Thermal-mechanical response analysis of the first wall in Z-pinch driven fusion-fission hybrid energy reactor

The simulation software ANSYS was used to calculate the thermal-mechanical response of the first wall in Z-pinch driven fusion-fission hybrid energy reactor under pulsed thermal flux, including distribution of temperature, stress and strain of the first wall materials along its depth direction. The results indicate that the periodic (10 s) transient pulse loading does not lead to the temperature accumulation in the first wall. The maximum temperature of the first wall appears on the surface of the tungsten coating. The maximum stress of the tungsten coating is 130 MPa. The maximum stress of the Zr alloy substrate is 33 MPa. (authors)