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核电钢A508的腐蚀疲劳研究 |
王正;贺菁;任晨星 |
郑州工学院 |
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CORROSION FATIGUE OF REACTOR PRESSURE VESSEL STEEL A508 IN DISTILLED WATER |
WANG Zheng;HE Jing;REN Chenxing (Zhengzhou Institute of Technology) |
1NcikelRW,压力容器技术进展-1,缺陷分析.北京:机械工业出版社,19912McHenryHI,PenseAW.FatiguteCrackPropagationinSteelAlloyatElevatedTemperatures.ASTM,STP520;345~354,Philadelphia,19733CampbellJE,GerberichWW.断裂力学在选材方面的应用.北京:冶金工业出版社,19924KondoT,Kikuyanma.CorrosionFatigueofASTMA302BSteelinHighTemperatureWater,TheSimulatedNuclearReactorEnvironment,CorrosionFatigue:ChemistryMechanicsandMicrostructure.NACE-2,1971.5395NagataN.EnvironmentallyAssistedCrackingofStructuralMaterialsforLightWaterReactors.NRIMSpecialReport,TOkyo,19946KiesJA,etal.ASTM,SPT381,1965:3287H.克舍.金属腐蚀.北京:化学工业出版社,19848王正,张振宇,任晨星.中国腐蚀与防护学报,1994:14(1):439CongletonJ,ShojiT,ParknisRN.Corr.Sci.,1985,25:63310王正,王志奇.中国腐蚀与防护学报,1996,16(3):161. |
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