HR job title
- Professor
- Contact Info
- 1 979 862 1745
Mcdeavitt, Sean Professor
Positions
- Professor, Nuclear Engineering, College of Engineering
- Director, Nuclear Engineering & Science Center, Texas A&M Engineering Experiment Station (TEES)
- Director, Nuclear Power Institute, Texas A&M Engineering Experiment Station (TEES)
- Faculty Affiliate, Energy Institute, Texas A&M Engineering Experiment Station (TEES)
Research Areas
- Overview
- Publications
- Research
- Teaching
- Works By Students
- Background
- Contact
- Other
- View All
Overview
Publications
selected publications
-
academic article
-
Weiss, A. G., Aranguren, B., Butt, M. I., Tsvetkov, P. V., Kimber, M. L., & McDeavitt, S. M.
(2023).
A Data-driven approach to predicting neutron penetration through media. Annals of Nuclear Energy.
192, 109953-109953.
-
Weiss, A. G., V. Tsvetkov, P., Hearne, J., Kimber, M. L., Wootan, D. W., & McDeavitt, S. M.
(2023).
A sensitivity analysis to predict the neutronics behavior of samples irradiated in the VTR rabbit system. Annals of Nuclear Energy.
185, 109708-109708.
-
McDeavitt, S. M., Wootan, D., Kimber, M., Kirkland, K. V., Ortega, L. H., Perez-Nunez, D., ... Woolstenhulme, N. E.
(2023).
Concept Descriptions for the VTR Rabbit System and Driver Fuel Test Assemblies. 197(11), 2840-2852.
-
Badry, F., Singh, M., Ortega, L. H., Mcdeavitt, S. M., & Ahmed, K.
(2022).
An experimentally validated mesoscale model for the effective thermal conductivity of U-Zr fuels. Journal of Nuclear Materials.
574, 154203-154203.
-
Ortega, L. H., Yee, K. L., Perez-Nunez, D., McDeavitt, S. M., Steinman, C., Schultz, R. R., Dunzik-Gougar, M. L., & Spencer, B. W.
(2022).
Thermal-shock experiments for separate-effects validation of UO2 fuel fracture models. 572, 154035-154035.
-
Ortega, L. H., Livingston, R. J., & McDeavitt, S. M.
(2022).
Improved leach resistance of FLiBe by conversion to a substituted fluorapatite. Nuclear Materials and Energy.
32, 101223-101223.
-
McClenny, L. D., Butt, M. I., Abdoelatef, M. G., Pate, M. J., Yee, K. L., Harikrishnan, R., ... Ahmed, K.
(2022).
Experimentally validated multiphysics modeling of fracture induced by thermal shocks in sintered UO2 pellets. Journal of Nuclear Materials.
565, 153719-153719.
-
Weiss, A. G., Butt, M. I., Tsvetkov, P. V., Kimber, M. L., & McDeavitt, S. M.
(2021).
A novel method for the design and selection of neutron-attenuating media. Annals of Nuclear Energy.
160, 108368-108368.
-
Cordes, N., Sudderth, L., Butt, M., Jewell, J., Meyer, M., & McDeavitt, S.
(2021).
Laboratory-based 3D X-ray microscopy of unirradiated U-10Zr fuel. Microscopy and Microanalysis.
27(S1), 1938-1939.
-
Einkauf, J. D., Ortega, L. H., McDeavitt, S. M., & Burns, J. D.
(2020).
Ion-Exchange Kinetics of Alpha-Zirconium Phosphate Nanoplatelets for Application in Targeted Alpha Therapy. Solvent Extraction and Ion Exchange.
38(6), 612-628.
-
Ortega, L. H., Blamer, B., Stern, K. M., Vollmer, J., & McDeavitt, S. M.
(2020).
Thermal conductivity of uranium metal and uranium-zirconium alloys fabricated via powder metallurgy. Journal of Nuclear Materials.
531, 151982-151982.
-
Badry, F., Brito, R., Abdoelatef, M. G., McDeavitt, S., & Ahmed, K.
(2019).
An Experimentally Validated Mesoscale Model of Thermal Conductivity of a UO2 and BeO Composite Nuclear Fuel. JOM.
71(12), 4829-4838.
-
Evans, J. A., Anderson, S. A., Faierson, E. J., Perez-Nunez, D., & McDeavitt, S. M.
(2019).
Anisotropic Radiation-Induced Changes in Type 316L Stainless Steel Rods Built by Laser Additive Manufacturing. Nuclear Technology.
205(4), 563-581.
-
Sudderth, L., Perez-Nunez, D., Keiser, D., & McDeavitt, S.
(2018).
Fabrication of ZrN Barrier Coatings for U-Mo Microspheres Via Fluidized Bed Chemical Vapor Deposition Using a Metalorganic Precursor. 202(1), 81-93.
