首页> 外文会议>NATO final project workshop on fracture resistance of steels for containers of spent nuclear fuel arranged within science for peace program >CONSTRUCTION OF J-Q LOCUS FOR MATERIAL OF REACTOR PRESSURE VESSEL WWER 440 IN THE DUCTILE-BRITTLE TRANSITION REGION
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CONSTRUCTION OF J-Q LOCUS FOR MATERIAL OF REACTOR PRESSURE VESSEL WWER 440 IN THE DUCTILE-BRITTLE TRANSITION REGION

机译:韧性脆性过渡区域反应堆压力容器WWER 440材料的J-Q基因座的构造

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In the paper effect of shallow crack (in-plane constraint) on fracture toughness of reactor pressure vessel WWER 440 is examined, using two-parameter fracture mechanics approach. For this purpose, experimental tests were performed on 18 specimens of SEN(B) type and 18 specimens of SEN(T) type, for three relative crack depths a/W = 0.09, 0.16 (0.17), 0.5, for each type of loading. The tests were performed at the temperature near reference temperature T_0 determined according to Master Curve concept, in the ductile-brittle transition region. Based on 2D and 3D FE calculations, values of two fracture parameters J and Q were determined. Due to different forms of stress fields found for the two types of loading, the Q-parameter was examined for different values of normalized distance from crack front, i.e. r.σ_0/J= 2,4, 6, 8 and 10. Based on a reasonable criterion, the J-Q locus for the examined steel was suggested. Besides of this, also the shift of Master Curve reference temperature due to shallow crack effect was examined and compared with similar results valid for steel A533B.
机译:在浅裂的纸张效果(面内约束)上反应堆压力容器的断裂韧性WWER 440被检查,使用两个参数断裂力学接近。为了这个目的,实验测试是在18个标本SEN(B)类型的,并且18个标本SEN(T)型的进行,三个相对裂纹深度的/ W = 0.09,0.16(0.17),0.5%,对于每种类型的装载。试验在T_0根据主曲线概念确定的温度接近基准温度下进行,在延性 - 脆性转变区域。根据2D和3D FE计算,分别确定的两个裂缝参数J和Q的值。由于不同形式的应力场的发现对于两种类型的载荷,检测用于从裂纹前端,ierσ_0/ J = 2,4,6,基于合理的8和10归一化距离的不同值的Q参数标准,为研究钢JQ轨迹建议。此外此,也主曲线的基准温度的由于浅裂纹效果的移位进行了检查,并用适用于钢A533B类似的结果进行比较。

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