高温ガス炉の崩壊熱除去用水冷形冷却パネルシステムの設計・評価手法に関する研究

概要

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An experiment was performed to simulate a water cooling panel system for decay heat removal from a high-temperature gas-cooled reactor (HTGR) in order to investigate the performance of decay heat removal and the temperature distribution of components of the system. The test apparatus was composed of a pressure vessel 1 m in diameter and 3 m in height, containing heaters with the maximum heating rate of 100 kW which simulated residual heat of the core and cooling panels surrounding the pressure vessel. The analytical code TANPACTST2 was applied to analyze the experimental data to investigate the validity of the analytical method and model proposed. Under the conditions of helium gas at the pressure of 0.73 MPa and temperature of 210℃ in the pressure vessel, temperatures of the pressure vessel were well estimated within the errors of -29 to +37℃ compared with the experimental data. The analyses indicated that the heat transfer-red to the cooling panel was 11.4% less than the experimental value and the heat transferred by thermal radiation was 74.4% of total heat input. It was also found that the lower head of the pressure vessel was effectively cooled by the natural convection through the flow channels at the upper and lower edges of skirt-type supports of the pressure vessel.
社団法人日本機械学会の論文
1996-08-25