包壳管是反应堆内重要的安全屏障,其在服役环境下承受一定裂变气体内压,同时面临芯块和包壳间机械相互作用的考验.开展包壳管环向拉伸性能研究,对反应堆燃料组件设计和安全分析具有重要意义.奥氏体不锈钢是快中子反应堆包壳管重要候选材料,具有良好的高温力学性能.本文针对奥氏体不锈钢包壳管高温环向拉伸试验,研究了夹具、标距段宽度和润滑条件等试验参数对包壳管环向拉伸试验的影响.结果表明:三嵌块夹具可以避免试样标距段向内展平,且夹具和试样间摩擦力较小;标距段的宽度对包壳管环向拉伸强度影响不大,但是标距段宽度过大或者过小都会造成试样延伸率下降;夹具与试样间隙的摩擦会增加拉伸载荷,降低延伸率,使用石墨润滑可以有效减小摩擦力的影响.
Cladding tubes are vitally important safety barrier in the reactors,which contain fission gas in service environment and bear the mechanical interaction between pellet and cladding.Research on tensile properties of cladding tubes is important for the design and safety analysis of fuel assembly in nuclear reactors.Due to good high temperature mechanical properties,austenitic stainless steel is an important candidate material for cladding tube in fast reactors.The hoop tensile tests at high temperature of austenitic stainless steel cladding are performed to study the effect of different mandrels,gauge section width and lubricating conditions on the hoop tensile properties.The results show that three-piece tooling can be used to avoid the occurrence of bending moment in the gauge sections,and reduce friction between mandrels and specimens.The influence of gauge section width on tensile strength can be ignored.But the effect of the gauge section width on elongation is obvious.The friction between mandrels and sample will increase tensile load and decrease elongation,and it can be reduced by the graphite effectively.
参考文献
- 下载量()
- 访问量()
- 您的评分：
-
10%
-
20%
-
30%
-
40%
-
50%