-
Mi, H., Mikael, S., Swinnich, E., Allen, T., Sridharan, K., Butt, D. P., ... Ma, Z.
(2018).
Detecting the Oxidation of Zircaloy Claddings by Infrared Interference. Nano.
13(2), 1850015-1850015.
-
Garcia, C. B., Brito, R. A., Ortega, L. H., Malone, J. P., & McDeavitt, S. M.
(2017).
Manufacture of a UO2-Based Nuclear Fuel with Improved Thermal Conductivity with the Addition of BeO. Metallurgical and Materials Transactions E.
4(2-4), 70-76.
-
Irukuvarghula, S., Blamer, B., Ahn, S., Vogel, S. C., Losko, A. S., & McDeavitt, S. M.
(2017).
Texture evolution during annealing of hot extruded U-10wt%Zr alloy by in situ neutron diffraction. Journal of Nuclear Materials.
497, 10-15.
-
Arrieta, M. Y., Keiser, D., Perez-Nunez, D., & McDeavitt, S. M.
(2017).
Fluidized Bed Chemical Vapor Deposition of Zirconium Nitride Films. 199(2), 219-226.
-
Agnolet, G., Baker, W., Barker, D., Beck, R., Carroll, T. J., Cesar, J., ... Yadavalli, S. A.
(2017).
Background studies for the MINER Coherent Neutrino Scattering reactor experiment. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment.
853, 53-60.
-
Spencer, K. Y., Sudderth, L., Brito, R. A., Evans, J. A., Hart, C. S., Hu, A., ... McDeavitt, S. M.
(2016).
Sensitivity study for accident tolerant fuels: Property comparisons and behavior simulations in a simplified PWR to enable ATF development and design. Nuclear Engineering and Design.
309, 197-212.
-
Ahn, S., Irukuvarghula, S., & McDeavitt, S. M.
(2016).
Microstructure of -U and -UZr2 phase uranium-zirconium alloys irradiated with 140-keV He+ ion-beam. 681, 6-11.
-
Irukuvarghula, S., Ahn, S., & McDeavitt, S. M.
(2016).
Decomposition of the phase in as-cast and quenched U-Zr alloys. 473(Intermetallics182010), 206-217.
-
Ortega, L. H., Blamer, B. J., Evans, J. A., & McDeavitt, S. M.
(2016).
Development of an accident-tolerant fuel composite from uranium mononitride (UN) and uranium sesquisilicide (U3 Si2) with increased uranium loading. 471, 116-121.
-
Ahn, S., Irukuvarghula, S., & McDeavitt, S. M.
(2014).
Thermophysical investigations of the uranium-zirconium alloy system. Journal of Alloys and Compounds.
611, 355-362.
-
Humrickhouse-Helmreich, C. J., Corbin, R., & McDeavitt, S. M.
(2014).
Measurement of thermal diffusivity of depleted uranium metal microspheres. Journal of Nuclear Materials.
446(1-3), 100-105.
-
Kelley, R., & McDeavitt, S.
(2013).
Design of an integrated system to recycle Zircaloy cladding using a hydridemillingdehydride process. Nuclear Engineering and Design.
263, 47-58.
-
Jahangiri, N., Raraz, A. G., Indacochea, J. E., & McDeavitt, S. M.
(2013).
Assessing Corrosion of UNS S30403 Stainless Steel for Applications in Nuclear Waste Reprocessing Systems. Corrosion: journal of science and engineering.
69(6), 568-579.
-
McKeown, J. T., Irukuvarghula, S., Ahn, S., Wall, M. A., Hsiung, L. L., McDeavitt, S., & Turchi, P.
(2013).
Coexistence of the and phases in an as-cast uranium-rich UZr alloy. Journal of Nuclear Materials.
436(1-3), 100-104.
-
Dasari, S., Jahangiri, N., Raraz, A. G., Indacochea, J. E., & McDeavitt, S. M.
(2013).
Corrosion Behavior of Type 304L Stainless Steel in UREX plus Nitric Acid Solutions Using Immersion and Rotating Cage Techniques. 69(5), 448-461.
-
Taleyarkhan, R. P., Lapinskas, J., Archambault, B., Webster, J. A., Grimes, T. F., Hagen, A., ... Charlton, W.
(2013).
Real-time monitoring of actinides in chemical nuclear fuel reprocessing plants. 91(4), 688-702.
-
Jahangiri, N., Raraz, A. G., Indacochea, J. E., & McDeavitt, S. M.
(2012).
EIS monitoring of electrochemical behavior of 304L stainless steel during immersion in a diluted nitric acid solution. Journal of Corrosion Science and Engineering.
15, 1-19.
-
Archambault, B. C., Lapinskas, J. R., Wang, J., Webster, J. A., McDeavitt, S., & Taleyarkhan, R. P.
(2011).
