Ductile-to-brittle transition temperature for high-burnup cladding alloys exposed to simulated drying-storage conditions von Billone, M.C., Burtseva, T.A., Einziger, R.E.

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High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110 von Yan, Y., Burtseva, T.A., Billone, M.C.

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Nanomedicine in Action: An Overview of Cancer Nanomedicine on the Market and in Clinical Trials von Wang, Ruibing, Mullett, Wayne M., Billone, Paul S.

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Design and material issues for high performance SiCf/SiC-based fusion power cores von RAFFRAY, A. R, JONES, R, RICCARDI, B, TILLACK, M. S, AIELLO, G, BILLONE, M, GIANCARLI, L, GOLFIER, H, HASEGAWA, A, KATOH, Y, KOHYAMA, A, NISHIO, S

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Fusion power core engineering for the ARIES-ST power plant von Tillack, M.S, Wang, X.R, Pulsifer, J, Malang, S, Sze, D.K, Billone, M, Sviatoslavsky, I

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Thermal and tritium transport in Li2O and Li2ZrO3 von Billone, M.C.

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Irradiation creep of vanadium-base alloys von Tsai, H., Matsui, H., Billone, M.C., Strain, R.V., Smith, D.L.

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Vanadium-base alloys for fusion first-wall/blanket applications von Smith, D.L, Billone, M.C, Natesan, K

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Influence of temperature and hydrogen content on stress-induced radial hydride precipitation in Zircaloy-4 cladding von Desquines, J., Drouan, D., Billone, M., Puls, M.P., March, P., Fourgeaud, S., Getrey, C., Elbaz, V., Philippe, M.

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Determination of actinide and fission-product isotopes in very-high-burnup spent nuclear fuel von Sullivan, V. S., Bowers, D. L., Clark, M. A., Graczyk, D. G., Tsai, Y., Streets, W. E., Vander Pol, M. H., Billone, M. C.

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TIARA analysis of tritium inventory in Li2O von BILLONE, M. C

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Materials integration issues for high performance fusion power systems von Smith, D.L, Billone, M.C, Majumdar, S, Mattas, R.F, Sze, D.-K

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Diffusion/desorption of tritium from irradiated beryllium von Baldwin, D.L., Billone, M.C.

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High temperature oxidation behavior of Zr-1Nb cladding alloy E110 von Yan, Y., Burtseva, T., Billone, M. C., Nuclear Engineering Division

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Radial-hydride Embrittlement of High-burnup Zircaloy-4 Fuel Cladding von DAUM, Robert, MAJUMDAR, Saurin, LIU, Yung, BILLONE, Michael

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Status of beryllium development for fusion applications von BILLONE, M. C, DALLE DONNE, M, MACAULAY-NEWCOMBE, R. G

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Performance limits for fusion first-wall structural materials von Smith, D.L., Majumdar, S., Billone, M., Mattas, R.

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Revision of the tensile database for V–Ti and V–Cr–Ti alloys tested at ANL von Billone, M.C., Chung, H.M., Smith, D.L.

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The influence of surface desorption on tritium recovery and inventory in fusion solid breeders von Billone, M.C.

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Implications of radiation-induced reductions in ductility to the design of austenitic stainless steel structures von Lucas, G.E., Billone, M., Pawel, J.E., Hamilton, M.L.

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