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Primary view of U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1
Cottrell, William B. & Savolainen, A. W.
August 1965
Primary view of Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1971
Oak Ridge National Laboratory
August 1971
Primary view of In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C
Jenks, G. H. & Baker, J. E.
August 15, 1963
Primary view of A Revision of Computer Code POWERCO (Cost of Electricity Produced by Nuclear Power Stations) to Include Breakdowns of Power Cost and Fixed Charge Rates
Salmon, Royes
August 1969
Primary view of Progress in Nondestructive Testing: A Summary of Hanford Achievements in These Programs Under General Electric, 1952 - 1964
Walker, R. A. & Russell, J. T.
August 1964
Primary view of Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory
Reardon, W. A.; Clayton, E. D.; Brown, C. L.; Masterson, R. H.; Powell, T. J.; Richey, C. R. et al.
August 1, 1960
Primary view of Dissolution of Power Reactor Fuel Cores
Blaine, H. T.
August 26, 1960
Primary view of Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C
Wilburn, N. P.
August 12, 1960
Primary view of Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements
Hanthorn, H. E.
August 1962
Primary view of In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962
Doman, D. R. & Pankaskie, P. J.
August 1962
Primary view of Protective Clothing Monitoring System
Rankin, M. O. & Spear, W. G.
August 1, 1963
Primary view of The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings
Binford, F. T.; Cramer, E. N. & Cramer, E. N.
August 1964
Primary view of Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961
Aerojet-General Corporation
August 10, 1961
Primary view of A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables
Salmon, Royes
August 1964
Primary view of Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962
Aerojet-General Corporation
August 17, 1962
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
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