From the viewpoint of safety design of nuclear reactor and an economic terms, It is important to clear the mechanism of post boiling transition heat transfer and to estimate correctly the fuel rod wall temperature. So, in this research, we proposed a calculation model of post boiling transition heat transfer and developed a method to predict the axial variation of the fuel rod wall temperature. Furthermore, we evaluated the prediction accuracy and validity of this prediction method by comparing the prediction results with experimental data for a circular tube measured by Bennett et al (1) under the actual BWR's operating conditions. From the results, it was concluded that under high pressure (7MPa) and for a wide range of conditions, the method developed in this research was able to predict accurately.
|ジャーナル||Nihon Kikai Gakkai Ronbunshu, B Hen/Transactions of the Japan Society of Mechanical Engineers, Part B|
|出版ステータス||Published - 2013|
ASJC Scopus subject areas
- Mechanical Engineering
- Condensed Matter Physics