In order to model the mobility of the postulated disrupted core in a core disruptive accident of a liquid metal faster reactor and to provide data for the verification of a reactor safety analysis code (SIMMER-III) a series of experiments was performed to simulate the behavior of a solid particle bed in a liquid pool against pressure transients. Experimental analyses using the SIMMER-III code show that physical models and methods used in the code can reasonably represent the transient behaviors of pool multiphase flows with rich solid phases as observed in the experiments. The validation of several key models of SIMMER-III was also discussed for treating transient behaviors of the solid-particle phase in multiphase flows.
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering