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E.A. West

University of Michigan

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Publication

Featured researches published by E.A. West.

Journal of Nuclear Materials | 2007

Corrosion and stress corrosion cracking in supercritical water

Gary S. Was; Pantip Ampornrat; Gaurav Gupta; S. Teysseyre; E.A. West; Todd R. Allen; Kumar Sridharan; Lizhen Tan; Yun Chen; X. Ren; C. Pister

Journal of Nuclear Materials | 2009

IGSCC of grain boundary engineered 316L and 690 in supercritical water

E.A. West; Gary S. Was

Journal of Nuclear Materials | 2007

Effect of irradiation on stress corrosion cracking in supercritical water

S. Teysseyre; Zhijie Jiao; E.A. West; Gary S. Was

Reference Module in Materials Science and Materials Engineering#R##N#Comprehensive Nuclear Materials | 2012

Material Performance in Supercritical Water

Todd R. Allen; Yun Chen; X. Ren; Kumar Sridharan; Lizhen Tan; Gary S. Was; E.A. West; D. Guzonas

Journal of Nuclear Materials | 2009

Irradiation-assisted stress corrosion cracking of austenitic alloys in supercritical water

Rongsheng Zhou; E.A. West; Zhijie Jiao; Gary S. Was

Journal of Nuclear Materials | 2011

A model for the normal stress dependence of intergranular cracking of irradiated 316L stainless steel in supercritical water

E.A. West; Gary S. Was

Journal of Nuclear Materials | 2013

Strain incompatibilities and their role in intergranular cracking of irradiated 316L stainless steel

E.A. West; Gary S. Was

Metallurgical and Materials Transactions A-physical Metallurgy and Materials Science | 2012

Role of Localized Deformation in Irradiation-Assisted Stress Corrosion Cracking Initiation

E.A. West; M.D. McMurtrey; Zhijie Jiao; Gary S. Was

13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007 | 2007

Influence of irradiation induced microstructure on the stress corrosion cracking behavior of austenitic alloys in supercritical water

E.A. West; S. Teysseyre; Z. Jiao; Gary S. Was

714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009 | 2009

Intergranular cracking behavior of irradiated austenitic alloys in supercritical water

G. S. Was; R. Zhou; E.A. West; Z. Jiao

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Collaboration

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Gary S. Was

University of Michigan

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S. Teysseyre

University of Michigan

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Zhijie Jiao

University of Michigan

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Kumar Sridharan

University of Wisconsin-Madison

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Lizhen Tan

Oak Ridge National Laboratory

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Todd R. Allen

University of Wisconsin-Madison

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X. Ren

University of Wisconsin-Madison

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Yun Chen

West Virginia University

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C. Pister

University of Wisconsin-Madison

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Gaurav Gupta

University of Michigan

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