混凝土安全壳整体性能试验峰值压力持续时间探讨

摘要

Due to verify the integrity of the containment structure under design‐basis accident ,containment structure integrity test (CTT ) must be conducted during construction phase in nuclear power plant .Nonlinear finite element model analysis of the pre‐stressed concrete containment structure was done based on the containment CTT for certain nuclear plant unit 3 .T he results show that the maximal radial displacements of concrete containment location in the mid‐height of the cylinder wall under maximal pressure plateau condition at 0.483 MPa ,and most of the design pressure is born by the pre‐stressing system . The containment structure is in the compression state on the whole ,and the simulation method is effective with a high accuracy which agrees well with CT T performed on‐site in certain nuclear plant unit 3 .Based on domestic and inter‐ national design codes and standards on CTTs ,the duration of maximal pressure plateau in the CTT is put forward in details .Some conclusions are proposed ,which can contrib‐ute to containment CT T designing in China .%核电站建造阶段必须进行安全壳整体性能试验（CTT），验证在设计基准事故时安全壳结构的完整性。本文针对某核电厂3号机组预应力混凝土安全壳CTT进行非线性有限元分析。结果表明：筒体闸门洞口标高附近径向变形最大，预应力钢束承担了峰值压力0.483 M Pa作用下大部分设计内压，安全壳整体结构处于受压状态，与实际试验状态基本吻合。同时，对国内外法规标准关于安全壳峰值压力持续时间的规定进行总结，提出相关结论及建议，可为安全壳CT T方案设计提供参考。