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Journal Articles

Effects of Cold-Work Degree on Stress Corrosion Cracking Behavior of Alloy 600 in Simulated Boiling Water Reactor (BWR) Water Environments

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Wen-Feng Lu, Jiunn-Yuan Huang, Tai-Cheng Chen, Kun-Chao Tsai
Journal: Corrosion
CORROSION (2020) 76 (10): 930–940.
https://doi.org/10.5006/3426
Published: 08 July 2020
View articletitled, Effects of Cold-Work Degree on Stress Corrosion Cracking Behavior of Alloy 600 in Simulated Boiling Water Reactor (BWR) Water Environments
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Journal Articles

Hydrothermal Corrosion of Coatings on Silicon Carbide in Boiling Water Reactor Conditions

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Stephen S. Raiman, Peter Doyle, Caen Ang, Yutai Katoh, Kurt A. Terrani
Journal: Corrosion
CORROSION (2019) 75 (2): 217–223.
https://doi.org/10.5006/2997
Published: 13 November 2018
View articletitled, Hydrothermal Corrosion of Coatings on Silicon Carbide in Boiling Water Reactor Conditions
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Journal Articles

A Brief History of Environmental Cracking in Hot Water

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Peter L. Andresen
Journal: Corrosion
CORROSION (2019) 75 (3): 240–253.
https://doi.org/10.5006/2881
Published: 14 July 2018
View articletitled, A Brief History of Environmental Cracking in Hot Water
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Journal Articles

2015 Frank Newman Speller Award: Stress Corrosion Cracking and Nuclear Power

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J.A. Gorman
Journal: Corrosion
CORROSION (2015) 71 (12): 1414–1433.
https://doi.org/10.5006/1898
Published: 01 December 2015
View articletitled, 2015 Frank Newman Speller Award: Stress Corrosion Cracking and Nuclear Power
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Journal Articles

Stress Corrosion Cracking of Ferritic-Martensitic Steels in Simulated Boiling Water Reactor Environment

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Parag M. Ahmedabadi, Gary S. Was
Journal: Corrosion
CORROSION (2016) 72 (1): 66–77.
https://doi.org/10.5006/1806
Published: 05 October 2015
View articletitled, Stress Corrosion Cracking of Ferritic-Martensitic Steels in Simulated Boiling Water Reactor Environment
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Journal Articles

Effect of Flow Conditions on the Deposition of Platinum Nanoparticles on Stainless Steel Surfaces

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Pascal V. Grundler, Amuthan Ramar, Lyubomira Veleva, Stefan Ritter
Journal: Corrosion
CORROSION (2015) 71 (1): 101–113.
https://doi.org/10.5006/1263
Published: 29 July 2014
View articletitled, Effect of Flow Conditions on the Deposition of Platinum Nanoparticles on Stainless Steel Surfaces
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Journal Articles

2012 Research Topical Symposium Proceedings – “Corrosion Degradation of Materials in Nuclear Power Reactors—Lessons Learned and Future Challenges”

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Raul B. Rebak
Journal: Corrosion
CORROSION (2013) 69 (10): 951–952.
https://doi.org/10.5006/0010-9312-69.10.951
Published: 01 September 2013
View articletitled, 2012 Research Topical Symposium Proceedings – “Corrosion Degradation of Materials in Nuclear Power Reactors—Lessons Learned and Future Challenges”
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Journal Articles

Stress Corrosion Cracking of Current Structural Materials in Commercial Nuclear Power Plants

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Peter L. Andresen
Journal: Corrosion
CORROSION (2013) 69 (10): 1024–1038.
https://doi.org/10.5006/0801
Published: 22 February 2013
View articletitled, Stress Corrosion Cracking of Current Structural Materials in Commercial Nuclear Power Plants
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Journal Articles

Irradiation-Assisted Stress Corrosion Cracking and Impact on Life Extension

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Anna Hojná
Journal: Corrosion
CORROSION (2013) 69 (10): 964–974.
https://doi.org/10.5006/0803
Published: 05 February 2013
View articletitled, Irradiation-Assisted Stress Corrosion Cracking and Impact on Life Extension
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Journal Articles

Historical Experience Providing Bases for Predicting Corrosion and Stress Corrosion in Emerging Supercritical Water Nuclear Technology: Part 1—Review

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X. Ru, R.W. Staehle
Journal: Corrosion
CORROSION (2013) 69 (3): 211–229.
https://doi.org/10.5006/0726
Published: 10 August 2012
View articletitled, Historical Experience Providing Bases for Predicting Corrosion and Stress Corrosion in Emerging Supercritical Water Nuclear Technology: Part 1—Review
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Journal Articles

Capabilities for Conducting Crack Growth Test of Neutron-Irradiated Alloys in Light Water Reactor Environments

