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Primary view of Applied Health Physics Annual Report for 1963
Morgan, K. Z.; Davis, D. M.; Hart, J. C.; Abee, H. H.; Gupton, E. D. & Warden, A. D.
August 1964
Primary view of Gas-Cooled Reactor Project Semiannual Progress Report: September 1964
Trauger, D. B. & Whitman, G. D.
February 1965
Primary view of Gas-Cooled Reactor Project Semiannual Progress Report: March 1965
Trauger, D. B. & Whitman, G. D.
June 1965
Primary view of Maritime Reactor Project Annual Progress Report for Period Ending November 30, 1963
McCurdy, H. C.
March 1965
Primary view of Molten-Salt Reactor Program Quarterly Progress Report: October 1957
MacPherson, H. G.
February 21, 1958
Primary view of Molten-Salt Reactor Program Semiannual Progress Report for Period Ending July 31, 1964
Briggs, R. B.
November 1964
Primary view of Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965
Briggs, R. B.
June 1965
Primary view of Snap-8 Corrosion Program Quarterly Progress Report for Period Ending November 30, 1964
Savage, H. W.; Compere, E. L.; MacPherson, R. E.; Huntley, W. R. & Taboada, A.
March 1965
Primary view of Health Physics Instrument Manual
Davis, D. M. & Gupton, E. D.
May 16, 1963
Primary view of Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums
Bourgette, D. T.
November 1964
Primary view of Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride
Gens, T. A.
October 1964
Primary view of Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney
Jones, Edith Seymour
February 1965
Primary view of High-Density Concrete for Gamma and Neutron Attenuation
Northup, T. E.
March 1965
Primary view of Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor
Thurber, W. C.; McQuilkin, F. R.; Long, E. L., Jr. & Osborne, M. F.
November 1964
Primary view of Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV
deSaussure, G.; Weston, L. W.; Gwin, R.; Russell, J. E. & Hockenbury, R. W.
April 1965
Primary view of Optical Mapping of Oak Ridge Research Reactor Experiment Tubes
Abbatiello, A. A.
April 1965
Primary view of Type 316 Stainless Steel, Inconel, and Haynes Alloy No. 25 Natural-Circulation Boiling-Potassium Corrosion Test Loops
Jansen, D. H. & Hoffman, E. E.
June 1965
Primary view of Review of Radioisotopes Program, 1964
Gillette, J. H.
May 1965
Primary view of Preliminary Designs for Four Integrated Gas-Cooled Ceramic-Fueled and -Moderated Reactor Core and Steam Generator Units
Fraas, A. P.
1962
Primary view of Corn Pone: A Multigroup, Multiregion Reactor Code
Kinney, W. E. & Coveyou, R. R.
1961?
Primary view of Development of the Assembly Method for Fuel Elements for the Advanced Test Reactor
Knight, R. W. & Leitten, C. F., Jr.
1964
Primary view of Metallurgy Division Annual Progress Report, September 1, 1959
Oak Ridge National Laboratory. Metallurgy Division.
December 16, 1959
Primary view of Molten-Salt Reactor Program Quarterly Progress Report: October 1958
Oak Ridge National Laboratory
1959
Primary view of Molten-Salt Reactor Program Quarterly Progress Report: April 1959
Oak Ridge National Laboratory
June 26, 1959
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