核电厂新型预应力混凝土安全壳及其非能动冷却系统设计与分析

摘要

A new nuclear power plant prestressed concrete containment and its passive cooling system design were proposed for CAP1700 nuclear power plant as an example . T he thermal-hydraulic calculation method for the new passive containment cooling sys-tem of CAP1700 was introduced and the operating parameters in accident condition were obtained .The result shows that the design of passive containment cooling system for CAP1700 is feasible and can meet the cooling demand in accident condition .Reservoir capacity of tank has a big margin and can be further optimized by calculation .%本文以C A P1700核电厂为例，提出了一种新的核电厂预应力混凝土安全壳及其非能动冷却方案，介绍了新式非能动安全壳冷却系统热工水力计算方法，并给出事故工况下新非能动安全壳冷却系统的运行参数。结果表明，C A P1700非能动安全壳冷却系统的设计是可行的，能满足事故工况下的冷却需求。贮水箱水量有很大的裕量，可通过计算进一步优化贮水量。