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以RELAP/MOD3为分析工具,对典型沸水堆核电厂乏燃料水池热工水力行为进行模拟,详细分析乏燃料水池自然循环对流换热、丧失冷却性能下燃料裸露过程、应急洒水喷淋、热辐射等。验证所建立的乏燃料水池模型计算乏燃料水池冷却系统正常运行下的稳态过程可用后,对丧失冷却事故条件下的乏燃料水池丧失冷却事故下安全性能进行分析。计算结果为乏燃料水池冷却丧失性能后17.87 d乏燃料将裸露;若考虑辐射传热因素则包壳峰值温度达到1204℃的时间延后8.97 h;若按照美国核能研究所(NEI)建议的12.6kg/s喷淋洒水量,需要2.4 h可将燃料温度由726.9℃降至100℃。
Taking RELAP / MOD3 as the analysis tool, the thermal-hydraulic behavior of spent fuel pool in typical BWR plant was simulated. The convection heat transfer in the natural circulation of spent fuel pool was analyzed in detail. The process of fuel exposure, cooling sprinkler and heat radiation Wait. After verifying the established model of spent fuel pool, the steady state process of the spent fuel pool cooling system can be calculated and the safety performance of the spent fuel pool under cooling accident without cooling accident after losing the cooling accident is analyzed. The calculated result is that the spent fuel will be exposed at 17.87 days after spent cooling in the spent fuel pool, and 8.97 hours after the peak temperature of the cladding reaches 1204 ° C if radiation heat transfer is taken into account. According to the NEI recommendation of 12.6 kg / s spray water spray, it takes 2.4 h to reduce the fuel temperature from 726.9 ℃ to 100 ℃.