Page 54 - 《摩擦学学报》2020年第3期
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320                                     摩   擦   学   学   报                                第 40 卷


                                                                                  A


                                                                                     1 mm
                                                                                  B

            A-B


                                                                                    100 μm


               Fig. 11  The cross-section morphologies of worn 690 alloy,D=100 μm,T=90 ℃,690 alloy/06Cr13
                        图 11    690合金的剖面分析结果,D=100 μm,T=90 ℃,配副材料06Cr13

   致. 总体而言,690合金磨损不严重.                                    发生器传热管的微振磨损及其防护[J]. 核安全, 2006, (3): 27–32].
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   3    结论                                           [  5  ]  Ding  Xunshen.  The  design  safety  of  steam  generators  in  NPP[J].
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   增加,氧化程度加剧,磨损加剧;主要的磨损机制为磨
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   起的作用加剧. 由于水的作用,690合金的磨损轻微,                             of  nuclear  power  equipment  and  structures  for  a  long-term[J].
   其剖面未见裂纹和磨屑层.                                           Nuclear Power Engineering, 2000, 21(3): 221–231 (in Chinese) [唐
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   EPMA线扫描结果表明,在磨损区域中氧和铁的含量                               j.ysxb.1004.0609.2010.08.016.
   变化呈现锯齿状;黏着磨损致使的材料转移,690合金                         [  8  ]  Zheng Jinsong, Zhao Lina, Li Gan. The effect of contact force and
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