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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Radiation-damage in molybdenum–rhenium alloys for space reactor applications
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Radiation-damage in molybdenum–rhenium alloys for space reactor applications

机译:太空反应堆应用中的钼–合金的辐射损伤

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Various Mo–Re alloys are attractive candidates for use as fuel cladding and core structural materials in spacecraft reactor applications. Molybdenum alloys with rhenium contents of 41–47.5% (wt%), in particular, have good creep resistance and ductility in both base metal and weldments. However, irradiation-induced changes such as transmutation and radiation-induced segregation could lead to precipitation and, ultimately, radiation-induced embrittlement. The objective of this work is to evaluate the performance of Mo–41Re and Mo–47.5Re after irradiation at space reactor relevant temperatures. Tensile specimens of Mo–41Re and Mo–47.5Re alloys were irradiated to 0.7 displacements per atom (dpa) at 1073, 1223, and 1373 K and 1.4 dpa at 1073 K in the High Flux Isotope Reactor at Oak Ridge National Laboratory. Following irradiation, the specimens were strained to failure at a rate of 1 × 10?3 s?1 in vacuum at the irradiation temperature. In addition, unirradiated specimens and specimens aged for 1100 h at each irradiation temperature were also tested. Fracture mode of the tensile specimens was determined. The tensile tests and fractography showed severe embrittlement and IG failure with increasing temperatures above 1100 K, even at the lowest fluence. This high temperature embrittlement is likely the result of irradiation-induced changes such as transmutation and radiation-induced segregation. These factors could lead to precipitation and, ultimately, radiation-induced embrittlement. The objective of this work is to examine the irradiation-induced degradation for these Mo–Re alloys under neutron irradiation.
机译:各种Mo-Re合金是航天器反应堆应用中用作燃料包壳和核心结构材料的有吸引力的候选材料。 with含量为41–47.5%(wt%)的钼合金在母材和焊件中均具有良好的抗蠕变性和延展性。但是,由辐射引起的变化,例如trans变和由辐射引起的偏析,可能导致沉淀,最终导致由辐射引起的脆化。这项工作的目的是评估在空间反应堆相关温度下辐照后Mo–41Re和Mo–47.5Re的性能。在橡树岭国家实验室的高通量同位素反应堆中,对Mo–41Re和Mo–47.5Re合金的拉伸试样分别在1073、1223和1373 K处辐照至每原子0.7位移(dpa),在1073 K处辐照至1.4 dpa。辐照后,在真空中于辐照温度下以1×10?3 s?1的速率将样品应变至破坏。另外,还测试了未辐照样品和在每个辐照温度下老化1100小时的样品。确定了拉伸试样的断裂模式。拉伸试验和断口扫描显示,即使在最低通量下,随着温度升高至1100 K以上,严重脆化和中空玻璃破坏。这种高温脆化很可能是辐照引起的变化(如trans变和辐照引起的偏析)的结果。这些因素可能导致沉淀,最终导致辐射引起的脆化。这项工作的目的是检查中子辐照下这些Mo-Re合金的辐照诱导降解。

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