New Insights into Internal Oxidation of Alloy 690 and Model Alloys in Hydrogenated Steam

被引:0
作者
Riahi, Ali [1 ]
Zhu, Hao [1 ]
Eskandari, Ali [1 ]
Persaud, Suraj Y. [2 ]
Newman, Roger C. [1 ]
机构
[1] Univ Toronto, Dept Chem Engn & Appl Chem, 200 Coll St, Toronto, ON M5S 3E5, Canada
[2] Queens Univ, Dept Mech & Mat Engn, 130 Stuart St, Kingston, ON K7L 3N6, Canada
基金
加拿大自然科学与工程研究理事会;
关键词
electron microscopy; internal oxidation; nickel alloy; preferential oxidation; stress corrosion cracking; time-of-flight-secondary ion mass spectrometry; STRESS-CORROSION CRACKING; PRIMARY WATER; GROWTH-RATE; BEHAVIOR; DIFFUSION;
D O I
10.5006/4439
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The oxidation behavior of Alloy 690 and Ni-xCr-10Fe model alloys exposed to 480 degrees C hydrogenated steam, in the nickel metal stability region, was studied using a variety of techniques, including time -resolved scanning electron microscopy, transmission electron microscopy, time -offlight secondary ion mass spectrometry, and electron energy loss spectroscopy. The alloy underwent internal oxidation intragranularly, resulting in the expulsion of metallic Ni nodules to the surface. A compact Cr-rich "healing" layer developed over time at the intragranular internal oxidation front near grain boundaries and significantly retards further internal oxidation. Protective external Cr-rich oxide formed at and very near the grain boundaries, hindering intergranular oxidation. In view of the fact that the protective oxide forms micrometers away from the grain boundaries, one cannot simply say that Cr diffuses up the boundary and forms an oxide that spreads laterally-internal stress relief must play a role, just as it does within the grains, only with different mechanisms at play.
引用
收藏
页码:11 / 23
页数:13
相关论文
共 46 条
  • [1] Effects of hydrogen on stress corrosion crack growth rate of nickel alloys in high-temperature water
    Andresen, P. L.
    Hickling, J.
    Ahluwalia, A.
    Wilson, J.
    [J]. CORROSION, 2008, 64 (09) : 707 - 720
  • [2] Andresen P.L., 2009, paper no. 09414
  • [3] Intergranular Stress Corrosion Cracking Growth Behavior of Ni-Cr-Fe Alloys in Pressurized Water Reactor Primary Water
    Arioka, Koji
    Yamada, Takuyo
    Miyamoto, Tomoki
    Aoki, Masanori
    [J]. CORROSION, 2014, 70 (07) : 695 - 707
  • [4] Advanced microstructural characterization of the intergranular oxidation of Alloy 600
    Bertali, G.
    Scenini, F.
    Burke, M. G.
    [J]. CORROSION SCIENCE, 2015, 100 : 474 - 483
  • [5] MICROSTRUCTURAL AND MICROCHEMICAL MECHANISMS CONTROLLING INTERGRANULAR STRESS-CORROSION CRACKING IN LIGHT-WATER-REACTOR SYSTEMS
    BRUEMMER, SM
    WAS, GS
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 216 : 348 - 363
  • [6] Selective internal oxidation as a mechanism for intergranular stress corrosion cracking of Ni-Cr-Fe alloys
    Capell, Brent M.
    Was, Gary S.
    [J]. METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2007, 38A (06): : 1244 - 1259
  • [7] Combrade P., 2005, Proc. 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, The Minerals, Metals, and Materials Society [TMS], Salt Lake City, P883
  • [8] Coriou H., 1960, 3 METALLURGY S AMSTE, P161
  • [9] A CRITIQUE OF INTERNAL OXIDATION IN ALLOYS DURING THE POST-WAGNER ERA
    DOUGLASS, DL
    [J]. OXIDATION OF METALS, 1995, 44 (1-2): : 81 - 111
  • [10] IGSCC BEHAVIOR OF ALLOY 600 STEAM-GENERATOR TUBING IN WATER OR STEAM TESTS ABOVE 360-C
    ECONOMY, G
    JACKO, RJ
    PEMENT, FW
    [J]. CORROSION, 1987, 43 (12) : 727 - 734