SCC behavior of model Alloy 600 containing minor element cerium in a caustic solution

Joung Soo Kim; Yong Sun Yi; Oh Chul Kwon; Yeonsoo Lim; Mahgyo Jung

SCC behavior of model Alloy 600 containing minor element cerium in a caustic solution

Joung Soo Kim, Yong Sun Yi, Oh Chul Kwon, Yeonsoo Lim, Mahgyo Jung

SG Materials Team

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

High purity model alloys with major compositions of Ni-15Cr-9Fe-0.03C (600CE0) and Ni-15Cr-9Fe-0.03C-0.04Ce (600CE4) were produced. Using these model alloys the effect of an alloying element, Ce, on the SCC behavior of Alloy 600 was evaluated. To precipitate the carbides on the grain boundaries, a thermal treatment (TT) was performed on both the solution annealed alloys. Microstructural examinations using SEM and TEM EDX techniques showed that the same structural carbides, Cr₇C₃, were precipitated in both alloys and no significant difference in the amount of Cr depletion along the grain boundaries was observed between the two model alloys. However, it was found that the coverage of the grain boundary by the carbides was higher in the Ce-bearing alloy (600CE4). The SCC susceptibility of the alloys was investigated in a 40%NaOH solution at 315°C. Being evaluated in terms of the maximum crack depth, the SCC susceptibility of the alloy turned out to be reduced by the addition of Ce. The increased resistance to SCC of alloy 600CE4 was attributed to the increased coverage of the grain boundaries by carbides.

Original language	British English
Title of host publication	Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Pages	1277-1284
Number of pages	8
State	Published - 2005
Event	12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors - Salt Lake City, UT, United States Duration: 14 Aug 2005 → 18 Aug 2005

Publication series

Name	Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Conference

Conference	12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Country/Territory	United States
City	Salt Lake City, UT
Period	14/08/05 → 18/08/05

Keywords

Alloy 600
Cerium
Stress Corrosion Cracking

Cite this

Kim, J. S., Yi, Y. S., Kwon, O. C., Lim, Y., & Jung, M. (2005). SCC behavior of model Alloy 600 containing minor element cerium in a caustic solution. In Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (pp. 1277-1284). (Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors).

Kim, Joung Soo ; Yi, Yong Sun ; Kwon, Oh Chul et al. / SCC behavior of model Alloy 600 containing minor element cerium in a caustic solution. Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. 2005. pp. 1277-1284 (Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors).

@inproceedings{409db66bf23042d7a28ffcc7b6f9eec9,

title = "SCC behavior of model Alloy 600 containing minor element cerium in a caustic solution",

abstract = "High purity model alloys with major compositions of Ni-15Cr-9Fe-0.03C (600CE0) and Ni-15Cr-9Fe-0.03C-0.04Ce (600CE4) were produced. Using these model alloys the effect of an alloying element, Ce, on the SCC behavior of Alloy 600 was evaluated. To precipitate the carbides on the grain boundaries, a thermal treatment (TT) was performed on both the solution annealed alloys. Microstructural examinations using SEM and TEM EDX techniques showed that the same structural carbides, Cr7C3, were precipitated in both alloys and no significant difference in the amount of Cr depletion along the grain boundaries was observed between the two model alloys. However, it was found that the coverage of the grain boundary by the carbides was higher in the Ce-bearing alloy (600CE4). The SCC susceptibility of the alloys was investigated in a 40%NaOH solution at 315°C. Being evaluated in terms of the maximum crack depth, the SCC susceptibility of the alloy turned out to be reduced by the addition of Ce. The increased resistance to SCC of alloy 600CE4 was attributed to the increased coverage of the grain boundaries by carbides.",

keywords = "Alloy 600, Cerium, Stress Corrosion Cracking",

author = "Kim, {Joung Soo} and Yi, {Yong Sun} and Kwon, {Oh Chul} and Yeonsoo Lim and Mahgyo Jung",

year = "2005",

language = "British English",

isbn = "9780873395953",

series = "Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors",

pages = "1277--1284",

booktitle = "Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors",

note = "12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ; Conference date: 14-08-2005 Through 18-08-2005",

}

Kim, JS, Yi, YS, Kwon, OC, Lim, Y & Jung, M 2005, SCC behavior of model Alloy 600 containing minor element cerium in a caustic solution. in Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, pp. 1277-1284, 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Salt Lake City, UT, United States, 14/08/05.

SCC behavior of model Alloy 600 containing minor element cerium in a caustic solution. / Kim, Joung Soo; Yi, Yong Sun; Kwon, Oh Chul et al.
Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. 2005. p. 1277-1284 (Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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T1 - SCC behavior of model Alloy 600 containing minor element cerium in a caustic solution

AU - Kim, Joung Soo

AU - Yi, Yong Sun

AU - Kwon, Oh Chul

AU - Lim, Yeonsoo

AU - Jung, Mahgyo

PY - 2005

Y1 - 2005

N2 - High purity model alloys with major compositions of Ni-15Cr-9Fe-0.03C (600CE0) and Ni-15Cr-9Fe-0.03C-0.04Ce (600CE4) were produced. Using these model alloys the effect of an alloying element, Ce, on the SCC behavior of Alloy 600 was evaluated. To precipitate the carbides on the grain boundaries, a thermal treatment (TT) was performed on both the solution annealed alloys. Microstructural examinations using SEM and TEM EDX techniques showed that the same structural carbides, Cr7C3, were precipitated in both alloys and no significant difference in the amount of Cr depletion along the grain boundaries was observed between the two model alloys. However, it was found that the coverage of the grain boundary by the carbides was higher in the Ce-bearing alloy (600CE4). The SCC susceptibility of the alloys was investigated in a 40%NaOH solution at 315°C. Being evaluated in terms of the maximum crack depth, the SCC susceptibility of the alloy turned out to be reduced by the addition of Ce. The increased resistance to SCC of alloy 600CE4 was attributed to the increased coverage of the grain boundaries by carbides.

AB - High purity model alloys with major compositions of Ni-15Cr-9Fe-0.03C (600CE0) and Ni-15Cr-9Fe-0.03C-0.04Ce (600CE4) were produced. Using these model alloys the effect of an alloying element, Ce, on the SCC behavior of Alloy 600 was evaluated. To precipitate the carbides on the grain boundaries, a thermal treatment (TT) was performed on both the solution annealed alloys. Microstructural examinations using SEM and TEM EDX techniques showed that the same structural carbides, Cr7C3, were precipitated in both alloys and no significant difference in the amount of Cr depletion along the grain boundaries was observed between the two model alloys. However, it was found that the coverage of the grain boundary by the carbides was higher in the Ce-bearing alloy (600CE4). The SCC susceptibility of the alloys was investigated in a 40%NaOH solution at 315°C. Being evaluated in terms of the maximum crack depth, the SCC susceptibility of the alloy turned out to be reduced by the addition of Ce. The increased resistance to SCC of alloy 600CE4 was attributed to the increased coverage of the grain boundaries by carbides.

KW - Alloy 600

KW - Cerium

KW - Stress Corrosion Cracking

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M3 - Conference contribution

AN - SCOPUS:33745190253

SN - 9780873395953

T3 - Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

SP - 1277

EP - 1284

BT - Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

T2 - 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Y2 - 14 August 2005 through 18 August 2005

ER -

Kim JS, Yi YS, Kwon OC, Lim Y, Jung M. SCC behavior of model Alloy 600 containing minor element cerium in a caustic solution. In Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. 2005. p. 1277-1284. (Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors).

SCC behavior of model Alloy 600 containing minor element cerium in a caustic solution

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Conference

Keywords

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