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

将开发用于GEN IV加拿大超临界水反应堆（SCWR）堆芯设计的参数化固体力学模型，以预测反应堆堆芯在早期设计阶段的瞬态温度场、位移场、应变场和应力场。 该模型将基于正常运行、启动、停机、故障和事故条件下的三维瞬态有限元热应力分析。 该模型将与流体流速、压力、温度和密度的现有最佳估计数相结合。 将使用温度和如果需要的话微结构依赖的性质。该模型将包括非线性接触元素，用于根据最佳可用知识进行热和应力分析，如果无法获得，则对每个接触界面的差距宽度、表面粗糙度、间隙材料进行敏感性研究将是有益的。

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.