A high-resolution characterization of the initiation of stress corrosion crack in Alloy 690 in simulated pressurized water reactor primary water

Kuang, Wenjun; Was, Gary S.

doi:10.1016/j.corsci.2019.108243

Title: A high-resolution characterization of the initiation of stress corrosion crack in Alloy 690 in simulated pressurized water reactor primary water

Journal Article · 01 February 2020 · Corrosion Science

DOI: https://doi.org/10.1016/j.corsci.2019.108243 · OSTI ID:1775695

Kuang, Wenjun; Was, Gary S.

Not Available

View Accepted Manuscript (Publisher)

Cite

Export

Save

Sponsoring Organization:: USDOE

OSTI ID:: 1775695

Journal Information:: Corrosion Science, Journal Name: Corrosion Science Journal Issue: C Vol. 163; ISSN 0010-938X

Publisher:: ElsevierCopyright Statement

Country of Publication:: United Kingdom

Language:: English

References (30)

Grain-Size Effects on the High-Temperature Oxidation of Modified 304 Austenitic Stainless Steel Kim, Ju-Heon; Kim, Dong-Ik; Suwas, Satyam Oxidation of Metals, Vol. 79, Issue 3-4 https://doi.org/10.1007/s11085-012-9347-x	journal	December 2012
The Effect of Temperature on the Preferential Intergranular Oxidation Susceptibility of Alloy 600 Bertali, G.; Burke, M. G.; Scenini, F. Metallurgical and Materials Transactions A, Vol. 49, Issue 5 https://doi.org/10.1007/s11661-018-4491-9	journal	February 2018
The IGSCC, sensitization, and microstructure study of Alloys 600 and 690 Kai, J. J.; Tsai, C. H.; Yu, G. P. Nuclear Engineering and Design, Vol. 144, Issue 3 https://doi.org/10.1016/0029-5493(93)90040-G	journal	November 1993
How oxidized grain boundaries fail Dugdale, Helen; Armstrong, David E. J.; Tarleton, Edmund Acta Materialia, Vol. 61, Issue 13 https://doi.org/10.1016/j.actamat.2013.05.012	journal	August 2013
The role of grain boundary microchemistry in irradiation-assisted stress corrosion cracking of a Fe-13Cr-15Ni alloy He, Mo-Rigen; Johnson, Drew C.; Was, Gary S. Acta Materialia, Vol. 138 https://doi.org/10.1016/j.actamat.2017.07.042	journal	October 2017
Insights into the stress corrosion cracking of solution annealed alloy 690 in simulated pressurized water reactor primary water under dynamic straining Kuang, Wenjun; Song, Miao; Was, Gary S. Acta Materialia, Vol. 151 https://doi.org/10.1016/j.actamat.2018.04.002	journal	June 2018
The effect of grain boundary structure on the intergranular degradation behavior of solution annealed alloy 690 in high temperature, hydrogenated water Kuang, Wenjun; Was, Gary S. Acta Materialia, Vol. 182 https://doi.org/10.1016/j.actamat.2019.10.041	journal	January 2020
The mechanism of oxide film formation on Alloy 690 in oxygenated high temperature water Kuang, Wenjun; Wu, Xinqiang; Han, En-Hou Corrosion Science, Vol. 53, Issue 11 https://doi.org/10.1016/j.corsci.2011.07.038	journal	November 2011
Influence of dissolved oxygen concentration on the oxide film formed on Alloy 690 in high temperature water Kuang, Wenjun; Wu, Xinqiang; Han, En-Hou Corrosion Science, Vol. 69 https://doi.org/10.1016/j.corsci.2012.12.003	journal	April 2013
The role of grain boundaries in the initial oxidation behavior of austenitic stainless steel containing alloyed Cu at 700°C for advanced thermal power plant applications Kim, Ju-Heon; Kim, Byung Kyu; Kim, Dong-Ik Corrosion Science, Vol. 96 https://doi.org/10.1016/j.corsci.2015.03.014	journal	July 2015
The effects of grain boundary carbide density and strain rate on the stress corrosion cracking behavior of cold rolled Alloy 690 Kuang, Wenjun; Was, Gary S. Corrosion Science, Vol. 97 https://doi.org/10.1016/j.corsci.2015.04.020	journal	August 2015
Advanced microstructural characterization of the intergranular oxidation of Alloy 600 Bertali, G.; Scenini, F.; Burke, M. G. Corrosion Science, Vol. 100 https://doi.org/10.1016/j.corsci.2015.08.010	journal	November 2015
Micro-mechanical measurement of fracture behaviour of individual grain boundaries in Ni alloy 600 exposed to a pressurized water reactor environment Stratulat, Alisa; Armstrong, David E. J.; Roberts, Steve G. Corrosion Science, Vol. 104 https://doi.org/10.1016/j.corsci.2015.10.019	journal	March 2016
High resolution analysis of oxidation in Ni-Fe-Cr alloys after exposure to 315 °C deaerated water with added hydrogen Persaud, S. Y.; Smith, J.; Korinek, A. Corrosion Science, Vol. 106 https://doi.org/10.1016/j.corsci.2016.02.009	journal	May 2016
Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment Lim, Yun Soo; Kim, Sung Woo; Hwang, Seong Sik Corrosion Science, Vol. 108 https://doi.org/10.1016/j.corsci.2016.02.040	journal	July 2016
