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

[2E12] A Study on Cooling Process of Decay Heat Removal Systems in a Reactor Vessel of Sodium-cooled fast Reactor by Scaled Water Experiments

Flow Visualization Experiments Simulating Operation of Decay Heat Removal Systems under a Severe Accident

*Ayako Ono¹, Akikazu Kurihara¹, Masaaki Tanaka¹, Hiroyuki Ohshima¹, Yasuhiro Miyake², Masami Ito⁴, Shigeru Nakane³ (1. JAEA, 2. NDD, 3. NESI, 4. ASCEND)

Keywords:Sodium-cooled fast reactor, Severe accident, Decay heat removal, Water experiment

Thermal-hydraulic phenomena driven by natural circulation in a reactor vessel were investigated by scaled model water experiments simulating a reactor vessel in order to enforce of safety and optimize design and operation of decay heat removal systems under not only normal operation condition but also severe accident condition. Flow visualization tests revealed the behavior of cold flow from the dipped-type heat exchanger and cooling process of the core and debris scattering in the vessel.