Uniform corrosion behavior of Zr-1Sn-0.35Fe-0.15Cr-xNb alloys in 400 °C super-heated steam with oxygen

被引：8

作者：

Xu, Shitong ^{[1
]}

Bai, Yong ^{[1
]}

Huang, Jiansong ^{[1
]}

Yao, Meiyi ^{[1
]}

Hu, Lijuan ^{[1
]}

Lin, Xiaodong ^{[1
]}

Xie, Yaoping ^{[1
]}

Liang, Xue ^{[2
]}

Peng, Jianchao ^{[2
]}

Zhou, Bangxin ^{[1
]}

机构：

[1] Shanghai Univ, Sch Mat Sci & Engn, Shanghai 200444, Peoples R China

[2] Shanghai Univ, Lab Microstruct, Shanghai 200444, Peoples R China

来源：

CORROSION SCIENCE | 2023年 / 214卷

关键词：

A; Zirconium alloys; B; TEM; XPS; C; High temperature corrosion; DISSOLVED-OXYGEN; ZR-NB; ZIRCONIUM; OXIDATION; ZIRCALOY;

D O I：

10.1016/j.corsci.2023.111004

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Zr-1Sn-0.35Fe-0.15Cr-xNb (x = 0.05, 0.10, 0.15, wt%) alloys were designed to explore the effect of oxygen concentrations and Nb contents on the uniform corrosion behavior of the alloys. Results showed that the effect of trace Nb content on the uniform corrosion behavior of Zr alloys is related to the DO concentrations in steam; DO can accelerate the corrosion of the alloys, and this effect is enhanced with the increase of the DO concentrations. A mechanism of the accelerated corrosion rate by Nb and DO was proposed, which provides theoretical guidance for the selection of fuel cladding materials for small nuclear reactors.

引用

页数：13

共 41 条

[1]

[Anonymous], 2011, ASTM G2/G2M-06

[2] EFFECTS OF RADIATION AND OXYGEN ON AQUEOUS OXIDATION OF ZIRCONIUM AND ITS ALLOYS AT 290 DEGREES C [J].

BRADHURST, DH ;

SHIRVINGTON, PJ ;

HEUER, PM .

JOURNAL OF NUCLEAR MATERIALS, 1973, 46 (01) :53-76

[3] CORROSION BEHAVIOR OF Zr(Fex, Cr1-x)2 ALLOYS IN 400 °C SUPERHEATED STEAM [J].

Cao Xiaoxiao ;

Yao Meiyi ;

Peng Jianchao ;

Zhou Bangxin .

ACTA METALLURGICA SINICA, 2011, 47 (07) :882-886

[4] Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys [J].

Cox, B .

JOURNAL OF NUCLEAR MATERIALS, 2005, 336 (2-3) :331-368

[5]

Eucken C.M., 1989, ZIRCONIUM NUCL IND 8, P113

[6] PRODUCTS AT THE SURFACE OF ZIRCALOY CLADDING UNDER LOCA CONDITIONS [J].

FURUTA, T ;

MOTOHASHI, H .

JOURNAL OF NUCLEAR MATERIALS, 1980, 95 (03) :303-306

[7]

Garzarolli F., 1996, ZIRCONIUM NUCL IND 1, P850

[8]

Graham RA., 1989, 8 INT S ZIRC NUCL IN, P334

[9] The characterisation of second phases in the Zr-Nb and Zr-Nb-Sn-Fe alloys: A critical review [J].

Harte, Allan ;

Griffiths, Malcolm ;

Preuss, Michael .

JOURNAL OF NUCLEAR MATERIALS, 2018, 505 :227-239

[10]

Hauffe K, 1965, Oxidation of Metal. [M], P176

← 1 2 3 4 5 →