Ascertaining directionality information from incident nuclear radiation. Nuclear Engineering and Design.
241(10), 4299-4305.
-
McDeavitt, S. M., Ragusa, J., Revankar, S. T., Solomon, A. A., & Malone, J.
(2011).
A high-conductivity oxide fuel concept. NUCLEAR ENGINEERING INTERNATIONAL.
56(682), 40-42.
-
Parkison, A. J., & Mcdeavitt, S. M.
(2011).
Hydride Formation Process for the Powder Metallurgical Recycle of Zircaloy from Used Nuclear Fuel. 42A(1), 192-201.
-
Ortega, L. H., Kaminski, M. D., & McDeavitt, S. M.
(2010).
Pollucite and feldspar formation in sintered bentonite for nuclear waste immobilization. Applied Clay Science.
50(4), 594-599.
-
Goddard, B., Charlton, W. S., & McDeavitt, S. M.
(2010).
Development of a real-time detection strategy for process monitoring during nuclear fuel reprocessing using the UREX+3a method. Nuclear Engineering and Design.
240(11), 3904-3909.
-
Fu, E. G., Carter, J., Martin, M., Xie, G., Zhang, X., Wang, Y. Q., ... Shao, L.
(2010).
Ar-ion-milling-induced structural changes of Cu50Zr45Ti5 metallic glass. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms.
268(6), 545-549.
-
Totemeier, A. R., & McDeavitt, S. M.
(2009).
Powder metallurgical fabrication of zirconium matrix cermet nuclear fuels. 44(20), 5494-5500.
-
Carter, J., Fu, E. G., Martin, M., Xie, G., Zhang, X., Wang, Y. Q., ... Shao, L.
(2009).
Ion irradiation induced nanocrystal formation in amorphous Zr55Cu30Al10Ni5 alloy. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms.
267(17), 2827-2831.
-
Goddard, B., Charlton, W. S., & McDeavitt, S. M.
(2009).
Real-time detection of UREX + 3a extraction streams for materials accountancy. Journal of Nuclear Materials Management.
38(1), 34-39.
-
Lapinskas, J. R., Zielinski, S. M., Webster, J. A., Taleyarkhan, R. P., McDeavitt, S. M., & Xu, Y.
(2009).
TENSION METASTABLE FLUID DETECTION SYSTEMS FOR SPECIAL NUCLEAR MATERIAL DETECTION AND MONITORING. 4, 607-614.
-
Carter, J., Fu, E., McDeavitt, S., Zhang, X., Xie, G., & Shao, L.
(2007).
Characterization of high strength alloy formed by ion irradiation of metallic glasses. 561-565(PART 3), 1737-+.
-
McDeavitt, S. M., Parkison, A., Totemeier, A. R., & Wegener, J. J.
(2007).
Fabrication of cermet nuclear fuels designed for the transmutation of transuranic isotopes. 561-565(PART 3), 1733-1736.
-
McDeavitt, S. M., Xu, Y., Downar, T. J., & Solomon, A. A.
(2007).
Zirconium Matrix Cermet for a Mixed Uranium-Thorium Oxide Fuel in an SBWR. 157(1), 37-52.
-
Indacochea, J. E., Polar, A., & McDeavitt, S. M.
(2005).
Challenges in joining advanced ceramic materials: Interface formation of ceramic/metal high-temperature brazes. 502, 7-12.
-
Hanrahan, R. J., Boehlert, C., & McDeavitt, S.
(2003).
Plutonium: A reactive nuclear metal. JOM.
55(9), 12-12.
-
Wade, D. C., Doctor, R., Leibowitz, L., Mendelsohn, M. H., McDeavitt, S., Runge, J., ... Tsvetkova, G.
(2003).
ICONE11-36576 STAR-H2 : A 400 MWTH LEAD-COOLED, LONG REFUELING INTERVAL REACTOR FOR HYDROGEN PRODUCTION. The Proceedings of the International Conference on Nuclear Engineering (ICONE).
2003(0), 203-203.
-
McDeavitt, S. M., Billings, G. W., & Indacochea, J. E.
(2002).
Interfacial reactions of zirconium and zirconium-alloy liquid metals with beryllia at elevated temperatures. 37(17), 3765-3776.
-
McDeavitt, S. M., Billings, G. W., & Indacochea, J. E.
(2002).
High temperature interaction behavior at liquid metal-ceramic interfaces. Journal of Materials Engineering and Performance.
11(4), 392-401.
-
Indacochea, J. E., McDeavitt, S., & Billings, G. W.
(2001).
Interface Interactions of Dissimilar Materials at Elevated Temperatures. 3(11), 895-901.
-
Abraham, D. P., Richardson, J. W., & McDeavitt, S. M.
(2001).
Microscopy and neutron diffraction study of a zirconium-8 wt% stainless steel alloy. 36(21), 5143-5154.
