Search Results - "Yacout, A.M."

Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel by Salvato, D., Smith, C.A., Ye, B., Mei, Z.-G., Yacout, A.M., Van Eyken, J., Miller, B.D., Keiser, D.D., Glagolenko, I.Y., Giglio, J.J., Robinson, A.B., Leenaers, A., Wight, J., Henley, J.L.

“…[Display omitted] •Scanning electron microscopy (SEM) is usually employed to analyze fission gas porosity in irradiated U-Mo fuel.•In back-scattered electron…”
Get full text

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…”
Get full text

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…”
Get full text

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…”
Get full text

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…”
Get full text

Temperature Effects on Interdiffusion of Al and U-Mo under Irradiation by Ye, B., Miao, Y., Shi, J., Salvato, D., Mo, K., Jamison, L., Bergeron, A., Hofman, G.L., Leenaers, A., Oaks, A., Yacout, A.M., Van den Berghe, S., Petry, W., Kim, Y.S.

“…A high-energy Xe ion irradiation experiment was conducted to investigate the temperature dependence of interdiffusion in bilayer Al-UMo samples under…”
Get full text

Effectiveness of the metal coating on U–7Mo dispersion fuel in Al during irradiation by Kim, Sunghwan, Kim, Yeon Soo, Jeong, Y.J., Mo, K., Miao, Y., Ye, B., Oaks, A., Bhattacharya, S., Lee, K.H., Kim, K.N., Park, J.M., Yacout, A.M.

“…The effectiveness of a transition metal coating layer as a diffusion barrier between the UMo and matrix Al was examined. The samples were cut from KAERI-made…”
Get full text

High-energy synchrotron study of in-pile-irradiated U–Mo fuels by Miao, Yinbin, Mo, Kun, Ye, Bei, Jamison, Laura, Mei, Zhi-Gang, Gan, Jian, Miller, Brandon, Madden, James, Park, Jun-Sang, Almer, Jonathan, Bhattacharya, Sumit, Kim, Yeon Soo, Hofman, Gerard L., Yacout, Abdellatif M.

“…Here synchrotron scattering analysis results on U–7wt.%Mo fuel specimens irradiated in the Advanced Test Reactor to three burnup levels (3.0, 5.2, and…”
Get full text

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…”
Get full text

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…”
Get full text

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…”
Get full text

Derivation of kinetic coefficients by atomistic methods for studying defect behavior in Mo by Insepov, Z., Rest, J., Yacout, A.M., Kuksin, A.Yu, Norman, G.E., Stegailov, V.V., Starikov, S.V., Yanilkin, A.V.

“…► A multiscale concept couples molecular dynamics (MD) with ab initio and kinetic rate theory. ► Evolution of a system of self-interstitial atoms and vacancies…”
Get full text

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…”
Get full text

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…”
Get full text

On the use of Fresnel boundary and interface conditions in radiative-transfer calculations for multilayered media by Garcia, R.D.M., Siewert, C.E., Yacout, A.M.

“…The ADO (analytical discrete ordinates) method is used to establish a concise and accurate solution for a multi-layer radiative-transfer problem with Fresnel…”
Get full text

Fission gas transport and its interactions with irradiation-induced defects in lanthanum doped ceria by Yun, D., Ye, B., Oaks, A.J., Chen, W., Kirk, M.A., Rest, J., Yacout, A.M., Stubbins, J.F.

“…To help understand the mechanisms of irradiation-induced defect formation and evolution in nuclear fuel, systematic experimental efforts have been carried out…”
Get full text

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…”
Get full text

Radiative transfer in a multi-layer medium subject to Fresnel boundary and interface conditions and uniform illumination by obliquely incident parallel rays by Garcia, R.D.M., Siewert, C.E., Yacout, A.M.

“…The ADO (analytical discrete ordinates) method, a pre-processing procedure, and the break-point analysis developed for azimuthally symmetric problems in a…”
Get full text

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…”
Get full text

The effects of xenon implantation in ceria with and without lanthanum by Ye, B., Yun, D., Oaks, A.J., Chen, W., Kirk, M.A., Rest, J., Yacout, A.M., Stubbins, J.F.

“…A combination of in situ and ex situ transmission electron microscopy (TEM) experiments was used to study the evolution of defect clusters during implantation…”
Get full text