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Maintenance of ETR Coolant

Description: Report describing the maintenance system in place for the coolant system of an Engineering Test Reactor (ETR).
Date: August 15, 1958
Creator: Haas, F. C.
Partner: UNT Libraries Government Documents Department
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Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO

Description: Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.
Date: August 23, 1956
Creator: Andelin, Robert L.; Anderson, Edward L. & McVey, W. H.
Partner: UNT Libraries Government Documents Department
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Applied Health Physics Annual Report for 1963

Description: Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.
Date: August 1964
Creator: Morgan, K. Z.; Davis, D. M.; Hart, J. C.; Abee, H. H.; Gupton, E. D. & Warden, A. D.
Partner: UNT Libraries Government Documents Department
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Design and Economic Evaluation of Fixed Blankets for Fast Reactors

Description: Report evaluating the design characteristics and limitations of fixed blankets for breeder reactors. This also includes economic considerations for each tested blanket.
Date: August 30, 1963
Creator: Klickman, A. E.; Ball, G. L.; Edwards, J. J.; Jens, W. H.; Segal, B. M.; Stanford, R. E. L. et al.
Partner: UNT Libraries Government Documents Department
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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

Description: Report presenting the calculation of the costs incurred in shipping irradiated uranium-containing fuel elements. A computer code that designs a cask and calculates the shipping costs is presented. By use of the code, shipping costs were calculated for typical reactor fuels.
Date: August 1964
Creator: Salmon, Royes
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Description: Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
Partner: UNT Libraries Government Documents Department
open access

The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings

Description: Report containing a series of drawings detailing the Oak Ridge National Laboratory's high flux isotope reactor, its surroundings, and its systems.
Date: August 1964
Creator: Binford, F. T.; Cramer, E. N. & Cramer, E. N.
Partner: UNT Libraries Government Documents Department
open access

Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory

Description: Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory.
Date: August 1, 1960
Creator: Reardon, W. A.; Clayton, E. D.; Brown, C. L.; Masterson, R. H.; Powell, T. J.; Richey, C. R. et al.
Partner: UNT Libraries Government Documents Department
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Dissolution of Power Reactor Fuel Cores

Description: Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.
Date: August 26, 1960
Creator: Blaine, H. T.
Partner: UNT Libraries Government Documents Department
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Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C

Description: Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations.
Date: August 12, 1960
Creator: Wilburn, N. P.
Partner: UNT Libraries Government Documents Department
open access

Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

Description: Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.
Date: August 1962
Creator: Hanthorn, H. E.
Partner: UNT Libraries Government Documents Department
open access

Protective Clothing Monitoring System

Description: Report describing the development and installation of an automated conveyor-type laundry system for the purpose of monitoring laboratory clothing for beta-gamma contamination.
Date: August 1, 1963
Creator: Rankin, M. O. & Spear, W. G.
Partner: UNT Libraries Government Documents Department
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FUDGE 4A: A Computer Program for Gamma Dose Rate Distribution from Rectangular Sources

Description: Report issued by the Brookhaven National Laboratory discussing the recently modified FUDGE 4A computer program. As stated in the introduction, "this report presents the details and technical information required for the proper use of FUDGE 4A" (p. 1). This report includes tables, and illustrations.
Date: August 1968
Creator: Galanter, Leonard & Krishnamurthy, Krishnaswamy
Partner: UNT Libraries Government Documents Department
open access

Stress Corrosion Cracking in Uranium-Molybdenum Alloys

Description: Investigation conducted to determine the cause of cracking, during tension, on the surface of tensile specimens of uranium-molybdenum alloys.
Date: August 12, 1963
Creator: Pridgeon, J. W.
Partner: UNT Libraries Government Documents Department
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