Creep Inverse Problem of the Power Reactor Fuel Assembly Elements Contact Interaction

摘要

Creep inverse task solution for parameters identification of Zr1Nb alloy creep law is considered. Zr1Nb alloy is commonly used as a structural material for power reactor core elements. Strength and reliability justification of the fuel assembly (FA) components, manufactured from Zr1Nb alloy, requires the knowledge of the relationship between the intensity of creep strain rate, temperature and stress intensity. However, FA elements analyses performed using the known coefficients for the Zr1Nb alloy creep law, are not consistent with the experimental data. In this paper the results of parameters identification Zr1Nb alloy creep law are shown. The results are obtained using the numerical and experimental investigations of contact interaction between fuel rod and spacer grid cell. Numerical experiments, performed using verified creep law, are close to the experimental data. The results of this research can be used for a wide spectrum of thermal strength calculations of FA elements manufactured from Zr1Nb alloy.