Safety Analysis of Loss of Cooling Accident for Typical Spent Fuel Pool
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摘要: 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℃。Abstract: A model of spent fuel pool in nuclear power plants is developed by using the system code RELAP5/MOD3 and it simulates the hot water behavior of the whole spent fuel pool in the present paper. The nodalization in the model is based on the cycles of spent fuels. Based on the model, normal operation of the spent fuel pool and its cooling system is simulated. The spent fuel pool loss of cooling accident is simulated after that. The effects of radiation heat transfer mode, spray before leakage of radioactive material and the nodalization of hot channel and bypass outside of rack on the temperature response are analyzed. It is shown in the calculation that the model is able to simulate the normal operation of the spent fuel pool and its cooling system and succeeds in establishing the mechanism of natural convection cooling. The fuel uncover time is 17.87 days and it takes 19.14 days for fuel PCT to exceed 1204℃. The 12.6 kg/s spray cooling takes 2.4 hour to reduce the temperature of the fuels from 726.9℃ to 100℃.
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Key words:
- Spent fuel pool /
- Decay power /
- PCT /
- Spray /
- Radiation heat transfer
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