Thermal-mechanical response analysis of the first wall in Z-pinch driven fusion-fission hybrid energy reactor
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摘要: 利用ANSYS程序对Z箍缩驱动聚变-裂变混合堆(Z-FFR)第一壁在瞬态热流加载下的热-力学响应进行了模拟计算，分析了第一壁温度、应力随时间和深度的分布。结果表明，周期性脉冲加载不会导致第一壁产生温度累积效应，第一壁温度峰值409 ℃，出现在钨层表面，钨层最大应力140 MPa，锆合金基底最大应力33 MPa。Abstract: 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.
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Key words:
- Z-FFR /
- first wall /
- thermal-mechanical responses /
- finite element analysis
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图 3 第一壁在不同时刻沿深度方向的温度响应
Figure 3. The temperature response of first wall at different time along the depth
图 4 钨层瞬态温度响应
Figure 4. Transient temperature response near the surface of the tungsten coating
图 6 钨层不同深度在5次循环加载下的温度响应
Figure 6. Cyclic temperature response at the surface of the tungsten coating for 5 cycles
图 7 钨层瞬态应力/应变响应
Figure 7. Transient stress/strain response near the surface of the tungsten coating
表 1 钨层和锆合金的热物理参数
Table 1. Temperature-dependent properties of W and Zr alloy
material temperature/℃ density/(g·cm-3) Posison′s ratio thermalconductivity/(W·m-1·K-1) coefficient ofthermal expansion/(10-6 ·K-1) elastic module/GPa W 200 19254 0.28 155 3.93 397 400 19203 0.28 139 3.94 397 600 19151 0.28 127 3.95 396 Zr alloy 200 8895 0.34 341 17.5 128 400 8883 0.36 346 18.1 120 600 8860 0.38 349 18.6 109 
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