2217 高速炉における高サイクル熱疲労に関する研究(3) 温度変動に関する Na と水の比較

概要

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A quantitative evaluation on thermal striping is of importance for structural integrity and also reactor safety. Thermal conductivity of sodium used in a fast reactor is approximately 100 times larger than that of water. We performed sodium and water experiments with the same geometry in order to evaluate temperature fluctuation characteristics in fluid near the structural surface. In the case of sodium, temperature fluctuation intensity decreased near the structural surface in comparison with water. And also, we investigated transfer characteristics of temperature fluctuation from fluid to structure. It was shown that the transfer characteristics of temperature fluctuation could be predicted using a steady state heat transfer coefficient and one-dimensional heat conduction theory in the structure.
社団法人日本機械学会の論文
2003-08-05