IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL von 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.

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The EBR-II X501 minor actinide burning experiment von Meyer, M.K., Hayes, S.L., Carmack, W.J., Tsai, H.

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Oxide scale formation and isothermal oxidation behavior of Mo–Si–B intermetallics at 600–1000°C von Meyer, M.K., Thom, A.J., Akinc, M.

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410: Incidence of Biphasic Reaction and Need for Hospitalization In Patients Admitted to an Emergency Department Observation Unit After Evaluation for Anaphylaxis von Meyer, M.K, Kanthala, A.R, Decker, W.W, Campbell, R.L

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Swelling of U-Mo Monolithic Fuel: Developing a Predictive Swelling Correlation under Research Reactor Conditions von Robinson, A.B., Williams, W.J., Hanson, W.A., Rabin, B.H., Lybeck, N.J., Meyer, M.K.

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Fabrication and characterization of dual phase magnesia–zirconia ceramics doped with plutonia von Medvedev, P.G., Jue, J.F., Frank, S.M., Meyer, M.K.

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Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density von Gan, J., Miller, B.D., Keiser, D.D., Jue, J.F., Madden, J.W., Robinson, A.B., Ozaltun, H., Moore, G., Meyer, M.K.

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Fuel development for gas-cooled fast reactors von Meyer, M.K., Fielding, R., Gan, J.

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Metallic fuels for advanced reactors von Carmack, W.J., Porter, D.L., Chang, Y.I., Hayes, S.L., Meyer, M.K., Burkes, D.E., Lee, C.B., Mizuno, T., Delage, F., Somers, J.

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Thermal stability of fission gas bubble superlattice in irradiated U–10Mo fuel von Gan, J., Keiser, D.D., Miller, B.D., Robinson, A.B., Wachs, D.M., Meyer, M.K.

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AB0021 Resistin Gene Transcription Is Regulated in Adaptive and Innate Immunity in Rheumatoid Arthritis von Andersen, M., Meyer, M.K., Nagaev, I., Nagaeva, O., WIkberg, J.E.S., Mincheva-Nilsson, L., Andersen, G.N.

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AB0020 The Melanocortin System Is Responsive in Disease Driving Immune Cells in Rheumatoid Arthritis and May Offer A Pathway To Curative Treatment von Andersen, M., Meyer, M.K., Nagaev, I., Nagaeva, O., WIkberg, J.E.S., Mincheva-Nilsson, L., Andersen, G.N.

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Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel von Meyer, M.K, Hofman, G.L, Hayes, S.L, Clark, C.R, Wiencek, T.C, Snelgrove, J.L, Strain, R.V, Kim, K.-H

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Determination of optimal imaging parameters for the reconstruction of a nuclear fuel assembly using limited angle neutron tomography von Abir, M.I., Islam, F.F., Craft, A., Williams, W.J., Wachs, D.M., Chichester, D.L., Meyer, M.K., Lee, H.K.

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Dual phase MgO-ZrO2 ceramics for use in LWR inert matrix fuel von MEDVEDEV, P. G, FRANK, S. M, O'HOLLERAN, T. P, MEYER, M. K

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Development of very-high-density low-enriched-uranium fuels von Snelgrove, J.L, Hofman, G.L, Meyer, M.K, Trybus, C.L, Wiencek, T.C

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Thermal conductivity and acid dissolution behavior of MgO-ZrO2 ceramics for use in LWR inert matrix fuel von MEDVEDEV, P. G, LAMBREGTS, M. J, MEYER, M. K

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Thermal conductivity and acid dissolution behavior of MgO–ZrO 2 ceramics for use in LWR inert matrix fuel von Medvedev, P.G., Lambregts, M.J., Meyer, M.K.

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Inert matrix fuel neutronic, thermal-hydraulic, and transient behavior in a light water reactor von Carmack, W.J., Todosow, M., Meyer, M.K., Pasamehmetoglu, K.O.

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Isothermal Oxidation Behavior of Mo-Si-B Intermetallics at 1450°C von Meyer, Mitchell K., Akinc, Mufit

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