-
Laidler, J. J., Burris, L., Collins, E. D., Duguid, J., Henry, R. N., Hill, J., ... Willit, J. L.
(2001).
Chemical partitioning technologies for an ATW system. 38(1-2), 65-79.
-
Leibowitz, L., McDeavitt, S. M., Graczyk, D. G., & Smith, F. P.
(2000).
Removal of Lithium Antimonide from Radioactive Glove Box. Journal of Hazardous, Toxic and Radioactive Waste.
4(4), 163-164.
-
McDeavitt, S. M.
(2000).
Uranium processing for the nuclear fuel cycle. JOM.
52(9), 11-11.
-
Benedict, R. W., Johnson, S. G., Keiser, D. D., OHolleran, T. P., Goff, K. M., McDeavitt, S., & Ebert, W.
(2000).
Waste forms from the electrometallurgical treatment of DOE spent fuel: Production and general characteristics. AIP Conference Proceedings.
532(1), 86-88.
-
Keiser, D. D., Abraham, D. P., Sinkler, W., Richardson, J. W., & McDeavitt, S. M.
(2000).
Actinide distribution in a stainless steel-15 wt% zirconium high-level nuclear waste form. 279(2-3), 234-244.
-
Abraham, D. P., Simpson, L. J., Devries, M. J., & McDeavitt, S. M.
(1999).
Corrosion testing of stainless steel-zirconium metal waste forms. MRS Online Proceedings Library.
556, 945-952.
-
McDeavitt, S. M., Abraham, D. P., & Park, J. Y.
(1998).
Evaluation of stainless steel zirconium alloys as high-level nuclear waste forms. 257(1), 21-34.
-
Abraham, D. P., Richardson, J. W., & McDeavitt, S. M.
(1997).
Laves inter-metallics in stainless steel-zirconium alloys. 240(1-2), 658-664.
-
Abraham, D. P., Richardson, J. W., & McDeavitt, S. M.
(1997).
Formation of the Fe23Zr6 phase in an Fe-Zr alloy. 37(2), 239-244.
-
Ackerman, J. P., Chow, L., McDeavitt, S. M., Pereira, C., & Woodman, R. H.
(1997).
Isolating wastes in the electrometallurgical treatment of spent nuclear fuel. 49(7), 26-28.
-
McDeavitt, S. M., Abraham, D. P., Park, J. Y., & Keiser, D. D.
(1997).
Stainless steel-zirconium waste forms from the treatment of spent nuclear fuel. 49(7), 29-32.
-
Abraham, D. P., McDeavitt, S. M., & Park, J.
(1996).
Microstructure and phase identification in type 304 stainless steel-zirconium alloys. 27(8), 2151-2159.
-
McDeavitt, S. M., & Solomon, A. A.
(1996).
Hot-isostatic pressing of U-1OZr by a coupled grain boundary diffusion and creep cavitation mechanism. 228(2), 184-200.
-
Solomon, A. A., & McDeavitt, S. M.
(1992).
Preparation of uranium-zirconium alloy nuclear fuel elements by PM. Metal Powder Report.
47(11), 55-55.
-
Weiss, A. G., Aranguren, B., Butt, M. I., Tsvetkov, P. V., Kimber, M. L., & McDeavitt, S. M.
(2023).
A Data-driven approach to predicting neutron penetration through media. Annals of Nuclear Energy.
192, 109953-109953.
-
chapter
-
Indacochea, J. E., Billings, G. W., & McDeavitt, S. M.
(2006).
Interfacial Reactions Between Metals and Ceramics at Elevated Temperatures. Ceramic Transactions.
Characterization & Control of Interfaces for High Quality Advanced Materials.
(pp. 103-111).
Wiley.
-
Indacochea, J. E., Billings, G. W., & McDeavitt, S. M.
(2006).
Interfacial Reactions Between Metals and Ceramics at Elevated Temperatures. Ceramic Transactions.
Characterization & Control of Interfaces for High Quality Advanced Materials.
(pp. 103-111).
Wiley.
-
conference paper
-
Weiss, A., Kirkland, K., Mcdeavitt, S., Wootan, D., & Kimber, M.
(2022).
Rabbit Delivery System Design and Thermal Analysis for a Versatile Test Reactor Environment
-
McDeavitt, S., Kimber, M., Kirkland, K., Ortega, L., Perez-Nunez, D., Tsvetkov, P., ... Weiss, A.
(2020).
Design and Demonstration of a Rabbit Experiment System for the Versatile Test Reactor. 1408-1411.
-
Porter, D., Jewell, J., Ahmed, K., Sudderth, L., Meyer, M., Butt, M., & McDeavitt, S.
(2020).
Preparation of U-10Zr Alloys for Irradiation Testing in the Advanced Test Reactor to Enable MARMOT Assessment and Validation. 586-588.
