乏燃料池丧失冷却后燃料操作区域温度压力的响应分析  

Analysis of Fuel Handling Area Temperature and Pressure Response Following Loss of Spent Fuel Pool Cooling

作　　者：王国栋[1] 王喆[1] 扈本学[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《核动力工程》2016年第6期104-108,共5页Nuclear Power Engineering

摘　　要：在国产先进百万千瓦级非能动压水堆(CAP1000)核电厂乏燃料池冷却系统设计中,燃料操作区域墙体上部装有常闭的蒸汽释放面板。在乏燃料池丧失正常冷却后,饱和蒸汽从乏燃料池进入燃料操作区域。在一定温度下,固定蒸汽释放面板的机构熔断,面板自动打开,缓解燃料操作区域的增压过程。本文应用GOTHIC程序8.0版本分析事故后燃料操作区域的三维温度场和压力响应。研究结果表明:在事故后的不同时刻,燃料操作区域存在不同程度的温度分层现象;在事故后约7500 s时刻,可熔机构熔断,蒸汽释放面板开启,燃料操作区域压力迅速降低,此后维持在较低压力水平。A normal-closed steam-relief panel is provided in the design of the spent fuel cooling system for CAP1000 nuclear power plant. Saturated steam is released from the spent fuel pool to fuel handling area under loss of cooling scenarios. The steam-relief panel will be opened in order to mitigate the pressurization process in the fuel handling area after the fusion of the fusible links, designed to yield at an appropriate temperature. A three-dimension temperature field and pressure response to the fuel handling area was performed using GOTHICS.0 code in this paper. The results show that temperature stratification behavior is expected depending on different time sequence. At time of about 7500s, the steam-relief panel is expected to be opened with distinct pressure decreasing in the fuel handling area and maintain a low pressure level after that.

关 键 词：燃料操作区域 蒸汽释放面板 GOTHIC 温度压力响应 

分 类 号：TL364.4[核科学技术—核技术及应用]