Search Results - "Silva, Chinthaka M"

Silicon Carbide Oxidation in Steam up to 2 MPa by Terrani, Kurt A., Pint, Bruce A., Parish, Chad M., Silva, Chinthaka M., Snead, Lance L., Katoh, Yutai

“…Growth and microstructure of a protective or nonprotective SiO2 scale and the subsequent volatilization of scale formed on high‐purity chemical vapor deposited…”
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High temperature steam oxidation of SiC coating layer of TRISO fuel particles by Terrani, Kurt A., Silva, Chinthaka M.

“…High-temperature oxidation behavior of SiC coating layer of TRISO fuel particles in 1500–1700°C steam at 1atm has been examined inside a zirconia furnace. The…”
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Radiation-Induced Changes in Quartz, A Mineral Analog of Nuclear Power Plant Concrete Aggregates by Silva, Chinthaka M, Rosseel, Thomas M, Kirkegaard, Marie C

“…Quartz single-crystal samples consisting of α-quartz crystal structure were neutron irradiated to fluences of 5 × 1018, 4 × 1019, and 2 × 1020 n/cm2 (E > 0.1…”
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Investigation of mechanical and microstructural properties of Zircaloy-4 under different experimental conditions by Silva, Chinthaka M., Leonard, Keith J., Van Abel, Eric, Geringer, J. Wilna, Bryan, Chris D.

“…Two types of Zircaloy-4 (alpha-annealed and beta-quenched) were investigated in their different forms. It was found that mechanical properties of Zircaloy-4…”
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Dynamic substrate reactions during room temperature heavy ion irradiation of CoCrCuFeNi high entropy alloy thin films by Lach, Timothy G., Silva, Chinthaka M., Zhou, Yufan, Boldman, Walker L., Rack, Philip D., Weber, William J., Zhang, Yanwen

“…High entropy alloys (HEAs) are promising materials for various applications including nuclear reactor environments. Thus, understanding their behavior under…”
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Fabrication of yttrium hydride for high-temperature moderator application by Hu, Xunxiang, Schappel, Danny, Silva, Chinthaka M., Terrani, Kurt A.

“…Given the superior thermal stability and highly attainable hydrogen density, yttrium hydride is an excellent high-temperature moderator material in advanced…”
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Radiation-Induced Changes in Single Crystal Calcite and Dolomite: Mineral Analogues of Light Water Reactor, Nuclear Power Plant Concrete Aggregates by Silva, Chinthaka M, Rosseel, Thomas M, Holliday, Kiel S

“…Two analogues of aggregates (calcite and dolomite) found in nuclear power plant (NPP) concrete have been neutron irradiated to fluences up to 2 × 1020 n/cm2 at…”
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An evaluation of tri-valent oxide (Cr2O3) as a grain enlarging dopant for UO2 nuclear fuels fabricated under reducing environment by Silva, Chinthaka M., Hunt, Rodney D., Holliday, Kiel S.

“…A study was performed to evaluate the microstructure and crystallography of nominally 500–2000 Cr2O3-doped UO2 fabricated in a temperature range of 1150–1750°C…”
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Crystallographic Study of Product Phases of Carbothermic Reduction and Nitridation of Hafnium Dioxide by Silva, Chinthaka M., Kondrat, Kyle J., Holliday, Kiel S., McCormack, Scott J.

“…Details of the carbothermic reduction/nitridation to synthesize hafnium nitride (HfN) and hafnium carbide (HfC) are scarce in the literature. Therefore, this…”
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Brittle nature and the related effects of zirconium hydrides in Zircaloy-4 by Silva, Chinthaka M., Ibrahim, Fadilah, Lindquist, Elizabeth G., McMurray, Jake W., Bryan, Chris D.

“…The use of zirconium alloys such as Zircaloy-4 in nuclear reactors is limited by brittle hydride formation, for example in harsh reactor operating conditions…”
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Evaluation of sintering effects on SiC-incorporated UO2 kernels under Ar and Ar–4%H2 environments by Silva, Chinthaka M., Lindemer, Terrence B., Hunt, Rodney D., Collins, Jack L., Terrani, Kurt A., Snead, Lance L.

