Analysis of Transient Behavior in the Spert-1 Reactor Experiment

DOI

Bibliographic Information

Other Title
  • <i>Spert-1 Experiment</i>の解析

Abstract

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 use 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 applicable 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.

Journal

Keywords

Details 詳細情報について

  • CRID
    1390001206551845632
  • NII Article ID
    130003909757
  • DOI
    10.3327/jaesj.3.1
  • ISSN
    21865256
    00047120
  • Text Lang
    ja
  • Data Source
    • JaLC
    • Crossref
    • CiNii Articles
  • Abstract License Flag
    Disallowed

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