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January 2013 Most Viewed Documents for Fission And Nuclear Technologies

  1. Laboratory studies of shear/leach processing of zircaloy clad metallic uranium reactor fuel
    Swanson, J.L.; Bray, L.A.; Kjarmo, H.E.; Ryan, J.L.; Matsuzaki, C.L.; Pitman, S.G.; Haberman, J.H.
  2. Working session 3: Tubing integrity
    Cueto-Felgueroso, C. [Tecnatom, S.A., San Sebastian de los Reyes, Madrid (Spain)]; Strosnider, J. [NRC, Washington, DC (United States)]
  3. Aqueous Biphasic Systems Based on Salting-Out Polyethylene Glycol or Ionic Solutions: Strategies for Actinide or Fission Product Separations
    Rogers, Robin D.; Gutowski, Keith E.; Griffin, Scott T.; Holbrey, John D.
  4. Use of Solid Hydride Fuel for Improved long-Life LWR Core Designs
    Greenspan, E
  5. DISSOLUTION OF ZIRCALOY 2 CLAD UO2 COMMERCIAL REACTOR FUEL
    Kessinger, G.; Thompson, M.
  6. Safeguardability of advanced spent fuel conditioning process
    Li, T. K. (Tien K.) ; Lee, S. Y. (Sang Yoon) ; Burr, Tom ; Russo, P. A. (Phyllis A.) ; Menlove, Howard O. ; Kim, H. D. ; Ko, W. I. (Won Il) ; Park, S. W. ; Park, H. S.
  7. IDENTIFYING IMPURITIES IN SURPLUS NON PIT PLUTONIUM FEEDS FOR MOX OR ALTERNATIVE DISPOSITION
    Allender, J; Moore, E
  8. TESTING AND CHARACTERIZATION OF ENGINEERED FORMS OF MONOSODIUM TITANATE (MST)
    Taylor-Pashow, K.; Nash, C.; Hobbs, D.
  9. Sodium fast reactor safety and licensing research plan. Volume I.
    Sofu, Tanju (Argonne National Laboratory, Argonne, IL); LaChance, Jeffrey L.; Bari, R. (Brokhaven National Laboratory Upton, NY); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.; Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN)
  10. Piping-reliability analysis for pressurized-water-reactor feedwater lines
    Woo, H.H.; Chou, C.K.