The basic research on a high-density ratio gas-liquid flow. 1995 fiscal year report on the study in advanced fundamental field

This study is the basic research on boiling behavior of mixing pool which consists of fuel and steel formed in the reactor core during the core damage accident of fast breeder reactor. This study is performed under the cooperative research between Power Reactor and Nuclear Fuel Development Corp. and Res. Reactor Inst., Kyoto Univ.. The objective of this study is the visualization using the neutron radiography technique for the simulation test which injects bubbles from the bottom of molten metal pool. This experiments serves basic data such as bubble diameter, movement, and void fraction of a high-density ratio gas-liquid flow. In addition, these experimental data will be applied for the model verification and improvement of the SIMMER-III code. As a first year of the cooperative research, in this fiscal year, the visualization performance of the radiography technique was tested using the solid sample with the void space which simulated a bubble. The result of this experiment is described in this report. (author)