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Yiren Chen

Argonne National Laboratory

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Archive | 2017

Investigation of the Use of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials

Vijay K. Vasudevan; John Jackson; Sebastien Teysseyre; Bogdan Alexandreanu; Yiren Chen

In this study, the effects of laser shock peening (LSP) on stress corrosion cracking (SCC) behavior of nickel based Alloy 600 in tetrathionate solution were investigated. The LSP induced compressive residual stresses and changes in the near surface microstructure, hardness were characterized. The effects of LSP on SCC susceptibility of Alloy 600 in tetrathionate solution were evaluated by slow strain rate tests and constant load tests. The results indicate a significantly longer time to failure and decreased susceptibility to SCC. These improvements were attributed to LSP induced compressive residual stresses, increased yield strength and hardening caused by near-surface microstructural changes.

Metallurgical and Materials Transactions A-physical Metallurgy and Materials Science | 2010

Evolution of Carbide Precipitates in 2.25Cr-1Mo Steel during Long-Term Service in a Power Plant

Yong Yang; Yiren Chen; Kumar Sridharan; Todd R. Allen

Journal of Nuclear Materials | 2015

Irradiation response of delta ferrite in as-cast and thermally aged cast stainless steel

Z. Li; Wei-Yang Lo; Yiren Chen; Janne Pakarinen; Yaqiao Wu; Todd M. Allen; Yong Yang

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors | 2012

Irradiation Microstructure of Austenitic Steels and Cast Steels Irradiated in the BOR-60 Reactor at 320°C

Yong Yang; Yiren Chen; Yina Huang; Todd M. Allen; A. S. Rao

Archive | 2015

Crack Growth Rate and Fracture Toughness J-R Curve Tests on Irradiated Cast Austenitic Stainless Steels

Yiren Chen; Bogdan Alexandreanu; Wei-Ying Chen; Zhangbo Li; Yong Yang; K. Natesan; A. S. Rao

Archive | 2009

PERSPECTIVES ON CORROSION IN SUPERCRITICAL WATER ENVIRONMENT: MATERIALS AND NOVEL TREATMENTS

Kumar Sridharan; Yiren Chen; Lizhen Tan; Xiaopin Ren; A. Kruizenga; Michael C. Anderson; Todd Allen

Journal of Nuclear Materials | 2018

Microstructural evolution of NF709 austenitic stainless steel under in-situ ion irradiations at room temperature, 300, 400, 500 and 600 °C

Chi Xu; Wei-Ying Chen; Yiren Chen; Yong Yang

Journal of Nuclear Materials | 2018

Irradiation effects in high entropy alloys and 316H stainless steel at 300 °C

Wei-Ying Chen; Xiang Liu; Yiren Chen; Jien-Wei Yeh; Ko-Kai Tseng; K. Natesan

ASME 2017 Pressure Vessels and Piping Conference | 2017

Fracture Toughness and Deformation Behavior of Cast Austenitic Stainless Steels After Thermal Aging

Yiren Chen; Wei-Ying Chen; Chi Xu; Xuan Zhang; Z. Li; Yong Yang; A. S. Rao; Bogdan Alexandreanu; K. Natesan

Archive | 2015

STRESS CORROSION CRACKING OF ALLOY 152 WELD BUTTER NEAR THE LOW ALLOY STEEL INTERFACE

Bogdan Alexandreanu; Yiren Chen; Ken Natesan; William J. Shack

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Yong Yang

Argonne National Laboratory

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Bogdan Alexandreanu

Argonne National Laboratory

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K. Natesan

Argonne National Laboratory

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Wei-Ying Chen

Argonne National Laboratory

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A. S. Rao

Nuclear Regulatory Commission

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Chi Xu

University of Florida

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Ken Natesan

Argonne National Laboratory

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Kumar Sridharan

University of Wisconsin-Madison

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William J. Shack

Argonne National Laboratory

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Yina Huang

Argonne National Laboratory

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