Analysis of Transient Behavior in the Spert-1 Reactor Experiment
Spert-1 Experimentの解析

Shigenori HAYASHI, Jiro WAKABAYASHI, Akira SAKURAI, Tetsuo IWAZUMI, Hideto AOKI, Motohiko KITAMURA
1961 Journal of the Atomic Energy Society of Japan  
In this report we present our study about Spert-1 reactor experiment which is a major part of the reactor safety investigation program, the results of our analysis are compared with the experiments. Analyses of Spert-1 reactor experiment have been made by S. G. Forbes, et al. using the modified Fuchs model, but by this method we cannot exactly estimate the transient behaviors of reactor in advance. On the other hand, our analysis is based on the conduction boiling model, and in our analysis we
more » ... se the design datas of Spert-1 reactor and some results of our fundamental experiments concerning transient heat transfer and transient boiling, so that our analytical method will be applica ble not only for the analysis of experiment but also for the preestimation of the transient behaviors of reactor. In this report we point out that the transient heat transfer before boiling occurs, heat transfer from fuel to aluminum cover, delay time of boiling, boiling temperature rise due to pressure rise and the life time of bubbles are important fcctors for the analysis of the transient behaviors of reactor. The results of analysis are sufficiently agreeable with experiment for our purpose.
doi:10.3327/jaesj.3.1 fatcat:u3uf4tc6pncxfegyek55zczqnm