Trishelle Copeland-Johnson is a Materials Research Scientist at Idaho National Laboratory (INL) with an expertise in strategizing multi-modal advanced characterization techniques to elucidate surface damage mechanisms of materials, notably corrosion of nuclear structural materials. Dr. Copeland-Johnson arrived at INL as a Glenn T. Seaborg Distinguished Postdoctoral Research Associate in 2021, investigating the role of actinide products on the corrosion mechanisms of Ni-based superalloys in chloride molten salts and the synergistic effects of gamma irradiation and radiolysis on the evolution of surface corrosion products on aluminum spent nuclear fuel cladding alloys. Dr. Copeland-Johnson transitioned to Materials Research Scientist in 2022 and currently leads a number of projects pertaining to characterizing molten salt corrosion mechanisms. She leads an INL laboratory-based research and development initiative to elucidate the role of long-range ordering phase transformations on the corrosion mechanism of Ni-based alloys in molten salts. She is also co-PI on a project funded by the Department of Energy Office of Basic Energy Sciences, leading groundbreaking efforts to investigate the impact iodide fission products on the corrosion mechanism of Ni-based alloys in chloride molten salts. Dr. Copeland-Johnson also leads a team evaluating the performance of additively manufactured SS316H after corrosion in molten salt for the Advanced Materials and Manufacturing Technologies program, funded through the Office of Nuclear Energy.
Dr. Copeland-Johnson also has an extensive record of professional development and outreach activities. She has served as the chair and vice-chair for the User Executive Committee for the BNL Center for Functional Nanomaterials, a Department of Energy Nanoscale Science Research Center. Also, she is a stanch supporter of enhancing the workforce development pipeline for underrepresented ethnicities in science and engineering disciplines through professional organizations, such the National Organization for the Advancement of Black Chemists and Chemical Engineers (NOBCChE) and the Minerals, Metals, & Materials Society (TMS). She was also awarded the 2022 INL Materials and Fuels Complex Mentor of the Year.
"Milestone 1.2.15: Feasibility of In Situ Accelerated Aluminum Coupon Radiolysis by Synchrotron X-Rays"
Trishelle Copeland-Johnson,
Vol.
2023
Link
Extended dry storage of aluminum-clad spent nuclear fuel (ASNF) requires an assessment of the radiolytic generation of molecular hydrogen gas (H2) from the ASNF’s corrosion layers. H2 accumulation can potentially lead to storage canister embrittlement/rupture and the accumulation of flammable gas mixtures in accident scenarios. To date, computational models have been developed for the prediction of radiolytic H2 generation from samples exposed to lower absorbed dose regimes (up to ~3 MGy). However, greater accuracy is needed for higher absorbed doses (> 25 MGy) where the concentration of H2 ultimately reaches a steady-state. Data in this area is limited due to the amount of time taken (months) to accumulate such high gamma doses. Furthermore, a recent study observed radiation-induced damage to the surface of pre-corroded aluminum alloy coupons at high absorbed gamma doses. Despite this observation and its implications, there is currently no computational connection between the radiolytic formation of H2 and changes in the composition and morphology of the cladding’s corrosion layers with absorbed dose. To develop a better understanding of the processes and effects described above, the present study aimed to evaluate the feasibility of leveraging synchrotron x-ray capabilities for coupled accelerated irradiation and in situ surface characterization of ASNF alloys. To that end, National Synchrotron Light Source II (NSLS-II) beamtime was secured and a series of aluminum alloy 1100 (AA1100) wires, prepared under a variety of conditions, were interrogated using ex situ x-ray diffraction (XRD) and scanning electron microscopy (SEM) techniques at Idaho National Laboratory (INL) and ex situ and in situ XRD capabilities at the NSLS-II x-ray powder diffraction (XPD) beamline. Results indicated that performing synchrotron XRD using the available XPD beamline configuration can provide sufficient radiation dose but cannot discern changes in the composition and morphology of sample corrosion layers. Additionally, ex situ XRD and SEM data from Idaho National Laboratory (INL) indicated that the pre-corrosion of AA1100 wires did not generate an appreciably thick corrosion layer, as compared with previous aluminum coupon studies. These thinner surface corrosion layers were not sufficient for detection by both ex situ and in situ synchrotron XRD, specifically under consideration of the NSLS-II XPD beamline’s configuration primarily capturing information from the sample’s bulk material, i.e., aluminum metal. In summary, the use of the NSLS-II XPD beamline for promoting accelerated radiolysis and in situ surface characterization is not appropriate for this program’s goals. |
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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