热老化对于核电压力容器用钢16MND5冲击行为的影响
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摘要
研究了不同热老化温度下核反应堆压力容器用钢16MND5冲击性能的演化情况。结果表明,热老化能够引发材料韧性下降,脆性上升。具体表现为材料韧脆转变温度的升高,冲击断口由韧性断裂为主的破坏形式逐步转化为脆性断裂为主的破坏形式,同时当老化时长达到一定程度时,韧性不会进一步降低,说明老化引起的脆化具有一定的极限值。因此,在工程领域考虑热老化引起的材料脆化时,既要考虑到老化引起脆化的危险性,同时也应合理估量脆化的影响程度。
Effects of thermal aging on Charpy V-notch impact properties in 16MND5 steel was investigated.The ductile to brittle transition temperature increased with the prolongation of thermal aging duration under impact test.According to the fracture analysis of the Charpy impact specimens with different thermal aging time by SEM,the typical ductile fracture transforms to the cleavage fracture with the extension of thermal aging time at cryogenic temperature.The thermal aging had unfavorable influence on the strength and impact toughness,which should be taken into consideration seriously
Effects of thermal aging on Charpy V-notch impact properties in 16MND5 steel was investigated.The ductile to brittle transition temperature increased with the prolongation of thermal aging duration under impact test.According to the fracture analysis of the Charpy impact specimens with different thermal aging time by SEM,the typical ductile fracture transforms to the cleavage fracture with the extension of thermal aging time at cryogenic temperature.The thermal aging had unfavorable influence on the strength and impact toughness,which should be taken into consideration seriously
引文
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[2]白晶,梁宝乙,赵长春,等.大型核电锻件用16MND5钢韧脆转变温度的确定[J].大型铸锻件,2011,(6):13-16.
[3]Tanguy B,Besson J,Piques R,et al.Ductile to brittle transition of an A508 steel characterized by Charpy impact test:Part I:experimental results[J].Engineering Fracture Mechanics,2005,72(1):49-72.
[4]Tanguy B,Besson J,Piques R,et al.Ductile to brittle transition of an A508 steel characterized by Charpy impact test:Part II:modeling of the Charpy transition curve[J].Engineering Fracture Mechanics,2005,72(3):413-434.
[5]Wan Q,Shu G,Wang R,et al.Study on the microstructure evolution of A508-3 steel under proton irradiarion[J].Acta Metallurgica Sinica-Chinese Edition-,2012,48(8):929.
[6]Lambrecht M,Almazouzi A.Positron annihilation study of neutron irradiated model alloys and of a reactor pressure vessel steel[J].Journal of Nuclear Materials,2009,385(2):334-338.
[7]Obrtlik K,Robertson C F,Marini B.Dislocation structures in 16MND5 pressure vessel steel strained in uniaxial tension[J].Journal of Nuclear Materials,2005,342(1):35-41.
[8]Priest R H,Belcher W P A,Mendes C M,et al.Irradiation surveillance data for an A508 forging and associated weld metal[J].International Journal of Pressure Vessels&Piping,2000,77(10):621-628.
[9]Wang W,Liu S,Xu G,et al.Effect of thermal aging on microstructure and mechanical properties of China Low-Activation martensitic steel at 550°C[J].Nuclear Engineering&Technology,2016,48(2):518-524.
[10]宗秋丽,孙宏,汪海燕,等.GB/T 229-2007金属材料夏比摆锤冲击试验方法简介[J].理化检验:物理分册,2010,3:190-192.
[11]Eichler B,Feldmann M,Kühn B,et al.Choice of steel material to avoid brittle fracture for Hollow Section Structures-JRC Scientific and Policy Reports[J].2012,7(1):28.