Search Results - "Yacout, A."

Continuous femoral nerve block enhances outcome of spinal anaesthesia in preventing perioperative cardiac complications in patients with cardiac risk by Yacout, A G, ELHoshy, H S

“…Elevated brain natriuretic peptide (BNP) is crucial to detect perioperative adverse cardiovascular events in patients with cardiac risk, even at low elevation…”
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Potential anti-proliferative activity of Salix mucronata and Triticum spelta plant extracts on liver and colorectal cancer cell lines by Ahmad, Ghada M., Abu Serie, Marwa M., Abdel-Latif, Mohamed S., Ghoneem, Tayseer, Ghareeb, Doaa A., Yacout, Galila A.

“…Cancer’s etiology is linked to oxidative stress. As a result, it's vital to find effective natural antioxidant remedies. Salix mucronata and Triticum spelta…”
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Author Correction: Potential anti-proliferative activity of Salix mucronata and Triticum spelta plant extracts on liver and colorectal cancer cell lines by Ahmad, Ghada M., Abu Serie, Marwa M., Abdel-Latif, Mohamed S., Ghoneem, Tayseer, Ghareeb, Doaa A., Yacout, Galila A.

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Migration of minor actinides and lanthanides in fast reactor metallic fuel by Kim, Yeon Soo, Hofman, G.L., Yacout, A.M.

“…Minor actinides (MA) and lanthanides (LA) migration to the cladding in fast reactor metallic fuel is a concern because of their reaction with the cladding…”
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U–Mo alloy fuel for TRU-burning advanced fast reactors by Kim, Yeon Soo, Hofman, G.L., Yacout, A.M., Kim, T.K.

“…The use of U–Mo instead of U–Zr as the base alloy fuel for transuranics (TRU)-burning advanced fast reactors is assessed in several aspects. While the…”
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Lanthanides migration and immobilization in U–Zr nuclear fuels by Bozzolo, G., Hofman, G.L., Yacout, A.M., Mosca, H.O.

“…Redistribution of lanthanides fission products during irradiation and migration to the surface of U–Zr based metallic fuels is a concern due to their…”
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Aluminum cladding oxide growth prediction for high flux research reactors by Kim, Yeon Soo, Chae, H.T., Van den Berghe, S., Leenaers, A., Kuzminov, V., Yacout, A.M.

“…Aluminum cladding oxidation of research-reactor fuel elements at high power conditions has a disadvantageous effect on fuel performance due to the lower…”
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Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe by Ye, B., Bhattacharya, S., Mo, K., Yun, D., Mohamed, W., Pellin, M., Fortner, J., Kim, Y.S., Hofman, G.L., Yacout, A.M., Wiencek, T., Van den Berghe, S., Leenaers, A.

“…Irradiation responses of U–Mo/Al dispersion fuel have been investigated by irradiation with 84MeV Xe26+ ions. Dispersion fuels fabricated with uncoated and…”
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Thermal creep modeling of HT9 steel for fast reactor applications by Ryu, Ho Jin, Kim, Yeon Soo, Yacout, A.M.

“…The ferritic martensitic steel HT9 is a primary candidate material for the fuel cladding of liquid–metal-cooled fast reactors (LMFRs) owing to its excellent…”
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Lanthanides migration in U–Zr based nuclear fuels by Bozzolo, G., Mosca, H.O., Yacout, A.M., Hofman, G.L.

“…Atomistic modeling using the BFS method for alloys is performed to study the formation of lanthanide-rich precipitates in U–Zr fuel and the segregation…”
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Synthesis of new 1,3,4-thiadiazole and 1,2,3,4-oxathiadiazole derivatives from carbohydrate precursors and study of their effect on tyrosinase enzyme by El-Sadek, Mohamed M, Hassan, Seham Y, Abdelwahab, Huda E, Yacout, Galila A

“…5-(1,2,3,4-Tetrahydroxybutyl)-2-methylfuran-3-carbohydrazide (2) was condensed with a variety of ketones to afford carbohydrazide derivatives 3-6. Acetylation…”
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Modeling of constituent redistribution in U–Pu–Zr metallic fuel by Kim, Yeon Soo, Hayes, S.L., Hofman, G.L., Yacout, A.M.

“…A computer model was developed to analyze constituent redistribution in U–Pu–Zr metallic nuclear fuels. Diffusion and thermochemical properties were…”
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Application of advanced validation concepts to oxide fuel performance codes: LIFE-4 fast-reactor and FRAPCON thermal-reactor fuel performance codes by Unal, C., Williams, B.J., Yacout, A., Higdon, D.M.

“…► The application of advanced validation techniques (sensitivity, calibration and prediction) to nuclear performance codes FRAPCON and LIFE-4 is the focus of…”
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Synthesis and bioassay of a new class of furanyl-1,3,4-oxadiazole derivatives by El Sadek, Mohamed M, Hassan, Seham Y, Abdelwahab, Huda E, Yacout, Galila A

“…Tyrosinase enzyme is a monophenol monoxygenase enzyme, which plays an important role in human as a rate limiting step enzyme for different specific metabolic…”
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Atomistic modeling of the interaction of cladding elements (Fe, Ni, Cr) with U–Zr fuel by Bozzolo, G., Mosca, H.O., Yacout, A.M., Hofman, G.L.

“…Atomistic simulations of U–Zr fuel and its interaction with Fe, Ni, and Cr using the BFS method for alloys are presented. Results for the γU–βZr solid solution…”
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Antioxidant and antitumor activities of new synthesized aromatic C-nucleoside derivatives by El Sadek, Mohamed M, Abd El-Dayem, Nagwa S, Hassan, Seham Y, Mostafa, Mohamed A, Yacout, Galila A

“…The carbohydrazide 1 was used as the precursor for the synthesis of a number of new aromatic C-nucleosides containing 1,3,4-oxadiazole 7,…”
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Cross section TEM characterization of high-energy-Xe-irradiated U-Mo by Ye, B., Jamison, L., Miao, Y., Bhattacharya, S., Hofman, G.L., Yacout, A.M.

“…U-Mo alloys irradiated with 84 MeV Xe ions to various doses were characterized with transmission electron microscopy (TEM) and scanning transmission electron…”
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Microstructure of as atomized and annealed U-Mo7 particles: A SEM/EBSD study of grain growth by Iltis, X., Zacharie-Aubrun, I., Ryu, H.J., Park, J.M., Leenaers, A., Yacout, A.M., Keiser, D.D., Vanni, F., Stepnik, B., Blay, T., Tarisien, N., Tanguy, C., Palancher, H.

“…Significant progresses in the performances under in-pile irradiation of particular U-Mo based fuels have been observed over the last fifteen years. One of the…”
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Atomistic modeling and simulation of the role of Be and Bi in Al diffusion in U–Mo fuel by Hofman, G.L., Bozzolo, G., Mosca, H.O., Yacout, A.M.

“…Within the RERTR program, previous experimental and modeling studies identified Si as the alloying addition to the Al cladding responsible for inhibiting Al…”
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Surface properties, thermal expansion, and segregation in the U–Zr solid solution by Bozzolo, G., Mosca, H.O., Yacout, A.M., Hofman, G.L., Kim, Y.S.

“…Atomistic simulation results of the (γU, βZr) solid solution behavior are discussed, including the behavior of the lattice parameter and coefficient of thermal…”
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