Abstract The nuclear reactors can undergo different forms of asymmetric operating conditions with one or more reactor coolant pump (RCP) fails or pressurized thermal shock (PTS) occurrences which can influence the life of reactor vessels. So, accurate descriptions of the heat transfer and the coolant flow within a nuclear reactor for the safety and performance concerns are always desirable. In this paper, computational fluid dynamics (CFD) simulation for a VVER-1200 reactor vessel was presented. Analyses of the reactor vessel were carried out for symmetric and asymmetric inlet boundary conditions, and also for loss-of-coolant accident conditions. Due to computational limits, some simplifications in the geometry of the RPV are introduced. As a result of the analyses, several parameters such as temperature, velocity, and pressure distributions were obtained for the whole reactor vessel. The obtained results for pressure losses through the reactor core matched with the analytical values of the VVER and the predicted thermal results agreed well with the design values. The obtained results show that it is possible to carry out further analysis for several asymmetric or accident conditions utilizing the CFD simulation knowledge obtained.

中文翻译：

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对称入口、非对称入口和 LOCA 条件下 VVER-1200 核反应堆容器的计算流体动力学分析

摘要 核反应堆可能会经历不同形式的不对称运行条件，一个或多个反应堆冷却剂泵 (RCP) 发生故障或发生加压热冲击 (PTS)，这会影响反应堆容器的寿命。因此，出于安全和性能考虑，始终需要准确描述核反应堆内的热传递和冷却剂流动。在本文中，介绍了 VVER-1200 反应堆容器的计算流体动力学 (CFD) 模拟。反应堆容器的分析是针对对称和非对称入口边界条件以及冷却剂损失事故条件进行的。由于计算限制，引入了 RPV 几何结构的一些简化。作为分析的结果，几个参数，如温度、速度、获得了整个反应堆容器的压力分布。通过反应堆堆芯获得的压力损失结果与 VVER 的分析值相匹配，预测的热结果与设计值非常吻合。所得结果表明，利用所获得的 CFD 仿真知识，可以对几种不对称或事故工况进行进一步分析。