<i>Spert-1 Experiment</i>の解析
書誌事項
- タイトル別名
-
- Analysis of Transient Behavior in the Spert-1 Reactor Experiment
抄録
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.
収録刊行物
-
- 日本原子力学会誌
-
日本原子力学会誌 3 (1), 1-8, 1961
一般社団法人 日本原子力学会
- Tweet
詳細情報 詳細情報について
-
- CRID
- 1390001206551845632
-
- NII論文ID
- 130003909757
-
- ISSN
- 21865256
- 00047120
-
- 本文言語コード
- ja
-
- データソース種別
-
- JaLC
- Crossref
- CiNii Articles
-
- 抄録ライセンスフラグ
- 使用不可