Multi-Scale Characterization of Porosity and Cracks in Silicon Carbide Cladding after Transient Reactor Test Facility Irradiation von Xu, Fei, Yao, Tiankai, Xu, Peng, Schulthess, Jason L, Matos, Mario D, Gonderman, Sean, Gazza, Jack, Kane, Joshua J, Cordes, Nikolaus L

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Advanced Crack Analytics on 3D X-ray Tomography of Irradiated Silicon Carbide Claddings von Xu, Fei, Kane, Joshua J., Xu, Peng, Cordes, Nikolaus, Schulthess, Jason L., Cinbiz, Mahmut Nedim, Gonderman, Sean, Deck, Christian, Gazza, Jack

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Thermal properties of U-Mo alloys irradiated under high fission power density von Burkes, Douglas E., Schwerdt, Ian J., Huber, Tanja K., Breitkreutz, Harald, Reiter, Christian, Petry, Winfried, Schulthess, Jason L., Casella, Andrew M., Casella, Amanda J., Buck, Edgar C., Pool, Karl N., MacFarlan, Paul J., Edwards, Matthew K., Smith, Frances N.

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Mechanical properties of irradiated UMo alloy fuel von Schulthess, Jason L., Lloyd, Wilson R., Rabin, Barry, Wheeler, Katelyn, Walters, Thomas W.

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Post-irradiation examination of UN-Mo-W fuels for space nuclear propulsion von Khan, Sarah A., Schulthess, Jason L., Charit, Indrajit, Craft, Aaron, Chuirazzi, William, Burns, Jatuporn, Frazer, David, Woolstenhulme, Nicolas, O'Brien, Robert

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Mechanical properties of irradiated U Mo alloy fuel von Schulthess, Jason L., Lloyd, Wilson R., Rabin, Barry, Wheeler, Katelyn, Walters, Thomas W.

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A standard capsule design for structural material testing in the Advanced Test Reactor von Anderson, K.S., Hale, D.D., Schulthess, J.L., Arrowood, M.M.

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Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating von Schulthess, Jason L., Spencer, Benjamin W., Petersen, Philip G., Woolstenhulme, Nicolas E., Ban, David, Frazer, David, Sudderth, Laura, Hamilton, Sarah, Jewell, James K., Mariani, Robert D.

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Elevated temperature tensile tests on DU–10Mo rolled foils von Schulthess, Jason, Lloyd, Randy, Rabin, Barry, Heighes, Michael, Trowbridge, Tammy, Perez, Emmanuel

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Resumption of water capsule reactivity-initiated accident testing at TREAT von Folsom, Charles P., Schulthess, Jason L., Kamerman, David W., Hansen, Robert S., Woolstenhulme, Nicolas E., Jensen, Colby B., Astle, Leigh A., Ocampo Giraldo, Luis, Fleming, Austin, Wachs, Daniel M.

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Dry in-pile fracture test (DRIFT) for separate-effects validation of ceramic fuel fracture models von Spencer, Benjamin W., Woolstenhulme, Nicolas E., Schulthess, Jason L., Fleming, Austin D., Astle, Leigh A., Devin Imholte, D., Hill, Connie M., Parry, James R., Chapman, Daniel B., Folsom, Charles P., Ban, David, Ramirez, Matthew R., Woolum, Connor T., Yeh, Ju-Yuan, Dunzik-Gougar, Mary Lou, Jensen, Colby B., Wachs, Daniel M.

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Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating von Schulthess, Jason L., Spencer, Benjamin W., Petersen, Philip G., Woolstenhulme, Nicolas E., Ban, David, Frazer, David M., Sudderth, Laura K., Hamilton, Sarah Rose, Jewell, James K., Mariani, Robert D.

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Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development von Schulthess, Jason L., Baird, Katelyn, Petersen, Philip, Salvato, Daniele, Ozaltun, Hakan, Hanson, William A., Ullum, Nicholas, Giglio, Jeffrey, Cole, James I.

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Advanced Analytics on 3D X-ray Tomography of Irradiated Silicon Carbide Claddings von Xu, Fei, Kane, Joshua J, Xu, Peng, Schulthess, Jason L, Gonderman, Sean, Cordesa, Nikolaus L

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Advanced Analytics on 3D X-ray Tomography of Irradiated Silicon Carbide Claddings von Xu, Fei, Kane, Joshua J, Xu, Peng, Schulthess, Jason L, Gonderman, Sean, Cordesa, Nikolaus L

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Effect of fission rate on the microstructure of coated UMo dispersion fuel von Leenaers, A., Parthoens, Y., Cornelis, G., Kuzminov, V., Koonen, E., Van den Berghe, S., Ye, B., Hofman, G.L., Schulthess, Jason

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Effect of fission rate on the microstructure of coated UMo dispersion fuel von Leenaers, A., Parthoens, Y., Cornelis, G., Kuzminov, V., Koonen, E., Van den Berghe, S., Ye, B., Hofman, G. L., Schulthess, Jason

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