-
Spencer, B. W., Woolstenhulme, N. E., Emerson, L. A., Yeh, J., Imholte, D., Hill, C., ... Ban, H.
(2019).
Separate-Effects Validation Experiments for Models of Fracture in Ceramic Nuclear Fuel
-
Hearne, J., McDeavitt, S., Scherr, J., Tsvetkov, P., & Wootan, D.
(2019).
Analysis of the VTR In-Core Environment with the Rabbit Delivery System Enabling Encapsulated Irradiations. 1427-1430.
-
Wachs, D., Weaver, K., Farmer, M., McDuffee, J., Sabharwal, P., Malloy, S., ... McDeavitt, S.
(2018).
Development of experimental capabilities for fuels and materials testing in the versatile test reactor. Transactions of the American Nuclear Society.
507-508.
-
Patel, V. M., Loo, S. M., Jaques, B., Hurley, M., McDeavitt, S. M., & Butt, D. P.
(2016).
Monitoring and predicting stress corrosion cracking of long term spent nuclear fuel storage. NACE - International Corrosion Conference Series.
4159-4171.
-
Sames, W. J., Dehoff, R. R., & McDeavitt, S. M.
(2014).
3D printing high temperature materials for nuclear industry applications. 100-101.
-
Ortega, L. H., Evans, J., & McDeavitt, S. M.
(2014).
Development of a high density uranium nitride-uranium silicide composite accident tolerant fuel. Transactions of the American Nuclear Society.
999-1000.
-
Jahangiri, N., Raraz, A. G., Indacochea, J. E., & McDeavitt, S.
(2013).
Corrosion Behavior of AISI 304L Stainless Steel for Applications in Nuclear Waste Reprocessing Equipment. Ceramic Transactions.
257-265.
-
McKeown, J. T., Ahn, S., Barnhart, B., Irukuvarghula, S., Wall, M., Hsiung, L. L., McDeavitt, S., & Turchi, P.
(2013).
Alloy development for advanced inert-matrix nuclear fuels. Transactions of the American Nuclear Society.
399-400.
-
Ahn, S., & McDeavitt, S. M.
(2013).
An investigation of U-Zr alloy phase diagram using in-situ heating electron diffractometry. Transactions of the American Nuclear Society.
608-611.
-
McDeavitt, S. M., Garcia, C., Ragusa, J. C., Smith, J., & Malone, J.
(2013).
Behavior assessments for UO
2 -BEO enhanced conductivity fuel in a PWR. 1161-1166.
-
Irukuvarghula, S., & McDeavitt, S. M.
(2013).
Formation mechanism of delta phase in the as-cast U-10wt%Zr alloy. Transactions of the American Nuclear Society.
612-615.
-
Ahn, S., & McDeavitt, S. M.
(2012).
Transformation enthalpies of uranium-zirconium alloy system. Transactions of the American Nuclear Society.
239-241.
-
Tsvetkov, P., Chirayath, S., Ragusa, J., McDeavitt, S., Gariazzo, C., Johns, J., ... Rochau, G. E.
(2011).
High temperature super-critical CO
2 -cooled integrated multi-modular thermal reactor. Transactions of the American Nuclear Society. 1117-1119.
-
Parkison, A. J., & McDeavitt, S. M.
(2011).
Hydride formation process development for the powder metallurgical recycle of zircaloy. Transactions of the American Nuclear Society.
99-100.
-
McDeavitt, S. M., Naramore, M., Ragusa, J., Revankar, S. T., Solomon, A. A., & Malone, J.
(2010).
Evaluation of high thermal conductivity oxide nuclear fuel concept containing beryllium. 621-625.
-
McDeavitt, S. M., Naramore, M., Miller, R., Ragusa, J. C., Revankar, S. T., Solomon, A. A., & Malone, J.
(2010).
Introducing a high thermal conductivity UO
2 -BeO nuclear fuel concept. Transactions of the American Nuclear Society. 273-274.
-
Ragusa, J. C., McDeavitt, S. M., & Naramore, M.
(2010).
Neutronic evaluation of high thermal conductivity UO2-BeO fuel. Transactions of the American Nuclear Society.
761-762.
-
Parkison, A. J., & McDeavitt, S. M.
(2010).
Potential zircaloy recycle method via hydride formation. Transactions of the American Nuclear Society.
243-244.
-
Hausaman, J. S., Garnetti, D. J., & McDeavitt, S. M.
(2010).
Powder metallurgy of alpha phase uranium alloys for TRU burning fast reactors. Transactions of the American Nuclear Society.
294-295.
-
Helmreich, G. W., Garnetti, D. J., & McDeavitt, S. M.
(2010).
Sintering -phase uranium and its alloys. Transactions of the American Nuclear Society.
296-297.
-
Creasy, J., & McDeavitt, S.
