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首页> 外文会议>Safety Related Issues of Spent Nuclear Fuel Storage; NATO Security Through Science Series C: Environmental Security >DEGRADATION IN MECHANICAL PROPERTIES OF STAINLESS STEELS C0.12Crl8Nil0Ti AND C0.08Crl6NillMo3—MATERIALS FOR HEXAGONAL DUCTS OF SPENT FUEL ASSEMBLIES FROM THE BN-350 FAST NEUTRON REACTOR
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DEGRADATION IN MECHANICAL PROPERTIES OF STAINLESS STEELS C0.12Crl8Nil0Ti AND C0.08Crl6NillMo3—MATERIALS FOR HEXAGONAL DUCTS OF SPENT FUEL ASSEMBLIES FROM THE BN-350 FAST NEUTRON REACTOR

机译：不锈钢C0.12Crl8Nil0Ti和C0.08Crl6NillMo3的力学性能的下降—六角燃料从BN-350快速中子反应器中燃烧成燃料的材料

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This paper discusses results of studying the structural behavior of the hexagonal assembly ducts of the BN-350 fast neutron reactor after irradiation in sodium and subsequent water storage at the reactor. Maximum irradiation dose for different ducts varied from ~11 dpa for an assembly on the core periphery to ~55 dpa for one at core center. The irradiation dose rate for various assemblies and along each assembly varied from ~10~(-8) dpa/s to 10~(-6) dpa/s, and temperature of irradiation ranged from 280℃ to 400℃. The changes in microstructure and physico-mechanical properties of 12Crl8NilOTi and 08Crl6NillMo3 steels were studied from 50×10×2 mm samples cut from the assembly ducts at various locations. Changes in microstructure and phase composition were studied by optical microscopy, transmission electron microscopy (TEM) and scanning electron microscopy (SEM), as well as X-ray structure analysis. Mechanical tensile tests and microhardness measurements were performed. For each location on the ducts values of the hydrostatic density (HD) and the transmutation He content, which are dependent on damage dose and temperature, were also determined. The paper describes the dependence of swelling on dose, dose rate, and temperature for both steels, as well as the dependence of yield stress, ultimate strength, and uniform and total elongation, on these parameters.
机译：本文讨论了研究BN-350快中子反应堆的六角形装配管道在钠中辐照并随后在反应堆中储水后的结构行为的结果。不同导管的最大辐照剂量从芯外围的组件的〜11 dpa到芯中心的组件的〜55 dpa不等。各个组件以及沿着每个组件的辐照剂量率在〜10〜（-8）dpa / s至10〜（-6）dpa / s之间，辐照温度为280℃至400℃。研究了从不同位置的装配管道上切出的50×10×2 mm样品，研究了12Crl8NilOTi和08Crl6NillMo3钢的显微组织和物理力学性能的变化。通过光学显微镜，透射电子显微镜（TEM）和扫描电子显微镜（SEM）以及X射线结构分析研究了微观结构和相组成的变化。进行了机械拉伸试验和显微硬度测量。对于导管上的每个位置，还确定了静压密度（HD）和trans变He含量的值，这些值取决于损伤剂量和温度。该论文描述了两种钢的溶胀对剂量，剂量率和温度的依赖性，以及屈服应力，极限强度，均匀和总伸长率对这些参数的依赖性。

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