Yaqiao Wu

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Research Professor

Boise State University

United States

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About

Yaqiao Wu is a Research Professor at Boise State University in the United States. His research areas encompass the effects of neutron irradiation on various materials, including thermomechanical processing of alloys and the mechanical behavior of stainless steel and nuclear structural alloys. Recent publications highlight his work on irradiation hardening, microstructural analysis using atom probe tomography, and the behavior of advanced materials under extreme conditions.

Recent Grants

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In-situ nano-tensile testing of neutron-irradiated HT-9 steel

Open Date: 2020-10-01

Close Date:

Grant: Close

Ion-Irradiation and Microstructural Change Studies of Glassy Carbon

Open Date: 2020-01-01

Close Date:

Grant: Close

Atom Probe Tomography Investigation on the Precipitation of Neutron Irradiated Austenitic Stainless Steels 800H/800H-TMP

Open Date: 2020-01-01

Close Date:

Grant: Close

Neutron Radiation Effect on Diffusion between Zr (and Zircaloy) and Cr for Accurate Lifetime Prediction of ATF

Open Date: 2019-10-01

Close Date: 2022-09-01

Grant: Close

APT Study of Zr-(Mo, Nb, Ta) Diffusion for Designing the Diffusion Barrier Interlayer of Cr Coated Zircaloy Accident-Tolerant Fuels

Open Date: 2019-09-01

Close Date: 2020-10-01

Articles (16)

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2025

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2022

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UNITED STATES

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Badri Narayanan

Assistant Professor

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Recent Grants

Articles (16)

Temperature-dependent mechanism on hardening mitigation in thermomechanically processed 800H alloys under neutron irradiation

Irradiation-assisted pseudoelasticity in 316L stainless steel through dislocation loop-controlled martensitic phase transformations

Observations of the irradiation hardening behavior in neutron irradiated HT-9 steels through in situ TEM nano-mechanical tests

Comparison of PM-HIP to forged SA508 pressure vessel steel under high-dose neutron irradiation

Ion irradiation and examination of Additive friction stir deposited 316 stainless steel

Atom probe tomography of segregation at grain boundaries and gas bubbles in neutron irradiated U-10 wt% Mo fuel

The role of Cr, P, and N solutes on the irradiated microstructure of bcc Fe

Mechanical testing data from neutron irradiations of PM-HIP and conventionally manufactured nuclear structural alloys

Thermomechanical Properties of Neutron Irradiated Al3Hf-Al Thermal Neutron Absorber Materials

Catalyzed oxidation of nuclear graphite by simulated fission products Sr, Eu, and I

Novel effects of grain size and ion implantation on grain boundary segregation in ion irradiated austenitic steel

In situ ion irradiation of amorphous TiO2 nanotubes

Deformation-Assisted Rejuvenation of Irradiation-Induced Phase Instabilities in Cu-Ta Heterophase Nanocomposite

Nucleation and growth of molybdenum disulfide grown by thermal atomic layer deposition on metal oxides

Thermoelectric power generation in the core of a nuclear reactor

Additive Manufacturing of Miniaturized Peak Temperature Monitors for In-Pile Applications

Collaborators (9)

Yongfeng zhang

Elton Graugnard

Min Long

Lan Li

David Estrada

Badri Narayanan

Assel Aitkaliyeva

Rajiv Mishra

Janelle Wharry

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