Thermal fracture analysis for coolant circulation pumps of nuclear reactors under thermal shock loads
In this paper, a model for cracks in the mainshaft of nuclear reactor coolant circulation pumps is established. Symplectic technique is used to derive the analytical stress intensity factors under thermal shock loads The transient temperature function, displacements and stresses are obtained by a generalized symplectic approach and separation of variables. The formulations of stress intensity factors and close forms for both displacements and stresses are extracted. In numerical examples, a parametric analysis practice is evaluated was performed for the crack behavior. Inaddition, a mainshaft of the nuclear main pump in The results show that the crack propagation will be prevented in certain temperature environment and the mechanism is revealed.
热冲击载荷 核反应堆 冷却剂循环泵 应力强度因子 裂纹扩展
Z.H. Zhou X.S. Xu Z.Q. Gun A.Y.T. Leung
State Key Laboratory of Structure Analysis of Industrial Equipment and Department of Engineering Mec Department of Building and Construction, City University of Hong Kong, Hong Kong
国内会议
太原
英文
1-13
2011-07-01（万方平台首次上网日期，不代表论文的发表时间）