Analysis of Fuel Handling Area Temperature and Pressure Response Following Loss of Spent Fuel Pool Cooling
-
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。Abstract: 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 GOTHIC8.0 code in this paper. The results show that temperature stratification behavior is expected depending on different time sequence. At time of about 7500 s, 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.
-
Key words:
- Fuel handling area /
- Steam-relief panel /
- GOTHIC /
- Temperature and pressure response
-
计量
- 文章访问数: 16
- HTML全文浏览量: 6
- PDF下载量: 0
- 被引次数: 0