Logan Joyce is a PhD student at Purdue University in the School of Nuclear Engineering. Since joining Purdue, he has gained experience in advanced manufacturing of ceramic materials including rare earth nitrides and garnet oxides as well as in the area of irradiation-assisted corrosion of accident tolerant fuel claddings. He has experience using various materials characterization tools such as scanning electron microscopes with energy dispersive x-ray spectroscopy, and x-ray diffractometers. His research interest is currently focused on accident tolerant fuel concepts for light water reactors including advanced fuels, claddings, and control rod materials. He has a BS in chemical engineering and an MS in nuclear engineering from University of Massachusetts Lowell.
"Oxidation behaviour of PM-C26M FeCrAl alloy in low-temperature steam 400 – 900 °C" Rajnikant V. Umretiya, Haozheng Qu, Zhongxia Shang, Yi Xie, Logan Joyce, [2025] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2025.101953 | |
"Oxide Layers in Ni-doped FeCrAl Alloy in 320°C Radioactive Hydrogenated Water" Peng Wang, Rajnikant V. Umretiya, Andrew Hoffman, Yi Xie, Logan Joyce, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.154987 · ISSN: 0022-3115 | |
"A Rapid Sintering Method for Cerium Nitride Pellet: A Uranium Mononitride Surrogate"
Yi Xie, Logan Joyce,
[2022]
Ceramics
· DOI: 10.3390/ceramics5040072
· ISSN: 2571-6131
Uranium mononitride (UN) is a candidate fuel material for light water reactors with higher uranium (U) loading and thermal conductivity than uranium dioxide (UO2). However, the sintering of UN pellets is challenging as the UN powder particles oxidize rapidly at high temperatures unless the oxygen concentration is extremely low. Oxidation during sintering either reduces the relative density of the sintered UN pellet or disintegrates the sintered UN pellet to powder. To address this problem, the present work developed a rapid sintering method for producing highly densified UN surrogate pellets with minimal oxidation. Cerium nitride (CeN) is used as a surrogate for UN to reduce radiation hazards. With the custom-developed fast-heating system, the sintering process was completed within 150 s. The sintering atmosphere was flowing nitrogen (N2). The sintered CeN pellet density was 95% of the theoretical density (TD) or higher. The microstructure was uniform with a 10–25 µm grain size as demonstrated by scanning electron microscopy (SEM) and contained trivial levels of oxides as demonstrated by X-ray diffraction (XRD). The resultant pellets indicate that the rapid sintering method is a promising method to make UN fuel pellets with equivalent or higher density to pellets made by conventional sintering methods, while also being more efficient in time and costs. |
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"Stochastic Approach to Inspection Evaluation: Methodology and Validation" [2022] ESARDA Bulletin · DOI: 10.3011/esarda.ijnsnp.2022.3 · EID: 2-s2.0-85133631918 · ISSN: 1977-5296 | |
Source: ORCID/CrossRef using DOI |
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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