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作 者:朱毓坤[1] 黄锦华[1] 胡刚[1] 霍铁军[1] 王晓宇[1]
出 处:《真空与低温》2003年第4期199-205,共7页Vacuum and Cryogenics
基 金:国家自然科学基金赞助(19885001)。
摘 要:高功率密度包层BFEB是以混合堆FEB的堆芯参数和真空室尺寸为依据,设计用作嬗变核废物的。在工程设计阶段的构件结构力学分析时,首先进行了热结构力学(Thermomechanics)分析与优化。包层模件采用Pro/ENGINEER2000i2设计制图编码建立模型后,随即进入Pro/MECHANICA2000i2功能编码进行热结构力学分析,即稳态热分析和稳态热应力分析。在机械构件材料和气氦冷却状态已定的情况下,通过分析,优化减小了作用于包层构件的表面热负载的分布起伏,即减小裂变功率密度沿包层各区的分布起伏;增大了氦冷却管板屏的拱弧曲率与圆角,以及其与氦汇流腔的焊接采用了优化的深度电子束焊接工艺等。经优化后,最终的分析计算表明:采用HT9铁素体钢制作的包层构件的最高温度为350℃,最大剪应力小于等于80MPa。Thermomechanics analyses, i.e. steady thermal analysis and steady stress analysis, have been carried out for the structure of a blanket BFEB. The Fusion Experimental Breeder, FEB, is adopted as the reference reactor. The ferrite steel HT9 is adopted as the structure material.The parts model for the blanket BFEB in Pro/ENGINEER code are created, then turn to Pro/MECHANICA code functionality for thermomechanics analyses. During analyses, the distribution of the power density in the blanket was optimised to be more flat, the arched curvature and rounds of cooling tube panels were optimised to less stiffness, and the boundary condition at the interface of helium cooling tube panel and manifold chamber was optimised,which is reasonable by using advanced welding processes with electron beam in a single pass. Finally, a maximum temperature Tm 350 ℃(<450 ℃) and a maximum shear stress τ_(max) 79.4 MPa(≤80 MPa) for component parts of the BFEB blanket have been shown in the calculations.
关 键 词:高功率密度包层 BFEB 热结构力学 混合堆 氦冷却管 电子束焊接 氦汇流腔 聚变堆 真空室
分 类 号:TL628[核科学技术—核技术及应用]
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