Development of gas entrainment evaluation method in the hot plenum of sodium-cooled fast reactor

Ezure, Toshiki ; Matsushita, Kentaro  ; Sasaki, Keisuke; Tanaka, Masaaki 

In the design of the pool-type demonstration sodium-cooled fast reactor (demonstration reactor), the prevention of gas entrainment in the hot plenum of the reactor vessel is one of important issues to be addressed in the conceptual design of demonstration reactor. Related to this problem, the authors have been developing an evaluation approach combining the analysis method of entrained gas-transport in the primary circuit, SYRENA, and the gas entrainment evaluation method, StreamViewer, at the free surface in the hot plenum of the demonstration reactor. In this study, a development plan of StreamViewer is presented toward application to the evaluation of the demonstration reactor design. Furthermore, an overview of scaled model water experiment of the pool-type demonstration reactor to obtain the validation date for StreamViewer is also presented.