“…Silicon carbide (SiC) is suggested as an oxygen getter in UO2 kernels used for tristructural isotropic (TRISO) particle fuels and to prevent kernel migration…”
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Effects of low-temperature neutron irradiation on the microstructure and tensile properties of duplex 2304 stainless steel and its electron-beam welds by Silva, Chinthaka M., Leonard, Keith J., Garrison, Lauren M., Bryan, Chris D.

“…A lean duplex stainless steel material (2304-grade) in its base metal and electron beam (e-beam) welded conditions were studied microstructurally and…”
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Processing and microstructure of a Cu-Al-Fe-Mn alloy via droplet-on-demand additive manufacturing by Traxel, Kellen D., Elton, Eric S., Petersen, Amelia M., Silva, Chinthaka M., Perron, Aurélien, Jeffries, Jason R., Pascall, Andrew J.

“…Control over the microstructure and properties of alloys produced via additive manufacturing (AM) is a key barrier that limits widespread industrial adoption…”
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Unconventional Pathways to Carbide Phase Synthesis via Thermal Decomposition of UI4(1,4-dioxane)2 by Ferrier, Maryline G., Childs, Bradley C., Silva, Chinthaka M., Greenough, Michelle M., Moore, Emily E., Swift, Andrew J., Di Pietro, Silvina A., Martin, Aiden A., Jeffries, Jason R., Holliday, Kiel S.

“…UI4(1,4-dioxane)2 was subjected to laser-based heatinga method that enables localized, fast heating (T > 2000 °C) and rapid cooling under controlled…”
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Laser-Induced Thermal Decomposition of Uranium Coordination Compounds with Non-oxidic Ligands to Produce Nitride and Carbide Materials by Ferrier, Maryline G., Childs, Bradley C., Silva, Chinthaka M., Greenough, Michelle M., Moore, Emily E., Erickson, Karla A., Monreal, Marisa J., Colla, Christopher A., Marple, Maxwell A. T., Winston, Logan D., Burks, Janae N., Martin, Aiden A., Jeffries, Jason R., Holliday, Kiel S.

“…The production of ceramics from uranium coordination compounds can be achieved through thermal processing if an excess amount of the desired atoms (i.e., C or…”
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Impact of Low-Temperature Neutron Irradiation on Tensile Behavior of Base Metal and Electron-Beam Welded 316L Stainless Steel by Silva, Chinthaka M., Leonard, Keith J., Garrison, Lauren M., Bryan, Chris D., Holliday, Kiel S.

“…A study of 316L type stainless steel in its base metal and electron-beam (e-beam) welded conditions was performed to observe the effects of low-temperature…”
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Detection and analysis of particles with failed SiC in AGR-1 fuel compacts by Hunn, John D., Baldwin, Charles A., Gerczak, Tyler J., Montgomery, Fred C., Morris, Robert N., Silva, Chinthaka M., Demkowicz, Paul A., Harp, Jason M., Ploger, Scott A.

“…•Cesium release was used to detect SiC failure in HTGR fuel.•Tristructural-isotropic particles with SiC failure were isolated by gamma screening.•SiC failure…”
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Microstructure and tensile properties of droplet-on-demand additively manufactured AlSi7Mg by Traxel, Kellen D., Wilson-Heid, Alexander E., N. Watkins, Nicholas, M. Silva, Chinthaka, Jeffries, Jason R., J. Pascall, Andrew

“…A key barrier to industrial implementation of droplet-on-demand liquid metal jetting is the limited knowledge of process-properties relationships for printed…”
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Irradiation performance of AGR-1 high temperature reactor fuel by Demkowicz, Paul A., Hunn, John D., Ploger, Scott A., Morris, Robert N., Baldwin, Charles A., Harp, Jason M., Winston, Philip L., Gerczak, Tyler J., van Rooyen, Isabella J., Montgomery, Fred C., Silva, Chinthaka M.

“…•Post-irradiation examination was performed on AGR-1 coated particle fuel.•Cesium release from the particles was very low in the absence of failed SiC…”
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Synthesis of Phase-Pure U2N3 Microspheres and Its Decomposition into UN by Silva, Chinthaka M, Hunt, Rodney D, Snead, Lance L, Terrani, Kurt A

“…Uranium mononitride (UN) is important as a nuclear fuel. Fabrication of UN in its microspherical form also has its own merits since the advent of the concept…”
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