(2010).
Thermal properties of uranium molybdenum alloys at various stages of phase decomposition. Transactions of the American Nuclear Society.
291.
-
Dasari, S. K., Raraz, A. G., Indacochea, J. E., & McDeavitt, S. M.
(2010).
UREX+ 304L stainless steel centrifugal contactor corrosion due to hydrodynamic effects. NACE - International Corrosion Conference Series.
-
Jahangiri, N., Raraz, A. G., Indacochea, J. E., & McDeavitt, S. M.
(2010).
UREX+ centrifugal contactor corrosion in HNO
3 -HF aqueous solutions. NACE - International Corrosion Conference Series.
-
Helmreich, G. W., Sames, W. J., Garnetti, D. J., & McDeavitt, S. M.
(2010).
Uranium powder production using a hydride-dehydride process. Transactions of the American Nuclear Society.
880-881.
-
Lapinskas, J. R., Zielinski, S. M., Webster, J. A., Taleyarkhan, R. P., McDeavitt, S. M., & Xu, Y.
(2010).
Tension metastable fluid detection systems for special nuclear material detection and monitoring. Nuclear Engineering and Design.
2866-2871.
-
Goddard, B., Charlton, W. S., & McDeavitt, S. M.
(2009).
Real-time detection of UREX+3a extraction streams for process monitoring applications. Transactions of the American Nuclear Society.
155.
-
Mews, K. W., & McDeavitt, S.
(2009).
Sample preparation of U-Zr fuel alloys for TEM analysis. Transactions of the American Nuclear Society.
283-284.
-
Tsvetkov, P., Vierow, K., Peddicord, K., Ragusa, J., McDeavitt, S., Poston, J., Shao, L., & Willems, G.
(2008).
Autonomous multi-purpose floating power system with a compact static pebble bed reactor. 1571-1576.
-
Vierow, K., Best, F., Ford, J., Hassan, Y., McDeavitt, S., Ragusa, J., ... Tsvetkov, P.
(2008).
TAMU Nuclear safety curriculum development for a 21stcentury workforce. Transactions of the American Nuclear Society.
771-772.
-
Totemeier, A. R., & McDeavitt, S. M.
(2007).
A zirconium cermet for transuranic isotope storage and burning. 563-567.
-
Mews, P. A., & McDeavitt, S. M.
(2007).
Evaluation of zirconium-iron-rhenium alloy surrogates for a technetium alloy waste form. Transactions of the American Nuclear Society.
79-80.
-
Ortega, L. H., & McDeavitt, S. M.
(2007).
Precursors for the immobilization of radioactive cesium and strontium from spent nuclear fuel. 1385-1388.
-
McDeavitt, S. M., Downar, T. J., & Solomon, A. A.
(2005).
Cermet fuels for advanced fuel cycles and transmutation. 2987-2994.
-
Fielding, R., Meyer, M., Prabhakaran, R., Milled, T., & McDeavitt, S.
(2005).
Gas fast reactor fuel development. Transactions of the American Nuclear Society.
775-776.
-
McDeavitt, S. M., Kraemer, D. T., Parkinson, A., Totemeier, A. R., & Wegener, J. J.
(2005).
Zirconium matrix cermet storage form and transmutation fuel for transuranics. Transactions of the American Nuclear Society.
743-744.
-
Totemeier, A., Jevremovic, T., & McDeavitt, S.
(2004).
Shielding requirements for mission to mars nuclear engines. Transactions of the American Nuclear Society.
517-519.
-
Runge, J. M., Leibowitz, L., Barnes, L. A., Raraz, A. G., & McDeavitt, S. M.
(2003).
Performance of structural materials in lead-based reactor coolants at temperatures up to 800C. 2093-2099.
-
McDeavitt, S. M., Billings, G. W., & Indacochea, J. E.
(2003).
The role of interfaces in ceramic-metal bonding. 101-107.
-
McDeavitt, S. M., Downar, T. J., Solomon, A. A., Revankar, S. T., Hash, M. C., & Hebden, A. S.
(2002).
Thoria-Based Cermet Nuclear Fuel: Cermet Fabrication and Behavior Estimates. 59-67.
-
Downar, T. J., McDeavitt, S. M., Revankar, S. T., Solomon, A. A., & Kim, T. K.
(2002).
Thoria-Based Cermet Nuclear Fuel: Neutronics Fuel Design and Fuel Cycle Analysis. 47-57.
-
Solomon, A. A., McDeavitt, S. M., Chandramouli, V., Anthonysamy, S., Kuchibhotla, S., & Downar, T. J.
(2002).
Thoria-Based Cermet Nuclear Fuel: Sintered Microsphere Fabrication by Spray Drying. 111-118.
-
McDeavitt, S. M., Billings, G. W., & Indacochea, J. E.
(2001).
