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Analysis of Transient Behavior in the Spert-1 Reactor Experiment
Spert-1 Experimentの解析
1961
Journal of the Atomic Energy Society of Japan
Spert-1 Experimentの解析
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
doi:10.3327/jaesj.3.1
fatcat:u3uf4tc6pncxfegyek55zczqnm