Experimental verification of the fast reactor safety analysis code SIMMER-III for transient bubble behavior with condensation

Koji Morita, Tatsuya Matsumoto, Kenji Fukuda, Yoshiharu Tobita, Hidemasa Yamano, Ikken Sato

研究成果: ジャーナルへの寄稿学術誌査読

11 被引用数 (Scopus)


Experimental verification of a reactor safety analysis code, SIMMER-III, was undertaken for transient behaviors of large-scale bubbles with condensation. The present study aimed to verify the code for numerical simulations of relatively short-time-scale multi-phase, multi-component hydraulic problems. Among these, vaporization and condensation, or simultaneous heat and mass transfer, play important roles. In this study, a series of transient bubble behavior experiments dedicated to condensation phenomena with noncondensable gases was carried out. In the experiments, a pressurized mixture of noncondensable gas and steam was discharged as a large-scale single bubble into a cylindrical pool filled with stagnant subcooled water. The concentration of noncondensable gas was taken as an experimental parameter as was the species of noncondensable gas. The characteristics of transient behavior of large-scale bubbles with condensation observed in the experiments were estimated through experimental analyses using SIMMER-III. In the experiments with steam condensation, dispersion of the gas mixture discharged into the liquid pool was accompanied by vapor condensation at the bubble surface. SIMMER-III simulations suggested that the noncondensable gas had a less inhibiting effect on the condensation of large-scale bubbles. This is a different characteristic to that of the quasi-steady condensation of small-scale bubbles observed in our previous experiments.

ジャーナルNuclear Engineering and Design
出版ステータス出版済み - 1月 2008

!!!All Science Journal Classification (ASJC) codes

  • 機械工学
  • 核物理学および高エネルギー物理学
  • 安全性、リスク、信頼性、品質管理
  • 廃棄物管理と処理
  • 材料科学一般
  • 原子力エネルギーおよび原子力工学


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