新型安全壳热压耦合分析

Temperature and Pressure Coupling Effect of the New Domestic Containment Vessel

核电作为新型清洁能源具有广阔的发展前景,而安全壳作为其安全的最后一道保障,明确掌握其结构性能尤为重要。本文采用三维空间编程建模技术与分离式建模方法,建立国内新型安全壳精细化有限元仿真模型。计算核反应附带温度在安全壳内梯度分布,并对比施加温度与忽略温度两模型计算结果判断温度作用在内压分析中的必要性。在此基础上,对安全壳逐步施加内压荷载,探究新型安全壳各组分在超设计内压与温度作用下的服役性能与破坏机理。结果表明:保证安全壳功能完好与结构完整的极限内压分别为1.5倍与2.1倍设计内压;随内压荷载增加筒身径向位移呈现线性、非线性、破坏三个阶段;安全壳最薄弱位置位于设备闸门处。

Nuclear power as a new clean energy has broad development prospects, and containment as the last guarantee of its safety, it is particularly important to clearly grasp its structural performance. In this paper, a refined finite element simulation model including a new domestic containment vessel is established by using three-dimensional programming modeling technology and separate modeling method. The gradient distribution of incidental temperature of nuclear reaction in the containment was calculated, and the necessity of temperature effect in internal pressure analysis was judged by comparing the calculation results of two models of applied temperature and neglected temperature. On this basis, internal pressure load is gradually applied to the containment to investigate the service performance and failure mechanism of the new containment components under the action of excess internal pressure and temperature.The results show that the limit internal pressures to ensure the functional integrity and structural integrity of the containment vessel are 1.5 times and 2.1 times, respectively. With the increase of internal pressure load, the radial displacement of barrel presents three stages: linear, nonlinear and failure. The weakest position of the containment is at the equipment gate.