Search Results - "Keiser, D.D."

IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL by MEYER, M.K., GAN, J., JUE, J.F., KEISER, D.D., PEREZ, E., ROBINSON, A., WACHS, D.M., WOOLSTENHULME, N., HOFMAN, G.L., KIM, Y.S.

“…High-performance research reactors require fuel that operates at high specific power to high fission density, but at relatively low temperatures. Research…”
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Investigation of interdiffusion behavior in the Mo–Zr binary system via diffusion couple studies by Paz y Puente, A., Dickson, J., Keiser, D.D., Sohn, Y.H.

“…Zirconium has recently garnered attention for use as a diffusion barrier between U–Mo metallic nuclear fuels and Al alloy cladding. In order to gain a…”
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TEM characterization of U–7Mo/Al–2Si dispersion fuel irradiated to intermediate and high fission densities by Gan, J., Keiser, D.D., Miller, B.D., Robinson, A.B., Jue, J.F., Medvedev, P., Wachs, D.M.

“…This paper will discuss the results of transmission electron microscopy (TEM) analysis performed on two samples taken from the low-flux and high-flux sides of…”
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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…”
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Annealing influence on the microstructure of irradiated U-Mo monolithic fuel foils by Di Lemma, F.G., Jue, J.F., Trowbridge, T.L., Smith, C.A., Miller, B.D., Keiser, D.D., Giglio, J.J., Cole, J.I.

“…•Heat treatment influence on the microstructure of irradiated U-Mo fuel specimens was investigated.•Irradiation induced grain refining is influenced by the…”
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Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7wt%Mo dispersion fuels by Miller, B.D., Gan, J., Keiser, D.D., Robinson, A.B., Jue, J.F., Madden, J.W., Medvedev, P.G.

“…Transmission electron microscopy characterization of irradiated U–7wt%Mo dispersion fuel were performed on various U–Mo fuel samples to understand the effect…”
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Microstructure of the irradiated U3Si2/Al silicide dispersion fuel by GAN, J, KEISER, D. D, MILLER, B. D, JUE, J.-F, ROBINSON, A. B, MADDEN, J. W, MEDVEDEV, P. G, WACHS, D. M

“…The silicide dispersion fuel of U3Si2/Al is recognized as the best performance fuel for many nuclear research and test reactors with up to 4.8 gU/cm3 for…”
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IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL by Meyer, M.K, Gan, J, Jue, J.F, Keiser, D.D, Perez, E, Robinson, A, Wachs, D.M, Woolstenhulme, N, Hofman, G.L, Kim, Y.S

“…High-performance research reactors require fuel that operates at high specific power to high fission density, but at relatively low temperatures. Research…”
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The complex structural and chemical nature of monolithic U-10Mo fuel and Zr barrier layer by Barr, C.M., Lang, E., Burns, K., Price, P., Miller, B.D., Keiser, D.D., Aitkaliyeva, A., Hattar, K.

“…Nanoscale microstructural characterization by advanced transmission electron microscopy techniques on a U-10Mo/Zr barrier layer monolithic fuel plate was…”
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Microstructural development from interdiffusion and reaction between UMo and AA6061 alloys annealed at 600° and 550 °C by Perez, E., Keiser, D.D., Sohn, Y.H.

“…The U.S. Material Management and Minimization Reactor Conversion Program is developing low enrichment fuel systems encased in Al-alloy for use in research and…”
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Phase decomposition of γ-U (bcc) in U-10 wt% Mo fuel alloy during hot isostatic pressing of monolithic fuel plate by Park, Y., Eriksson, N., Newell, R., Keiser, D.D., Sohn, Y.H.

“…Eutectoid decomposition of γ-phase (cI2) into α-phase (oC4) and γ′-phase (tI6) during the hot isostatic pressing (HIP) of the U-10 wt% Mo (U10Mo) alloy was…”
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Effect of heat treatment on the microstructure of medium burn-up U-Mo monolithic fuel foils by Di Lemma, F.G., Trowbridge, T.L., Jue, J.F., Salvato, D., Anderson, S., Smith, C.A., Miller, B.D., Keiser, D.D., Giglio, J.J., Cole, J.I.

“…Using scanning electron microscopy (SEM), this study evaluates the microstructure evolution of uranium-molybdenum (U-Mo) fuel foils made with and without heat…”
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Interdiffusion and reactions between U–Mo and Zr at 650°C as a function of time by Park, Y., Keiser, D.D., Sohn, Y.H.

“…Development of monolithic U–Mo alloy fuel (typically U–10wt.%Mo) for the Reduced Enrichment for Research and Test Reactors (RERTR) program entails a use of Zr…”
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Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density by Gan, J., Miller, B.D., Keiser, D.D., Jue, J.F., Madden, J.W., Robinson, A.B., Ozaltun, H., Moore, G., Meyer, M.K.

“…Monolithic U-10Mo alloy fuel plates with Al-6061 cladding are being developed for use in research and test reactors as low enrichment fuel (<20% U-235…”
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Microstructural development from interdiffusion and reaction between U Mo and AA6061 alloys annealed at 600° and 550 °C by Perez, E., Keiser, D.D., Sohn, Y.H.

“…The U.S. Material Management and Minimization Reactor Conversion Program is developing low enrichment fuel systems encased in Al-alloy for use in research and…”
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3D reconstructions of irradiated UMo fuel to understand breaching effects in ZrN diffusion barriers by Miller, B.D., Keiser, D.D., Abir, M., Aitkaliyeva, A., Leenaers, A., Hernandez, B.J., Van Renterghem, W., Winston, A.

“…To understand interaction layer behavior in UMo fuel kernels coated with physical vapor deposition (PVD) ZrN barriers, two cubes of irradiated fuel were serial…”
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Phase development in a U–7wt.% Mo vs. Al–7wt.% Ge diffusion couple by Perez, E., Keiser, D.D., Sohn, Y.H.

“…Fuel development for the Reduced Enrichment for Research and Test Reactors (RERTR) program has demonstrated that U–Mo alloys in contact with Al develop…”
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Interdiffusion and reaction between U and Zr by Park, Y., Newell, R., Mehta, A., Keiser, D.D., Sohn, Y.H.

“…The microstructural development and diffusion kinetics were examined for the binary U vs. Zr system using solid-to-solid diffusion couples, U vs. Zr, annealed…”
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Texture analyses and microstructural evolution in monolithic U-Mo nuclear fuel by Lemma, F.G. Di, Burns, J., Madden, J.W., Winston, A.J., Robinson, A.B., Jue, J.F., Keiser, D.D., Cole, J.I.

“…•Microstructural evolution of irradiated monolithic U-Mo fuel plate was analyzed.•BCC rolled texture was developed after fabrication.•After irradiation, a loss…”
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Impacts of annealing treatment on the microstructure of U-Mo monolithic fuel plates by Di Lemma, F.G., Jue, J.F., Winston, A.J., Pu, X., Anderson, S., Keiser, D.D., Giglio, J.J., Cole, J.I.

“…The objective of this paper is to analyze the effect of different heat treatments on the fuel microstructure and texture in laboratory scale monolithic U-Mo…”
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