Yachun Wang

Profile Information

Name: Dr. Yachun Wang
Institution: Idaho National Laboratory
Position: Postdoc Research Associate
Affiliation: Nuclear Science &Technology
h-Index: 10
ORCID: 0000-0002-4952-3633
Biography: Yachun (Ya) Wang is currently a Postdoc Research Associate in Irradiated Fuels and Materials department (C610) at Idaho National Laboratory (INL). Yachun earned her Ph.D in Nuclear Science & Technology from Rensselaer Polytechnic Institute (RPI). Yachun has research background in uncovering the corrosion mechanism in ceramic materials and molten salt cored NiCr alloys through microstructural characterization methods (X-ray, SEM, FIB, TEM, and XPS). She also accumulated hands-on experience in in-situ microscale mechanical testing of structural materials and characterizing irradiated metallic fuel during her internship at INL-MFC. In the current Postdoc position, Yachun is focusing on in-situ microscale mechanical testing of nuclear materials. In addition, Yachun will promote the development and application of microscale digital image correlation (µDIC) method to facilitate full-filed and local displacement and strain analysis for microscale mechanical testing.
Expertise: Electron Microscopy, Fuel Cladding Chemical Interaction (FCCI), Irradiated Cladding, Microstructural Analysis, Tensile Properties

Publications:

		"Fuel-cladding chemical interaction of a prototype annular U-10Zr fuel with Fe-12Cr ferritic/martensitic HT-9 cladding" Xiang Liu, Luca Capriotti, Tiankai Yao, Jason Harp, Michael Benson, Yachun Wang, Fei Teng, Lingfeng He, https://www.sciencedirect.com/science/article/pii/S002231152031196X#ack0001 Vol. 544 2021 Link
		"Measurement of grain boundary strength of Inconel X-750 superalloy using in-situ micro-tensile testing techniques in FIB/SEM system" Yachun Wang, Xiang Liu, Daniel Murray, Fei Teng, Wen Jiang, Mukesh Bachhav, Laura Hawkins, Emmanuel Perez, Cheng Sun, Xianming Bai, Jie Lian, Colin Judge, John Jackson, Robert Carter, Lingfeng He, Materials Science & Engineering Vol. 849 2022 Link

NSUF Articles:

RTE 2nd Call Awards Announced - Projects total approximately $1.6 million These project awards went to principal investigators from 26 U.S. universities, eight national laboratories, two British universities, and one Canadian laboratory. Tuesday, May 14, 2019 - Calls and Awards
Department of Energy Nuclear Science User Facilities Awards 29 Rapid Turnaround Experiment Proposals - Awarded projects total nearly $1.14M in access awards Tuesday, June 8, 2021 - News Release, Calls and Awards

Accomplishments

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NSUF Author

Authored an NSUF-supported publication

NSUF Submitter

Submitted an RTE Proposal to NSUF

Accomplished Researcher

Awarded 3+ RTE Proposals

Accomplished Collaborator

Collaborated on 3+ RTE Proposals

NSUF Supported Research

A first Investigation in Lanthanide-induced Grain Boundary Embrittlement in HT9 Cladding via In-situ Micro-tensile Testing - FY 2021 RTE 1st Call, #4345

In-situ high temperature micro-tensile testing of reactor irradiated HT9 cladding - FY 2023 RTE 3rd Call, #4673

In-situ TEM Heating Investigation of M23C6 Stability in Neutron Irradiated HT9 - FY 2024 Super RTE Call, #5078

TEM Characterization of Neutron Irradiated Nd2Zr2O7 and Its Thermal Recovery Behavior - FY 2019 RTE 2nd Call, #1814

NSUF Research Collaborations

Determining Mechanical Properties of the Phases Formed of Irradiated U-19Pu-10Zr - FY 2023 RTE 3rd Call, #4751

In-situ Micro-tensile Testing for Measuring Grain Boundary Strength of NiCr Alloys under Simultaneous Irradiation and Corrosion Environments - FY 2020 RTE 1st Call, #3028

In-Situ TEM Nanomechanical Testing of Neutron Irradiated U-10Zr - FY 2024 RTE 3rd Call, #5177

In-situ TEM study of microstructural evolution and deformation in FFTF irradiated HT-9 cladding - FY 2024 RTE 3rd Call, #5142

Nano indentation hardness of U10Zr - FY 2024 RTE 3rd Call, #5181