Peter Chou

Profile Information
Name
Dr. Peter Chou
Institution
Electric Power Research Institute
Position
Principal Technical Leader
Affiliation
ANS
h-Index
ORCID
0000-0001-6203-7974
Biography

Dr. Peter Chou is a Principal Technical Leader in the Nuclear Sector of the Electric Power Research Institute (EPRI), an independent, nonprofit organization for public interest energy and environmental research that conducts research, development, and demonstration projects for the benefit of the public in the United States and internationally. He manages research on stress corrosion cracking and irradiation-assisted stress corrosion cracking in the primary environments of light-water reactors, focusing on the link between material microstructure and material reliability, and on the application of advanced characterization and micromechanical testing for industrial research. 

Expertise
Atom Probe Tomography, Irradiated Stainless Steel, Irradiation Assisted Stress Corrosion Cracking, Micromechanical Testing, Stress Corrosion Cracking
Publications:
"Correlative STEM-APT characterization of radiation-induced segregation and precipitation of in-service BWR 304 stainless steel" Timothy Lach, Kayla Yano, Danny Edwards, Thak Sang Byun, Peter Chou, Journal of Nuclear Materials Vol. 549 2021 Link
Radiation induced segregation and precipitation phenomena in an in-service boiling water reactor 304 stainless steel component were investigated using directly correlated 3D-atom probe tomography and scanning transmission electron microscopy. Significant quantitative differences in measured segregation at grain boundaries were found between the atom probe and energy dispersive spectroscopy measurements of the exact same locations. In particular, a much stronger Si segregation (~10 atomic% via atom probe versus ~4 atomic% via electron microscopy) and different Cr profile shapes were detected that are critical to models of radiation induced segregation and stress corrosion cracking behavior. These quantitative differences highlight the need for comparative microscopy and critical evaluation of limitations in each analytical method. Elemental segregation to dislocations and conjoined-clusters were also highlighted by atom probe; confirming and expanding upon what has been observed in test reactor neutron and accelerator-based ion irradiations.
Presentations:
"Irradiation Assisted Stress Corrosion Cracking Susceptibility of Alloy X-750 Exposed to BWR Environments" Peter Chou, John Jackson, Sebastien Teysseyre, TMS-2017 conference [unknown]