Long term oxidation resistance of alloys for gas-cooled reactors

被引：12

作者：

Cabet, C. ^{[1
]}

Duprey, B. ^{[1
]}

机构：

[1] CEA, DEN, DPC, SCCME,Lab Etud Corros Non Aqueuse, F-91191 Gif Sur Yvette, France

来源：

NUCLEAR ENGINEERING AND DESIGN | 2012年 / 251卷

关键词：

HIGH-TEMPERATURE CORROSION; NICKEL-BASE ALLOY; STRUCTURAL-MATERIALS; METALLIC MATERIALS; HELIUM; IMPURITIES; ENVIRONMENTS; INCONEL-617; MECHANISMS; BEHAVIOR;

D O I：

10.1016/j.nucengdes.2011.11.001

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Long term oxidation resistance of Alloy 617, Alloy 230, and Alloy X was investigated at 950 degrees C up to 5000 h in impure helium which simulates the environment of a high temperature reactor (HTR). Post-treatment examination showed that all materials oxidized during the tests with the growth of a surface chromium oxide that includes manganese or titanium. Oxidation induced the formation of a subsurface carbide-depleted zone. In addition, aluminum-containing alloys exhibited internal oxidation. Corrosion kinetics was globally parabolic corresponding to the growth of the external oxide as well as to internal oxidation. The oxidation behaviour of Alloy 617 is in good agreement with the data published in the 1980s. Alloy 230 and Alloy X showed smaller corrosion rate than Alloy 617. This higher oxidation of Alloy 617 was mainly attributed to a more intensive internal oxidation. Extrapolation of the measured kinetics over 20 years calls for the formation of a 50 mu m-thick surface Cr-oxide and for in-depth decarburization and penetration of alumina. (C) 2011 Elsevier B.V. All rights reserved.

引用

页码：139 / 145

页数：7

共 19 条

[1] THE CORROSION BEHAVIOR OF HIGH-TEMPERATURE ALLOYS DURING EXPOSURE FOR TIMES UP TO 10000 H IN PROTOTYPE NUCLEAR PROCESS HELIUM AT 700-DEGREES-C TO 900-DEGREES-C [J].

BATES, HGA .

NUCLEAR TECHNOLOGY, 1984, 66 (02) :415-428

[2] High temperature corrosion of structural materials under gas-cooled reactor helium [J].

Cabet, C ;

Terlain, A ;

Lett, P ;

Guétaz, L ;

Gentzbittel, JM .

MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION, 2006, 57 (02) :147-153

[3] Corrosion of high temperature metallic materials in VHTR [J].

Cabet, C. ;

Rouillard, F. .

JOURNAL OF NUCLEAR MATERIALS, 2009, 392 (02) :235-242

[4]

Cabet C., 2010, P ICAPP 10

[5] HIGH-TEMPERATURE CORROSION OF THE NICKEL-BASED ALLOY INCONEL-617 IN HELIUM CONTAINING SMALL AMOUNTS OF IMPURITIES [J].

CHRIST, HJ ;

KUNECKE, U ;

MEYER, K ;

SOCKEL, HG .

MATERIALS SCIENCE AND ENGINEERING, 1987, 87 (1-2) :161-168

[6] MECHANISMS OF HIGH-TEMPERATURE CORROSION IN HELIUM CONTAINING SMALL AMOUNTS OF IMPURITIES .2. CORROSION OF THE NICKEL-BASE ALLOY INCONEL-617 [J].

CHRIST, HJ ;

KUNECKE, U ;

MEYER, K ;

SOCKEL, HG .

OXIDATION OF METALS, 1988, 30 (1-2) :27-51

[7] MECHANISMS OF HIGH-TEMPERATURE CORROSION IN HELIUM CONTAINING SMALL AMOUNTS OF IMPURITIES .1. THEORETICAL AND EXPERIMENTAL CHARACTERIZATION OF THE GAS-PHASE [J].

CHRIST, HJ ;

SCHWANKE, D ;

UIHLEIN, T ;

SOCKEL, HG .

OXIDATION OF METALS, 1988, 30 (1-2) :1-26

[8]

Cook R. D., 1988, Proceedings of the International Conference on Courseware Design and Evaluation, P129

[9] OXIDATION OF NI-CR-AL ALLOYS BETWEEN 1000 DEGREES AND 1200 DEGREES C [J].

GIGGINS, CS ;

PETTIT, FS .

JOURNAL OF THE ELECTROCHEMICAL SOCIETY, 1971, 118 (11) :1782-&

[10] CORROSION OF METALLIC MATERIALS IN HTR-HELIUM ENVIRONMENTS [J].

GRAHAM, LW .

JOURNAL OF NUCLEAR MATERIALS, 1990, 171 (01) :76-83

← 1 2 →