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Y. Ashida, A. Flick, P.L. Andresen, G.S. Was
Journal: Corrosion
CORROSION (2013) 69 (2): 136–144.
https://doi.org/10.5006/0708
Published: 27 July 2012
View articletitled, Capabilities for Conducting Crack Growth Test of Neutron-Irradiated Alloys in Light Water Reactor Environments
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Journal Articles

Effect of Low-Temperature Sensitization on Intergranular Stress Corrosion Cracking Behavior of Austenitic Stainless Steels in Simulated Boiling Water Reactor Environment

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S.C. Bali, V. Kain, V.S. Raja
Journal: Corrosion
CORROSION (2009) 65 (11): 726–740.
https://doi.org/10.5006/1.3319099
Published: 01 November 2009
View articletitled, Effect of Low-Temperature Sensitization on Intergranular Stress Corrosion Cracking Behavior of Austenitic Stainless Steels in Simulated Boiling Water Reactor Environment
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Journal Articles

Stress Corrosion Cracking Crack Growth Behavior of Type 316L Stainless Steel Weld Metals in Boiling Water Reactor Environments

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J.H. Kim, R.G. Ballinger
Journal: Corrosion
CORROSION (2008) 64 (8): 645–656.
https://doi.org/10.5006/1.3279925
Published: 01 August 2008
View articletitled, Stress Corrosion Cracking Crack Growth Behavior of Type 316L Stainless Steel Weld Metals in Boiling Water Reactor Environments
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Journal Articles

Fatigue Crack Growth Behavior of Sensitized Type 304 Stainless Steel Under Boiling Water Reactor Conditions

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Y.Y. Chen, H.C. Shih, L.H. Wang, J.C. Oung
Journal: Corrosion
CORROSION (2007) 63 (11): 997–1008.
https://doi.org/10.5006/1.3278324
Published: 01 November 2007
View articletitled, Fatigue Crack Growth Behavior of Sensitized Type 304 Stainless Steel Under Boiling Water Reactor Conditions
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Journal Articles

Stress Corrosion Cracking Behavior of Alloys in Aggressive Nuclear Reactor Core Environments

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G.S. Was, P.L. Andresen
Journal: Corrosion
CORROSION (2007) 63 (1): 19–45.
https://doi.org/10.5006/1.3278331
Published: 01 January 2007
View articletitled, Stress Corrosion Cracking Behavior of Alloys in Aggressive Nuclear Reactor Core Environments
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Journal Articles

Evaluation of Alternate Reductants for Application in Light Water Reactors

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Y.-J. Kim
Journal: Corrosion
CORROSION (2006) 62 (9): 795–800.
https://doi.org/10.5006/1.3278304
Published: 01 September 2006
View articletitled, Evaluation of Alternate Reductants for Application in Light Water Reactors
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Journal Articles

Erratum: Factors Affecting the Crack Growth Rates of Reactor Pressure Vessel Steels Under Simulated Boiling Water Reactor Conditions

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Journal: Corrosion
CORROSION (2006) 62 (6): 552.
https://doi.org/10.5006/1.3280393
Published: 01 June 2006
View articletitled, Erratum: Factors Affecting the Crack Growth Rates of Reactor Pressure Vessel Steels Under Simulated Boiling Water Reactor Conditions
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Journal Articles

Factors Affecting the Crack Growth Rates of Reactor Pressure Vessel Steels Under Simulated Boiling Water Reactor Conditions

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Y.Y. Chen, H.C. Shih, L.H. Wang, J.C. Oung
Journal: Corrosion
CORROSION (2006) 62 (5): 403–418.
https://doi.org/10.5006/1.3278278
Published: 01 May 2006
View articletitled, Factors Affecting the Crack Growth Rates of Reactor Pressure Vessel Steels Under Simulated Boiling Water Reactor Conditions
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Journal Articles

Electrochemical Mitigation of Intergranular Stress Corrosion Cracking in Boiling Water Reactors

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Y.-J. Kim
Journal: Corrosion
CORROSION (2005) 61 (9): 889–894.
https://doi.org/10.5006/1.3280658
Published: 01 September 2005
View articletitled, Electrochemical Mitigation of Intergranular Stress Corrosion Cracking in Boiling Water Reactors
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Journal Articles

Influences of Stress Intensity Factor and Dissolved Hydrogen on the Fatigue Crack Growth Behavior of Low-Alloy Steel in Boiling Water Reactors

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Y.Y. Chen, L.H. Wang, J.C. Oung, H.C. Shih
Journal: Corrosion
CORROSION (2005) 61 (3): 273–284.
https://doi.org/10.5006/1.3280636
Published: 01 March 2005
View articletitled, Influences of Stress Intensity Factor and Dissolved Hydrogen on the Fatigue Crack Growth Behavior of Low-Alloy Steel in Boiling Water Reactors
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