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

为设计第四代加拿大超临界水反应堆(SCWR)堆芯，将建立一个参数固体力学模型，以便在设计初期预测堆芯内的瞬时温度、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，对正常运行、启动、关闭、翻转和事故情况进行分析。该模型将与对流体流动速度、压力、温度和密度的最佳估计相结合。如果需要，还可以使用与温度和微结构相关的特性。该模型将包括非线性接触单元，用于根据现有的最佳知识进行热和应力分析，如果没有的话，对每个接触界面的间隙宽度、表面粗糙度、间隙材料进行敏感性研究将是有帮助的。

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.