磷化处理对核主泵螺栓断裂行为的影响
赵东杨1, 周宇1(), 王冬颖2, 那铎1
Effect of Phosphating on Hydrogen Embrittlement of SA-540 B23 Steel for Nuclear Reactor Coolant Pump Bolt
ZHAO Dongyang1, ZHOU Yu1(), WANG Dongying2, NA Duo1

图1. 拉伸试样和断裂韧性试样尺寸图以及断裂韧性KIC与试样厚度B的关系图

Fig.1. Dimensional drawings of tensile specimen (a) and fracture toughness specimen (b) and relational graph between fracture toughness KIC and specimen thickness B (c) (unit: mm)