节点文献
核电站压水堆压力容器瞬态应力场分析
THE TRANSIENT STRESS ANALYSIS OF PWR PRESSURE VESSEL
【摘要】 在启动、运行、停堆设计瞬态工况下,用轴对称有限元法和三维有限元法分别分析了整体压力容器和接管段由冷却剂温度、压力、内热源、螺栓力和接管载荷等载荷变化而产生的瞬态温度场和应力场。分析表明:瞬态应力分析的关键部位在接管段;由γ射线辐照产生的二维内热源分布所引起的热应力几乎局限于活性区,其最大值比其它应力要小一至二个量级。
【Abstract】 Under design transients, such as heat-up,operation and cool-down, the transient temperature and stress field in the reactor pressure vessel involving its nozzle junctions are caused by temperature and pressure of coolant, internal heat generation, bolt’s load and nozzle’s loads. The axisymmetrical and three dimen-tions finite element methods are used for analysing these temperature and stress field. The results show that the stress field in nozzle junction is important and the thermal stresses resulting from two-dimension distribution of internal heat generation which is caused by Y-ray are almost limited in activity area and its maximum stress is less than other stresses in one or two order of magnitudes.
- 【文献出处】 中国核科技报告 ,China Nuclear Science and Technology Report , 编辑部邮箱 ,1988年S2期
- 【被引频次】2
- 【下载频次】47