Stress-Corrosion Cracking of an Inconel 600 Safe-End on a Reactor Nozzle

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Abstract

Cracking occurred in an ASME SB166 Inconel 600 safe-end forging on a nuclear reactor coolant water recirculation nozzle while it was in service. The safe-end was welded to a stainless-steel-clad carbon steel nozzle and a type 316 stainless steel transition metal pipe segment. An Inconel 600 thermal sleeve was welded to the safe-end, and a repair weld had obviously been made on the outside surface of the safe-end to correct a machining error. Initial visual examination of the safe-end disclosed that the cracking extended over approximately 85 deg of the circular circumference of the piece. Investigation (visual inspection, on-site radiographic inspection, limited ultrasonic inspection, chemical analysis, 53x metallographic cross sections and SEM images etched in 8:1 phosphoric acid) supported the conclusion that the cracking mechanism was intergranular SCC. No recommendations were made.
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反应器喷嘴上英科乃尔600安全端应力腐蚀开裂
核反应堆冷却水再循环喷嘴安全端锻件在使用过程中发生断裂。安全端焊接在不锈钢包层碳钢喷嘴和316型不锈钢过渡金属管段上。在安全端焊接了一个英科乃尔600热套管,并在安全端外表面进行了明显的补焊,以纠正加工误差。对安全端进行的初步目视检查显示,裂纹延伸了大约85度的圆周。调查(目视检查、现场射线检查、有限超声检查、化学分析、53x金相截面和8:1磷酸蚀刻的SEM图像)支持裂纹机制为晶间SCC的结论。没有提出任何建议。
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