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引用次数: 8

摘要

对奥氏体钢1.4301 (X5 CrNi 189)和两种铁素体钢1.4914和1.4923 (X18 CrMoVNb 121, X22 CrMoV 121)在液态锂中进行了拉伸试验,以了解这两种合金在液态碱金属环境中的力学性能。样品还在锂中进行了测试,并在550°C的温度下在锂中预暴露1000小时后在空气中进行了测试。拉伸试验结果表明,在未预先暴露于锂介质的情况下,奥氏体钢对锂环境不敏感。在预暴露后,试样在锂中测试时以脆性方式失效,在空气中测试时以延展性方式失效。这两种铁素体钢的性能相互比较,可以认为是非常相似的。试验表明,即使没有预暴露,钢的拉伸性能也会受到影响(塑性降低,脆性/剪切混合断裂模式)。在所有测试的钢中,锂的反应是由于晶界效应引起的。这些影响是由晶界的冶金状态决定的。所观察到的LME效应在反应堆运行的启动和中断过程中,当超过临界温度范围时,可能具有技术意义。在温度为400-500°C的毛毯工作条件下,材料的性能不应受到这种程度的影响。
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The fracture of austenitic and martensitic steel in liquid lithium

The austenitic steel 1.4301 (X5 CrNi 189) and the two ferritic steels 1.4914 and 1.4923 (X18 CrMoVNb 121, X22 CrMoV 121) have been tensile tested in liquid lithium in order to get information about the mechanical properties of these alloys in liquid alkali metal environment. Specimens have also been tested in lithium and in air after a pre-exposure in lithium for 1000 h at a temperature of 550°C.

The results of the tensile tests indicate that the austenitic steel is insensitive to lithium environment, when not pre-exposed to this medium before. After a pre-exposure the specimens fail in a brittle manner when tested in lithium, and in a ductile manner when tested in air. The behaviour of the two ferritic steels can be regarded as quite similar when compared to each other. The tests indicate that the steels are affected in their tensile properties even without a pre-exposure (lower ductility, brittle/shear mixed fracture mode). The reactions of the lithium are due to grain boundary effects in all steels tested. These effects are determined by the metallurgic state of the grain boundaries. The observed LME effects might be of technical significance during the procedures of starting and interrupting the reactor operation, when the critical temperature ranges are passed. The material behaviour under operating conditions of a blanket at temperatures of 400–500°C and with creep deformation should not be influenced to that degree.

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Preface Announcement Cryopumping for fusion reactors 2.1. Development of low activation Al alloys for the R-project 6. Research and development on the tritium handling technology in the R-project
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