NSUF - Nuclear Science User Facilities

Cynthia Adkins

Profile Information
Name
Dr. Cynthia Adkins
Institution
Idaho National Laboratory
Position
Staff Scientist
h-Index
ORCID
0000-0002-3834-6440
Expertise
Austenitic, Characterization, Iron Based Alloy, Martensite Steel, Microscopy, Plutonium Compounds, Stainless Steel, Thermal Conductivity, Thermal Diffusivity, Thermal Expansion, Thermophysical Properties, Uranium Compounds, Uranium Zirconium
Publications:
"Fuel-Cladding Interaction Between U-Pu-Zr Fuel and Fe" Assel Aitkaliyeva, James Cole, Brandon Miller, Cynthia Adkins, James Madden, Metallurgical and Materials Transactions E Vol. 2 2015 220-228 Link
This work investigates fuel-cladding chemical interaction (FCCI) between U-25Pu-14Zr (in wt pct) fuel and pure Fe at elevated temperatures, understanding of which is critical for evaluation of the fuel performance. Phases and microstructure formed in the quaternary uranium-plutonium-zirconium-iron (U-Pu-Zr-Fe) system were characterized using the transmission electron microscopy technique. Phases formed within the FCCI layer were identified using selective area electron diffraction (SAED) analysis as Fe2U (Fd- m), Fe2Zr (Fd-3m), a-U (Cmcm), Fe2Pu (Fd-3m), ß-Pu (C12/m1), and ß-Zr (Im-3m). U.S. Government Work. Not Protected by U.S. Copyright. Manuscript submitted June 23, 2015.
"Impact of neutron irradiation on the thermophysical properties of additively manufactured stainless steel and inconel" Mark Graham, Jeffrey King, Tsvetoslav Pavlov, Cynthia Adkins, Scott Middlemas, Donna Guillen, Journal of Nuclear Materials Vol. 549 2021 Link
"In-Pile Irradiation Induced Defects and the Effect on Thermal Diffusivity of MgO" Pavel Medvedev, Brandon Miller, Donald Moore, Juan Nino, Cynthia Adkins, Journal of Nuclear Materials Vol. 434 2013 90-96 Link
The effects of neutron irradiation temperature and dose on thermal diffusivity are investigated by comparing non-irradiated and in-pile irradiated MgO samples. MgO pellets were irradiated in-pile of the Advanced Test Reactor at Idaho National Laboratory. Samples were irradiated at 623 and 973 K to fast neutron fluences of ~1 x 1025 (1.5 dpa) and ~2 x 1025 n/m2 (3 dpa). Post irradiation examination included X-ray diffraction, scanning electron microscopy, laser flash thermal diffusivity, and transmission electron microscopy. Neutron irradiation of MgO causes a significant reduction in the thermal diffusivity (46 to 72% at room temperature) due to irradiation-induced defects. The radiation induced thermophysical and structural evolution of MgO is reported.
"TEM examination of phases formed between U–Pu–Zr fuel and Fe" Assel Aitkaliyeva, James Cole, Brandon Miller, Cynthia Adkins, James Madden, Journal of Nuclear Materials Vol. 467 2015 717-723 Link
Exposure to high temperatures and irradiation results in interaction and interdiffusion between fuel and cladding constituents that can lead to formation of undesirable brittle or low-melting point phases. A diffusion couple study has been conducted to understand fuel-cladding interaction occurring between Ue22Pue4Zr (in wt%) fuel and pure Fe at elevated temperatures. The phases formed within fuel claddingchemical interaction (FCCI) layer have been characterized in the transmission electron microscope (TEM). The phases formed within FCCI layer have been identified as Fe2U (Fd-3m), FeU6 (I4/mcm), Fe2Zr (Fd-3m), FeZr2 (I4/mcm), Fe2Pu (Fd-3m), UZr2 (P6/mmm), b-Zr (Im-3m), and ZrO2 (Fm-3m).
"TEM Identification of Phases in Metallic Pu-based Fuels" Assel Aitkaliyeva, Cynthia Adkins, James Madden, Microscopy & Microanalysis Vol. 22 2016 1476-1477 Link
"TEM identification of subsurface phases in ternary U–Pu–Zr fuel" Assel Aitkaliyeva, James Cole, Cynthia Adkins, James Madden, Journal of Nuclear Materials Vol. 473 2016 75-82 Link
Phases and microstructure in as-cast, annealed at 850 °C, and subsequently cooled U–23Pu–9Zr fuel were characterized using scanning and transmission electron microscopy techniques. SEM examination shows formation of three phases in the alloy that were identified in TEM using selective area diffraction pattern analysis: α-Zr globular and elongated δ-UZr2 inclusions and a thick oxide layer formed on top of β-Pu phase, which has been initially assumed to be ζ-(U, Pu). However, further examination of the cross-sectional TEM specimens identified the matrix phases as δ-UZr2, β-Pu, and (U, Zr)ht. Two types of inclusions were observed in the immediate vicinity of the specimen surface and they were consistent with α-Zr and ζ-(U, Pu).
Presentations:
" The Characterization of Microstructure and Chemistry of Transmutation Fuels" Assel Aitkaliyeva, Cynthia Adkins, 2017 ANS Annual Meeting June 12-15, (2017)
"Fabrication and Characterization of a Conduction Cooled Thermal Neutron Filter" Heng Ban, Thomas Hartmann, Cynthia Adkins, 2010 American Nuclear Society International Congress on Advances in Nuclear Power Plants ICAPP June 13-17, (2010)
"Thermal Conductivity Measurements of Irradiated Annular Low Burn-up U-10Zr Fuel" Mary Sevart, Daniele Salvato, Tiankai Yao, Cynthia Adkins, Luca Capriotti, Assel Aitkaliyeva, NSUF Annual Program Review April 15-17, (2025)
NSUF Articles:
NSUF awards 24 Rapid Turnaround Experiment proposals - Approximately $1.42M has been awarded. Wednesday, February 8, 2023 - Calls and Awards

About Us

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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