核能用2.25Cr-1Mo钢水蒸气氧化行为

doi:10.13228/j.boyuan.issn0449-749x.20200198

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Abstract In order to study the steam oxidation resistance of 2.25Cr-1Mo steel for nuclear power. A steam oxidation experiment of 2.25Cr-1Mo heat-resistant steel was carried out at 500 ℃ in 0.1 MPa for 600 h. Oxidation kinetics formulae was acquired from the weight gains results by analytical balance. Morphology and layered structure of oxide scales were characterized utilizing SEM. Phases of oxide products were identified by XRD and EDS. Results show that the steam oxidation weight gains curve of the 2.25Cr-1Mo steel conforms to the cubic law. The oxide scale has a double-layered structure,in which the inner layer is denser and the main phase is (Fe,Cr)₃O₄spinel,while the outer layer is loose and porous and the main phase are Fe₃O₄and Fe₂O₃. The measurement results of the corrosion rate of 2.25Cr-1Mo steel show that it has good resistance to steam oxidation.

Key words： 2.25Cr-1Mo steel high temperature steam oxidation kinetics morphology of oxide scale structure of oxide scale

Received: 15 April 2020

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	LI Chen-guang
	BAO Han-sheng
	LI Li
	BAI Yin
	ZHANG Wei
	ZHAO Ji-qing

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LI Chen-guang,BAO Han-sheng,LI Li等. Steam oxidation behavior of 2.25Cr-1Mo steel for nuclear power[J]. Iron and Steel, 2021, 56(1): 91-96.

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http://www.chinamet.cn/Jweb_gt/EN/10.13228/j.boyuan.issn0449-749x.20200198 OR http://www.chinamet.cn/Jweb_gt/EN/Y2021/V56/I1/91

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