2442 低減速スペクトル炉 PWR の熱的成立性評価

概要

論文の詳細を見る
A concept of PWR-type reduced moderation water reactor (RMWR) has been studied as a future reactor which install plutonium mixed-oxide (MOX) fuel attaining the high conversion ratio around 1.0 and negative void coefficient. Since the core has narrow gap width between the fuel rods around 1mm, an evaluation of thermal-hydraulic feasibility is important in the study. There is no data base which can be applicable to the evaluation. The DNB experiments with a triangle and tight-lattice seven-rod-bundle has been performed on the gap widths of 1.5mm and 1.0mm. It was found that the evaluation method of thermal margin with the COBRA-IV-I subchannel code and the KfK CHF correlation gave lower DNBRs than the experiments in both gap width cases. The same evaluation method was applied to the PWR-type RMWR. The results show that the concept has enough thermal margin and is feasible.
一般社団法人日本機械学会の論文
2000-07-31