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首页> 外文期刊>Materials Science >Methods of Improving the High-Temperature Strength and Corrosion Resistance of Vanadium and Certain Alloys Used in Reactors
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Methods of Improving the High-Temperature Strength and Corrosion Resistance of Vanadium and Certain Alloys Used in Reactors

机译:提高反应堆中钒及某些合金的高温强度和耐蚀性的方法

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We present new evidence for the high-temperaturestrength of vanadium and low-alloyed (up to 15 at. percent)vanadium-based alloys under conditions of prolonged (up to5000 h) high-temperature (973-1173 K) exposure to vacuum,helium, lithium and sodium melts, modeling reactor heat-transport media (10 Pa). The kinetics of phase transformationsin alloys of the systems V-Zr-C, V-Nb-Zr-C, V-Mo-Zr-C, andV-Ti-O in the process of prolonged aging under stress isanalyzed. It is established that the process of pre-decay of asolid solution has many stages and is intensified by the action ofstresses. The corresponding isothermal diagrams of the decay ofVTsU (V-Zr-C) alloy are constructed. We giverecommendations as to the choice of alloying elements with theaim of enhancing the high-temperature strength of vanadiumand vanadium alloys used for reactors. New alloys developed onthe basis of the systems V-Ti-O, V-Nb-Zr, V-Ta-Hf, V-Cr-Sc,and V-Cr-Nd and a new method of hardening thermochemicaltreatment of vanadium-titanium alloys with the use of oxygenfrom air have found application in pilot-engineeringdevelopments for high-temperature nuclear power plants.
机译:我们提供了新的证据,表明钒和低合金(高达15 at。%)钒基合金在长时间(高达5000 h)高温(973-1173 K)暴露于真空,氦气的条件下的高温强度,锂和钠熔体,模拟反应堆传热介质(10 Pa)。分析了V-Zr-C,V-Nb-Zr-C,V-Mo-Zr-C和V-Ti-O系合金在应力作用下长时间老化过程中的相变动力学。可以确定的是,固溶体的预分解过程有很多阶段,并且在应力作用下会加剧。绘制了相应的VTsU(V-Zr-C)合金等温线图。为了提高反应堆用钒和钒合金的高温强度,我们建议选择合金元素。在V-Ti-O,V-Nb-Zr,V-Ta-Hf,V-Cr-Sc和V-Cr-Nd系统的基础上开发了新合金,以及对钒钛合金进行硬化热处理的新方法空气中的氧气已被用于高温核电站的试点工程开发中。

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