Ceramic-Metal Interface Stability. 79-88.
-
McDeavitt, S. M., Billings, G. W., & Indacochea, J. E.
(2000).
Interaction phenomena at refractory metals/ceramic interfaces. 1029-1035.
-
Keiser, D. D., Sinkler, W., Abraham, D. P., Richardson, J. W., & McDeavitt, S. M.
(2000).
The effect of actinides on the microstructural development in a metallic high-level nuclear waste form. 111-122.
-
McDeavitt, S. M.
(1999).
Synthesis and casting of a lithium-bismuth compound for an ion-replacement electrorefiner. 1139-1142.
-
Abraham, D. P., & McDeavitt, S. M.
(1998).
Influence of zirconium content on fission product distributions in stainless steel zirconium waste forms. ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY.
U677-U677.
-
Keiser, D. D., & McDeavitt, S. M.
(1998).
Phase development in As-cast, zirconium-based alloys containing type 304 stainless steel and Pu. 1373-1378.
-
McDeavitt, S. M., & Billings, G. W.
(1998).
The development of stable ceramic materials for the containment of molten zirconium and uranium alloys. 1365-1365.
-
McDeavitt, S. M., Abraham, D. P., Keiser, D. D., & Park, J. Y.
(1996).
Alloy waste forms for metal fission products and actinides isolated by spent nuclear fuel treatment. 177-189.
-
MCDEAVITT, S. M., PARK, J. Y., & ACKERMAN, J. P.
(1994).
DEFINING A METAL-BASED WASTE FORM FOR IFR PYROPROCESSING WASTES. 305-319.
-
MCDEAVITT, S. M., SMITH, J. L., MCPHEETERS, C. C., PIERCE, R. D., & POA, D. S.
(1994).
ELECTRODE MATERIALS FOR THE REDUCTION OF CAO AND LI2O FOR ACTINIDE PYROPROCESSING. 215-215.
-
MCDEAVITT, S. M., & SOLOMON, A. A.
(1992).
PREPARATION AND PERFORMANCE OF U-10ZR ALLOY NUCLEAR-FUEL USING POWDER-METALLURGY TECHNIQUES. Advances in Powder Metallurgy.
109-123.
-
Weiss, A., Kirkland, K., Mcdeavitt, S., Wootan, D., & Kimber, M.
(2022).
Rabbit Delivery System Design and Thermal Analysis for a Versatile Test Reactor Environment
-
institutional repository document
-
McClenny, L. D., Butt, M. I., Abdoelatef, M. G., Pate, M. J., Yee, K. L., Rajendran, H., ... Ahmed, K.
(2021).
Experimentally Validated Multiphysics Modeling of Fracture Induced by Thermal Shocks in Sintered UO2 Pellets
-
McClenny, L. D., Butt, M. I., Abdoelatef, M. G., Pate, M. J., Yee, K. L., Rajendran, H., ... Ahmed, K.
(2021).
Experimentally Validated Multiphysics Modeling of Fracture Induced by Thermal Shocks in Sintered UO2 Pellets
-
patent
-
Ahlfeld, C., Bowen, W., Hyde, R., Klueh, R., Mcdeavitt, S., Walter, J., & Kirkendall, S.
(2018).
Nuclear fuel and method of fabricating the same
-
Solomon, A., Kuchibhotla, H., Revankar, S., Mcdeavitt, S., & Ragusa, J.
(2016).
Ceramic-ceramic composites and process therefor, nuclear fuels formed thereby, and nuclear reactor systems and processes operated therewith
-
Ahlfeld, C., Bowen, W., Hyde, R., Klueh, R., Mcdeavitt, S., Walter, J., & Kirkendall, S.
(2018).
Nuclear fuel and method of fabricating the same
Research
principal investigator on
- Demonstration of a Methodology for Direct Validation of MARMOT Irradiation-Induced Microstructural Evolution and Physical Property Models Using U-10ZR NEUP 18-14741 awarded by United States Department of Energy - (Washington D.C., District of Columbia, United States) 2018 - 2022
- Nuclear Science Center Reactor Upgrades awarded by United States Department of Energy - (Washington D.C., District of Columbia, United States) 2014 - 2016
co-principal investigator on
investigator on
Teaching
teaching activities
- MSEN691 Research Instructor
- NUEN201 Intro To Nuc Engr I Instructor
- NUEN265 Matl Sci Nuclear Energy Instructor
- NUEN485 Directed Studies Instructor
- NUEN491 Hnr-research Instructor
- NUEN661 Nuclear Fuel Performance Instructor
- NUEN684 Professional Internship: In-ab Instructor
- NUEN684 Professional Internship:in-ab Instructor
- NUEN685 Directed Studies Instructor
- NUEN685 Directed Studies Instructor
- NUEN691 Research Instructor
- NUEN691 Research Instructor
Works By Students
chaired theses and dissertations
-
Ahn, Sangjoon (2013-07). Comprehensive Investigation of the Uranium-Zirconium Alloy System: Thermophysical Properties, Phase Characterization and Ion Implantation Effects.