The oxidation of alloy 690 in simulated pressurized water reactor primary water Kuang, Wenjun; Song, Miao; Wang, Peng Corrosion Science, Vol. 126 https://doi.org/10.1016/j.corsci.2017.07.004	journal	September 2017
The effect of cold rolling on grain boundary structure and stress corrosion cracking susceptibility of twins in alloy 690 in simulated PWR primary water environment Kuang, Wenjun; Was, Gary S.; Miller, Cody Corrosion Science, Vol. 130 https://doi.org/10.1016/j.corsci.2017.11.002	journal	January 2018
Mechanism of dislocation channel-induced irradiation assisted stress corrosion crack initiation in austenitic stainless steel McMurtrey, M. D.; Cui, B.; Robertson, I. Current Opinion in Solid State and Materials Science, Vol. 19, Issue 5 https://doi.org/10.1016/j.cossms.2015.04.001	journal	October 2015
Stress corrosion crack initiation in Alloy 690 in high temperature water Moss, Tyler; Kuang, Wenjun; Was, Gary S. Current Opinion in Solid State and Materials Science, Vol. 22, Issue 1 https://doi.org/10.1016/j.cossms.2018.02.001	journal	February 2018
Advanced TEM characterization of stress corrosion cracking of Alloy 600 in pressurized water reactor primary water environment Sennour, M.; Laghoutaris, P.; Guerre, C. Journal of Nuclear Materials, Vol. 393, Issue 2 https://doi.org/10.1016/j.jnucmat.2009.06.014	journal	September 2009
Strain incompatibilities and their role in intergranular cracking of irradiated 316L stainless steel West, E. A.; Was, G. S. Journal of Nuclear Materials, Vol. 441, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.10.021	journal	October 2013
Microstructural characterization on intergranular stress corrosion cracking of Alloy 600 in PWR primary water environment Lim, Yun Soo; Kim, Hong Pyo; Hwang, Seong Sik Journal of Nuclear Materials, Vol. 440, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.03.088	journal	September 2013
The effects of strain rate and carbon concentration on the dynamic strain aging of cold rolled Ni-based alloy in high temperature water Kuang, Wenjun; Was, Gary S. Scripta Materialia, Vol. 107 https://doi.org/10.1016/j.scriptamat.2015.05.033	journal	October 2015
Oxidation of nickel-base welds 182 and 82 in simulated primary water of pressurised water reactors Wehbi, M.; Couvant, T.; Duhamel, C. Materials at High Temperatures, Vol. 32, Issue 1-2 https://doi.org/10.1179/1878641314Y.0000000031	journal	January 2015
TEM investigations of intergranular stress corrosion cracking in austenitic alloys in PWR environmental conditions Lozano-Perez, S.; Titchmarsh, J. M. Materials at High Temperatures, Vol. 20, Issue 4 https://doi.org/10.1179/mht.2003.066	journal	January 2003
Volume and Grain Boundary Diffusion of Chromium in Ni-Base Ni-Cr-Fe Alloys Chen, Tien-Fu; Tiwari, Gyanendra Prasad; Iijima, Yoshiaki MATERIALS TRANSACTIONS, Vol. 44, Issue 1 https://doi.org/10.2320/matertrans.44.40	journal	January 2003
High-Resolution Characterization of Intergranular Attack and Stress Corrosion Cracking of Alloy 600 in High-Temperature Primary Water Thomas, L. E.; Bruemmer, S. M. CORROSION, Vol. 56, Issue 6 https://doi.org/10.5006/1.3280561	journal	June 2000
Dependence of Stress Corrosion Cracking of Alloy 690 on Temperature, Cold Work, and Carbide Precipitation—Role of Diffusion of Vacancies at Crack Tips Arioka, K.; Yamada, T.; Miyamoto, T. CORROSION, Vol. 67, Issue 3 https://doi.org/10.5006/1.3563640	journal	March 2011
Degradation of Alloy 690 After Relatively Short Times Arioka, Koji; Staehle, Roger W.; Yamada, T. CORROSION, Vol. 72, Issue 10 https://doi.org/10.5006/2107	journal	October 2016
Precursor Evolution and Stress Corrosion Cracking Initiation of Cold-Worked Alloy 690 in Simulated Pressurized Water Reactor Primary Water Zhai, Ziqing; Toloczko, Mychailo; Kruska, Karen CORROSION, Vol. 73, Issue 10 https://doi.org/10.5006/2470	journal	May 2017

Similar Records

Precursor Evolution and Stress Corrosion Cracking Initiation of Cold-Worked Alloy 690 in Simulated Pressurized Water Reactor Primary Water

Journal Article · 2017 · Corrosion · OSTI ID:1378041

Zhai, Ziqing; Toloczko, Mychailo; Kruska, Karen; +1 more

Insights into the stress corrosion cracking of solution annealed alloy 690 in simulated pressurized water reactor primary water under dynamic straining

Journal Article · 2018 · Acta Materialia · OSTI ID:1548490

Kuang, Wenjun; Song, Miao; Was, Gary S.

The oxidation of alloy 690 in simulated pressurized water reactor primary water

Journal Article · 2017 · Corrosion Science · OSTI ID:1549550

Kuang, Wenjun; Song, Miao; Wang, Peng; +1 more

Title: A high-resolution characterization of the initiation of stress corrosion crack in Alloy 690 in simulated pressurized water reactor primary water

Citation Formats

References (30)

Similar Records

Related Subjects