P25-03 ROSA/LSTF 装置を用いた将来型炉の安全系に関する研究

概要

論文の詳細を見る
A research project is being conducted at the Japan Atomic Energy Research Institute (JAERI) for the safety systems of future reactors. The project consists of large-scale thermal-hydraulic tests using the ROSA/LSTF facility, separate effects tests, and the validation/improvement of the thermal-hydraulic codes. The present paper provides the belief description of the project, followed by two topics about the natural circulation in the PWR loop and the condensation heat transfer. The latter was investigated using the data obtained at the SPOT test facility in Russia constructed for the development of a passive cooling system for future reactors. The results have shown that the Dobson-Chato condensation correlation agrees with the data better than the Shah correlation, although the correlation was originally developed for refrigerants. This agrees with the results previously obtained in this project.
2002-06-14