Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Glenn R Waterbury"'
Publikováno v:
Nuclear Technology. 23:132-141
From joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Enengy Exhibition; San Francisco, California, USA (11 Nov 1973). The plutonium-containing samples analyzed for nuclear safeguards purposes range from heter
Autor:
William C. Bartels, Carleton D. Bingham, Morris W. Lerner, R. E. Reed, J. M. de Montmollin, T. A. Sellers, Thomas E. Sampson, Paul E. Fehlau, Gary M. Worth, Carl N. Henry, Darryl D. Jackson, James E. Rein, Glenn R Waterbury, C. Sastre, S. Barsali, R. Bovalini, F. Fineschi, B. Guerrini, S. Lanza, M. Mazzini, R. Mirandola, C. L. Schuske, D. Dickinson, S. J. Altschuler, Grover Tuck, T. J. Walker
Publikováno v:
Nuclear Technology. 23:96-99
Autor:
Glenn R. Waterbury, Charles F. Metz
Publikováno v:
Talanta. 6:237-245
Summary In the development of fuel processing methods for purifying Pu-Fe or Pu-Co fuel alloys, methods of chemical analysis were required for the alloying element and representative fission product elements. The initial Pu fissium alloy, which repre
Publikováno v:
Analytical Chemistry. 36:2094-2097
Zirconium and molybdenum in uranium-zirconium-molybdenum carbide are determined without chemical separation using an x-ray fluorescence spectrographic procedure. The mixed carbide is dissolved in nitrichydrofluoric acid, niobium is added to serve as
Publikováno v:
Journal of the American Chemical Society. 74:15-20
Autor:
Don S. Martin, Glenn R. Waterbury
Publikováno v:
Journal of the American Chemical Society. 75:4162-4167
Autor:
E.A. Hakkila, Glenn R. Waterbury
Publikováno v:
Talanta. 6:46-51
X-ray fluorescence methods have been used for determining molybdenum, niobium, thorium, tungsten, yttrium and zirconium as impurities or alloying constituents in tantalum and binary tantalum alloys being investigated as container materials for molten
Autor:
Glenn R. Waterbury, James E. Rein
Publikováno v:
The International Journal of Applied Radiation and Isotopes. 35:159-161
The 240 Pu oxide, enriched to 98.5% in 240 Pu, used for the half-life measurements was prepared by ion-exchange purification in nitric acid solution, followed by heating at 1250°C to the oxide. Four laboratories provided characterizations of plutoni
Autor:
Glenn R. Waterbury, James E. Rein
Publikováno v:
The International Journal of Applied Radiation and Isotopes. 29:485-487
The 239 Pu metal used for the half-life measurement was prepared by an electro-refining process and then chemically characterized by three laboratories. Data are presented for isotopic composition, total plutonium content, and metal and nonmetal impu
Publikováno v:
Analytical Chemistry. 41:665-667