-
Arrieta, Marie (2012-10). Low Temperature Chemical Vapor Deposition of Zirconium Nitride in a Fluidized Bed.
-
Barnhart, Brian A. (2013-08). Characterization of Zr-Fe-Cu Alloys for an Inert Matrix Fuel for Nuclear Energy Applications.
-
Clemens, Jeffrey Tyler (2014-05). Radiochemical Transformation of High Pressure Methane under Gamma, Electron, and Neutron Irradiation.
-
Creasy, John Thomas (2012-02). Thermal Properties of Uranium-Molybdenum Alloys: Phase Decomposition Effects of Heat Treatments.
-
Eichel, Daniel (2013-06). Atomic Diffusion in the Uranium-50wt% Zirconium Nuclear Fuel System.
-
Evans, Jordan Andrew (2017-12). Anisotropic Response of Laser Additively Manufactured Nuclear Alloys to Radiation Damage.
-
Garcia, Chad (2014-04). Sintering and Thermal Behavior of Uranium Dioxide in Beryllium Oxide Matrix.
-
Garnetti, David J. (2009-12). Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications.
-
Goddard, Braden (2009-12). Development of a Real-Time Detection Strategy for Material Accountancy and Process Monitoring During Nuclear Fuel Reprocessing Using the Urex+3A Method.
-
Hausaman, Jeffrey Stephen (2012-02). Hot Extrusion of Alpha Phase Uranium-Zirconium Alloys for TRU Burning Fast Reactors.
-
Helmreich, Grant (2010-12). Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications.
-
Hogelin, Thomas Russell (2010-12). Radioactive Flow Characterization for Real-Time Detection Systems in UREX+ Nuclear Fuel Reprocessing.
-
Humrickhouse, Carissa Joy (2012-07). Characterization of Thermal Properties of Depleted Uranium Metal Microspheres.
-
Irukuvarghula, Sandeep (2013-08). Solid State Phase Transformations in Uranium-Zirconium Alloys.
-
Kelley, Randy Dean (2010-08). Design of an Integrated System to Recycle Zircaloy Cladding Using a Hydride-Milling-Dehydride Process.
-
Kuhr, Samuel Houston (2012-10). An Electrolytic Method to Form Zirconium Hydride Phases in Zirconium Alloys with Morphologies Similar to Hydrides Formed in Used Nuclear Fuel.
-
Martinez, John Calvin (2015-05). Hydrogen Interactions in Zirconium Alloys for Nuclear Applications.
-
Mews, Kathryn Ann Wright (2013-05). Methods for Investigating Gas Bubble Formation in Uranium-Zirconium Alloys.
-
Mews, Paul Aaron (2007-12). Evaluation of zirconium-iron-rhenium alloys as surrogates for a technetium alloy waste form.
-
Ortega, Luis H. (2009-12). Sintered Bentonite Ceramics for the Immobilization of Cesium- and Strontium-Bearing Radioactive Waste.
-
Parkison, Adam J (2013-06). Separation of Zirconium from Uranium in U-Zr Alloys Using a Chlorination Process.
-
Parkison, Adam Joseph (2008-05). Hydride production in zircaloy-4 as a function of time and temperature.
-
Sames, William (2015-05). Additive Manufacturing of Inconel 718 using Electron Beam Melting: Processing, Post-Processing, & Mechanical Properties.
-
Sudderth, Laura (2015-04). Zirconium Nitride Coating Fabrication via Fluidized Bed Chemical Vapor Deposition.
-
Thompson, Chad 1984- (2012-11). A Rotating Electrode System for the Generation of Metal Alloy Microspheres.
-
Totemeier, Aaron Robert (2015-11). Helium Ion Implantation in Zirconium: Bubble Formation & Growth.
-
Wegener, Jeffrey J. (2008-12). Production of cerium oxide microsheres by an internal gelation sol-gel process.
-
Woolum, Connor (2014-12). Fabrication and Characterization of Uranium-Molybdenum-Zirconium Alloys.
Background
education and training
- Ph.D. in Nuclear Engineering, Purdue University - (West Lafayette, Indiana, United States) 1992
- M.S. in Nuclear Engineering, Purdue University - (West Lafayette, Indiana, United States) 1990
- B.S. in Nuclear Engineering, Purdue University - (West Lafayette, Indiana, United States) 1987
awards and honors
Contact
first name
- Sean
has last name
- Mcdeavitt
mailing address
-
Texas A&M University
Nuclear Engineering
3133 TAMU
College Station, TX 77843-3133
USA
Other
In the News
- mcdeavitt@tamu.edu