乏燃料水池LOCA工况事故分析研究
发布时间：2018-08-07 07:16
【摘要】：以大亚湾核电站乏燃料水池为原型,利用热工水力最佳估算程序RELAP5/MOD3.3程序分析乏燃料水池发生破口事故后的工况。分析结果表明:事故后6.1 h池水温度从52.6℃上升到100℃,池水开始沸腾,在16.6 h燃料组件开始裸露。这段时间内,若能够采取相应的措施冷却乏燃料水池中的水,或者及时向水池中补水,能够避免燃料组件裸露。
[Abstract]:Based on the spent fuel pool of Daya Bay Nuclear Power Station, the working conditions of the spent fuel pool after the breakage accident were analyzed by RELAP5/MOD3.3 program. The results show that when the water temperature rises from 52.6 鈩，
本文编号：2169276
[Abstract]:Based on the spent fuel pool of Daya Bay Nuclear Power Station, the working conditions of the spent fuel pool after the breakage accident were analyzed by RELAP5/MOD3.3 program. The results show that when the water temperature rises from 52.6 鈩，
本文编号：2169276
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