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E.J. Lahoda

Observed names: E. J. LAHODA, E. J. Lahoda, E. Lahoda, Edward J. Lahoda, Edward Lahoda, Lahoda, E. J.
ORCID: 0000-0002-4299-2066
Observed ORCID: 0000-0002-4299-2066
OpenAlex ID: A5041044407
High-temperature oxidation and quenching of chromium-coated zirconium alloy ATF cladding tubes with and w/o pre-damage
2021 · M. Steinbrück, U. Stegmaier, et al. · Journal of Nuclear Materials · 86
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Synthesis and sintering of UN-UO2 fuel composites
2015 · Brian J. Jaques, Jennifer Watkins, et al. · Journal of Nuclear Materials · 73
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Non-stoichiometry in U3Si2
2016 · S.C. Middleburgh, R.W. Grimes, et al. · Journal of Nuclear Materials · 68
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UN and U3Si2 composites densified by spark plasma sintering for accident-tolerant fuels
2021 · Bowen Gong, Erofili Kardoulaki, et al. · Ceramics International · 20
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完全にセラミック製マイクロカプセルに入れた燃料:現在および次世代原子炉のための変換技術―fcm燃料の特性と製造
2011 · Lance L. Snead, Kurt A. Terrani, et al. · Transactions of the American Nuclear Society · 17
Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors
2014 · Benjamin A. Lindley, Carlo Fiorina, et al. · Progress in Nuclear Energy · 16
Promises and Challenges of Thorium Implementation for Transuranic Transmutation - 13550
2013 · Fausto Franceschini, Ben Lindley, et al. · 8
Uranium mononitride as a potential commercial LWR fuel
2012 · Peng Xu, Yan Jiang, et al. · 8
Incorporation of gadolinium and boron into Zirconium alloy: Surface alloying of immiscible materials using an intense pulsed ion beam
2010 · T.J. Renk, K. Sridharan, et al. · Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms · 8
Unveiling Fracture Mechanics of a Curved Coating/Substrate System by Combined Digital Image Correlation and Numerical Finite Element Analyses
2023 · Diana E. Burden, Timothy M. Harrell, et al. · Engineering Fracture Mechanics · 4
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Transient behavior of oxide fuels with controlled microstructure and Cr2O3 additive
2024 · Dong Zhao, Heng Ban, et al. · npj Materials Degradation · 3
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Development of LWR Fuels with Enhanced Accident Tolerance ATF Feasibility Analysis and Final Technical Report Deliverable for the Westinghouse Accident Tolerant Fuel Program (Rev. 2)
2019 · Edward Lahoda, USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5), et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 3
Incorporation of Integral Fuel Burnable Absorbers Boron and Gadolinium into Zirconium-Alloy Fuel Clad Material
2004 · K. Sridharan, T.J. Renk, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 3
Mobile soil washing system
1994 · J. D. Sachse, Armin Dietrich, et al. · atw - International Journal for Nuclear Power · 3
Helium Recovery Using Semipermeable Membranes
1983 · F. E. MARTIN, T. S. SNYDER, et al. · ACS symposium series · 3
Incorporating ATF and advanced features in the robust fuel assembly (RFA) design
2019 · Michael E. Conner, Zeses Karoutas, et al. · Nuclear Espana (1996) · 2
Westinghouse Accident Tolerant Fuel Program
2013 · E.J. Lahoda, Sumit Ray, et al. · Transactions of the American Nuclear Society · 2
A Novel Fuel/reactor Cycle to Implement the 300 Years Nuclear Waste Policy Approach - 12377
2012 · Carelli, Fausto Franceschini, et al. · 2
Fusion Power Conversion and Isotope Separation System Analysis for an Athena-Like IFE Pilot Plant
2026 · Christina Caulkins, Abdullahi Mada, et al. · Fusion Science & Technology · 1
Phase Equilibria and Thermochemistry of Advanced Fuels: Modeling Burnup Behavior (Final Report)
2020 · Univ. of South Carolina, Columbia, SC (United States), Theodore Besmann, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
Advanced Power Ultra-Uprates of Existing Plants (APPU) Final Scientific/Technical Report
2006 · Pablo Rubiolo, USDOE - Office of Nuclear Energy, Science and Technology (NE), et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
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U.S. Bureau of Mines Final Report : Midnite Mine Water Treatment Studies
1996 · L. E. Schultze, David N. Nilsen, et al. · 1
Nitrate destruction by a plasma torch
1988 · D.E. Falk, E.J. Lahoda, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
Failure processes of a gradient 2D-braided SiC-based nuclear-fuel cladding material at room temperature and 1200°C: an in situ X-ray tomography study
2026 · Guanjie Yuan, Qiance Zhang, et al. · Composites Part B Engineering
Effects of outer coating thickness on the failure strength of a SiC-based nuclear-fuel cladding up to 1200°C
2026 · Guanjie Yuan, Qiance Zhang, et al. · Materials & Design
Works count: 35
Citation count: 334
H-index: 8
I10-index: 6
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