Parametric Structural Design of GEN IV Canadian Super Critical Water Reactor (SCWR)

本文将为加拿大第四代超临界水反应堆（SCWR）堆芯设计建立一个参数化固体力学模型，用于预测堆芯在设计初期的瞬态温度、位移、应变和应力场。该模型将基于三维瞬态有限元热应力分析，包括正常运行、启动、关闭、加急和事故情况。该模型将与流体流动速度、压力、温度和密度的最佳可用估计相结合。将使用温度和必要时与微观结构相关的性能。该模型将包括非线性接触元素，用于基于最佳可用知识的热和应力分析，如果没有可用知识，则对每个接触界面的间隙宽度，表面粗糙度，间隙材料的敏感性研究将有所帮助。

A parametric solid mechanics model for the design of the reactor core of the GEN IV Canadian Supercritical Water Reactor (SCWR)will be developed to predict transient temperature, displacement, strain and stress fields in the reactor core in the early design stages. The model would be based on 3D transient FEM thermal-stress analysis for normal operation, startup, shut-down, upset and accident conditions. The model would be coupled to the best available estimates of fluid flow velocities, pressures, temperatures and densities. Temperature and if needed microstructure dependent properties would be used. The model would include non-linear contact elements for thermal and stress analysis based on the best available knowledge and if not available, sensitivity studies would be helpful, of the gap width, surface roughness, gap material of each contact interface.