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Alloy Designing Study for Improving Mechanical Properties of SA 508 Steel for Nuclear Reactor Pressure Vessel

机译:提高核反应堆压力容器用SA 508钢力学性能的合金设计研究

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This study is concerned with the development oflow-alloy steels for nuclear reactor pressure vessel byinvestigating the effects of alloying elements on mechanicalproperties of base metals and heat affected zones (HAZ's).Four kinds of steels with different alloying elements werefabricated by vacuum-induction melting and heat treatment,and their tensile properties and Charpy impact toughness wereevaluated. Microstructural analyses indicated that coarseM_3C-type carbides and fine M_2C-type carbides wereprecipitated along lath boundaries and inside laths, respectively.In the steels having lower carbon content and highermolybdenum content, the amount of fine M_2C carbidesgreatly increased, while that of coarse M_3C carbidesdecreased, thereby leading to the improvement of tensileproperties and impact toughness. Their simulated HAZ's alsohad sufficient impact toughness after post-weld heat treatment.These findings suggested that low-alloy steels with highstrength and toughness could be processed by reducing theamount of carbon and manganese and by raising the amount of molybdenum.
机译:通过研究合金元素对贱金属和热影响区(HAZ's)力学性能的影响,本研究涉及核反应堆压力容器用低合金钢的开发。通过真空感应熔炼和熔炼制备了四种不同合金元素的钢。热处理,评估其拉伸性能和夏比冲击韧性。显微组织分析表明,粗M_3C型碳化物和细M_2C型碳化物分别沿板条边界和内板条析出。在碳含量较低和钼含量较高的钢中,细M_2C碳化物的数量显着增加,而粗M_3C碳化物的数量减少,从而导致拉伸性能和冲击韧性的改善。他们的模拟热影响区在焊后热处理后也具有足够的冲击韧性。这些发现表明,可以通过减少碳和锰的含量以及增加钼的含量来加工具有高强度和韧性的低合金钢。

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