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Irradiation-Assisted Stress Corrosion Cracking of Heat-Affected Zones of Austenitic Stainless Steel Welds

机译:奥氏体不锈钢焊缝热影响区域的辐照辅助应力腐蚀开裂

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Irradiation assisted stress corrosion cracking is known to appear in the internal components of boiling water reactors such as core shrouds. Although the behaviour of austenitic stainless steels base material has been thoroughly investigated, few studies were dedicated to the weld metal and heat affected zones (HAZ). The goal of this study is a contribution to better understand the welding and neutron-irradiation induced changes in the HAZ that may promote intergranular cracking. The evolution of residual stresses, microstructure, microchemistry, mechanical properties, and the stress corrosion behaviour of two welded austenitic stainless steels have been investigated, before and after irradiation. Slow Strain Rate Tensile (SSRT) tests were performed. Flat tensile samples, containing the weld and HAZ were fabricated from type AISI 304 and AISI 347 stainless steels. SSRT corrosion tests were performed at 290°C in low conductivity water with 200 ppb dissolved oxygen. Reference tests were performed in inert gas (argon). The irradiated HAZs presents typical irradiation-induced defects with slightly increased density. The tensile tests reveal a significant hardening of the material that is clearly related to the irradiation induced microstructure. Finally no intergranular fracture is observed for the irradiation dose and deformation conditions studied.
机译:已知辐照辅助应力腐蚀裂解出现在沸水反应器如芯护罩的内部组分中。尽管奥氏体不锈钢基础材料的行为已经彻底研究,但很少有研究专用于焊接金属和热影响的区域(HAZ)。本研究的目标是更好地了解焊接和中子辐照诱导的危险中可能促进晶间裂缝的爆破的贡献。在照射之前和之后,研究了残留应力,微观结构,微型化学,机械性能和应力腐蚀行为的演变。进行慢应变率拉伸(SSRT)测试。含有焊接和斑纹的扁平拉伸样品由AISI 304型和AISI 347不锈钢制成。 SSRT腐蚀试验在290℃下在低电导率水中进行,具有200ppb溶解的氧。参考试验在惰性气体(氩气)中进行。辐照的HAZS呈现典型的辐射诱导的缺陷,密度略微增加。拉伸试验揭示了与辐照诱导的微观结构明显相关的材料的显着硬化。最后没有观察到辐照剂量和测量条件的晶间骨折。

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