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1000-MWe LMFBR Follow-On Study, Task I Report: Volume 5, Concept IV System Description

From introduction: "The last of four designs to be developed by Babcock & Wilcox (B&W), Concept IV observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980."

Date: August 1967

Creator: Goulding, B. J.

Partner: UNT Libraries Government Documents Department

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Stress Corrosion Cracking in Uranium-Molybdenum Alloys

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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U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1

First volume of a compilation of information about reactor containment, written by experts from a variety of organizations.

Date: August 1965

Creator: Cottrell, William B. & Savolainen, A. W.

Partner: UNT Libraries Government Documents Department

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Design and Economic Evaluation of Fixed Blankets for Fast Reactors

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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Self-Sustained Hydrodynamic Oscillations in a Natural Circulation Two-Phase-Flow Boiling Loop

Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.

Date: August 1965

Creator: Jain, Kamal C.

Partner: UNT Libraries Government Documents Department

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In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

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

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Scintillation Spectrometry Gamma-Ray Catalogue: Volume 2

Gamma-Ray Spectrum diagrams.

Date: August 1964

Creator: Heath, R. L.

Partner: UNT Libraries Government Documents Department

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Progress in Nondestructive Testing: A Summary of Hanford Achievements in These Programs Under General Electric, 1952 - 1964

Report discussing the development of Hanford Laboratories' nondestructive testing programs and a summary of their results. Programs include AlSi fuel testing, N-Reactor fuel testing, and reactor research and development.

Date: August 1964

Creator: Walker, R. A. & Russell, J. T.

Partner: UNT Libraries Government Documents Department

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Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory

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

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

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

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Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

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

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In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962

Report containing the results of a two year program wherein the 85 zircaloy-2 pressure tubes in Hanford Laboratories' Plutonium Recycle Test Reactor (PRTR) were monitored. Experimental procedures and results are described.

Date: August 1962

Creator: Doman, D. R. & Pankaskie, P. J.

Partner: UNT Libraries Government Documents Department

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Protective Clothing Monitoring System

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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Nuclear Safety Program Semiannual Progress Report: for Period Ending June 30, 1962

Report that describes the research and developments of the Nuclear Safety Research and Development Program of the Oak Ridge National Laboratory.

Date: August 24, 1962

Creator: Oak Ridge National Laboratory

Partner: UNT Libraries Government Documents Department

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The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah

Report containing a survey of the radiation from the nuclear ship Savannah in order to determine the dose rate for people aboard.

Date: August 29, 1962

Creator: Blizard, E. P.; Blosser, T. V. & Freeston, R. M., Jr.

Partner: UNT Libraries Government Documents Department

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

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

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Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961

Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.

Date: August 10, 1961

Creator: Aerojet-General Corporation

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

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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Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.

Date: August 17, 1962

Creator: Aerojet-General Corporation

Partner: UNT Libraries Government Documents Department

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Homogeneous Reactor Project Quarterly Progress Report: February-April 1959

Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.

Date: August 8, 1959

Creator: Oak Ridge National Laboratory

Partner: UNT Libraries Government Documents Department

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Applied Health Physics Annual Report for 1963

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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Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO

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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Maintenance of ETR Coolant

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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1000-MWe LMFBR Follow-On Study, Task I Report: Volume 5, Concept IV System Description

Stress Corrosion Cracking in Uranium-Molybdenum Alloys

U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1

Design and Economic Evaluation of Fixed Blankets for Fast Reactors

Self-Sustained Hydrodynamic Oscillations in a Natural Circulation Two-Phase-Flow Boiling Loop

In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Scintillation Spectrometry Gamma-Ray Catalogue: Volume 2

Progress in Nondestructive Testing: A Summary of Hanford Achievements in These Programs Under General Electric, 1952 - 1964

Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory

Dissolution of Power Reactor Fuel Cores

Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C

Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962

Protective Clothing Monitoring System

Nuclear Safety Program Semiannual Progress Report: for Period Ending June 30, 1962

The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah

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

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961

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

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962

Homogeneous Reactor Project Quarterly Progress Report: February-April 1959

Applied Health Physics Annual Report for 1963

Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO

Maintenance of ETR Coolant