. However, the two-phase flow characteristics in the debris bed has not been understood enough. Therefore, in this study, the two-phase flow in a packed bed is measured to improve the prediction accuracy of the two-phase pressure drop in the porous media. The local void fraction distribution of gas-liquid two-phase flow in the packed bed was measured by X-ray transmission imaging, and the local two-phase flow structure was evaluated.