Xiang (Frank) Chen

Profile Information
Name
Dr. Xiang (Frank) Chen
Institution
Oak Ridge National Laboratory
Position
Research Staff
Affiliation
ASTM International
h-Index
16
ORCID
0000-0002-8662-5209
Biography

Dr. Xiang (Frank) Chen is a research staff member in the Materials Science & Technology Division of Oak Ridge National Laboratory. He is the principal investigator under several U.S. Department of Energy programs, including Fossil Energy and Carbon Management, Light Water Reactor Sustainability, and Fusion Materials Science. ​​​​​​​His research interests include the mechanical behavior of structural materials under extreme environments, such as radiation, elevated temperatures, and corrosive environment, and the correlation of mechanical property and materials microstructure. He has over 100 combined publications in peer-reviewed journals, conference proceedings, and technical reports. He is the co-chair for the ASTM E08.07.06 subcommittee in charge of ductile-brittle transition fracture toughness. He is the deputy pathway lead for the Light Water Reactor Sustainability Program Materials Research Pathway. Frank holds a Ph.D. degree and an M.S. degree in Nuclear Engineering from the University of Illinois at Urbana-Champaign and a B.E. degree in Nuclear Engineering from Shanghai Jiao Tong University in China.

Expertise
Mechanical Properties, PIE
Publications:
"Current Status of the Characterization of RPV Materials Harvested From the Decommissioned Zion Unit 1 Nuclear Power Plant" Thomas Rosseel, Xiang (Frank) Chen, ResearchGate Conference Paper Vol. 2017 Link
The decommissioning of Units 1 and 2 of the Zion Nuclear Power Station in Zion, Illinois, after ∼ 15 effective full-power years of service presents a unique opportunity to characterize the degradation of in-service reactor pressure vessel (RPV) materials and to assess currently available models for predicting radiation embrittlement of RPV steels [1–3]. Moreover, through-wall thickness attenuation and property distributions are being obtained and the results to be compared with surveillance specimen test data. It is anticipated that these efforts will provide a better understanding of materials degradation associated with extending the lifetime of existing nuclear power plants (NPPs) beyond 60 years of service and subsequent license renewal. In support of extended service and current operations of the US nuclear reactor fleet, the Oak Ridge National Laboratory (ORNL), through the U.S. Department of Energy, Light Water Reactor Sustainability (LWRS) Program, coordinated procurement of materials, components, and other items of interest from the decommissioned Zion NPPs. In this report, harvesting, cutting sample blocks, machining test specimens, test plans, and the current status of materials characterization of the RPV from the decommissioned Zion NPP Unit 1 will be discussed. The primary foci are the circumferential, Linde 80 flux, wire heat 72105 (WF-70) beltline weld and the A533B base metal from the intermediate shell harvested from a region of peak fluence (0.7 × 1019 n/cm2, E > 1.0 MeV) on the internal surface of the Zion Unit 1 vessel. Following the determination of the through-thickness chemical composition, Charpy impact, fracture toughness, tensile, and hardness testing are being performed to characterize the through-thickness mechanical properties of base metal and beltline-weld materials. In addition to mechanical properties, microstructural characterizations are being performed using various microstructural techniques, including Atom Probe Tomography, Small Angle Neutron Scattering, and Positron Annihilation Spectroscopy.