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0Cr30Ni60Fe10(Inconel-690)是目前认为在高温水中耐应力腐蚀性能最为优良的新型合金。美、法、日等国已采用这种合金作为核电站蒸汽发生器管材,秦山核电厂二期工程也将采用这种合金作为蒸汽发生器管材。本试验的目的在于模拟PWR核电站蒸汽发生器(SG)二次侧管板堆积物碱性组分浓集工况,评价日本住友和法国Vallurac提供的Inconel-690合金管材和瑞典Sandvik提供的Incoloy-800合金管材的抗苛性应力腐蚀破裂(CSCC)性能。管材试样为C形环,加载状态以缺口变形量(⊿)为指标,
0Cr30Ni60Fe10 (Inconel-690) is currently considered the newest alloy with the most excellent stress corrosion resistance in high temperature water. The United States, France, Japan and other countries have adopted this alloy as a nuclear power plant steam generator pipe, Qinshan Nuclear Power Plant Phase II project will also use this alloy as a steam generator pipe. The purpose of this experiment is to simulate the concentration condition of alkaline components in the secondary tube plate stack of the steam generator (SG) of PWR nuclear power station. The evaluation of the properties of the Inconel-690 alloy pipe supplied by Sumitomo and Vallurac in France and the Incoloy- 800 alloy pipe anti-caustic stress corrosion cracking (CSCC) performance. Pipe samples for the C-ring, the load state to notch deformation (⊿) as an indicator,