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目前,PWR核电站蒸汽发生器传热管材趋向于选用耐应力腐蚀合金Inconel-690。因此,对日本、法国产的Inconel-690合金的耐应力腐蚀性能进行了评价。实验方法是在沸腾的42%氯化镁溶液中恒变形C型弯曲试验。标准号为GB4334.8-84。
At present, PWR nuclear power plant steam generator heat transfer pipe tend to choose resistant stress corrosion alloy Inconel-690. Therefore, the stress corrosion resistance of Inconel-690 alloy produced in Japan and France was evaluated. The experimental method is a constant deformation C-type bending test in a boiling 42% magnesium chloride solution. Standard No. GB4334.8-84.