Progress Report on Loading of Titanium with Deuterium (open access)

Progress Report on Loading of Titanium with Deuterium

Report issued by the University of California Radiation Laboratory discussing an experiment in which a system was designed and built to load titanium with deuterium gas of a high purity. It discusses the results and the parameters affecting the amounts and purity of the absorbed gas.
Date: May 5, 1955
Creator: Ruff, James W.
Object Type: Report
System: The UNT Digital Library
Reactor Development Program Progress Report: April 1963 (open access)

Reactor Development Program Progress Report: April 1963

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: May 15, 1963
Creator: Adams, R. M. & Glassner, A.
Object Type: Report
System: The UNT Digital Library
Uranium-Bismuth In-Pile Corrosion Test Loop: Radiation Loop No. 1 (open access)

Uranium-Bismuth In-Pile Corrosion Test Loop: Radiation Loop No. 1

Report issued by the Brookhaven National Laboratory discussing uranium-bismuth corrosion test loops. Design, construction, and operation of the test loops are presented. This report includes tables, illustrations, and photographs.
Date: May 1961
Creator: Waide, C. H.; Kukacka, L. E.; Meyer, R. A.; Milau, J.; Klein, J. H.; Chow, J. G. Y. et al.
Object Type: Report
System: The UNT Digital Library
Summary Hazards Report on Enriched Fuel Element Loading for the BNL Research Reactor (open access)

Summary Hazards Report on Enriched Fuel Element Loading for the BNL Research Reactor

Report issued by the Brookhaven National Laboratory discussing a hazards report on replacing the research center's current fuel elements with new highly enriched elements. As stated in the introduction, "this report is a summary of the studies, both theoretical and experimental, which have been made so far of the nuclear properties of the "new" pile, of the stability of the new fuel elements, and of the safety and practicability of operation of the "new" pile" (p. 2). This report includes tables, and illustrations.
Date: May 24, 1956
Creator: Corngold, N.; Kaplan, I.; Chernick, J.; Gurinsky, D. H. & Fowell, R. W.
Object Type: Report
System: The UNT Digital Library
Health Physics Instrument Manual (open access)

Health Physics Instrument Manual

Report issued by the Oak Ridge National Laboratory discussing a Health Physics Instrument Manual. Descriptions, characteristics, and applications of different instruments are presented. This report includes tables, illustrations, and photographs.
Date: May 16, 1963
Creator: Davis, D. M. & Gupton, E. D.
Object Type: Report
System: The UNT Digital Library
Aqueous Homogeneous Reactors for Producing Central-Station Power (open access)

Aqueous Homogeneous Reactors for Producing Central-Station Power

Report issued by the Oak Ridge National Laboratory discussing aqueous homogeneous reactors used in central-station power. As stated in the introduction, "it contains an evaluation of the potentiality of producing power only, as exhibited by aqueous homogeneous systems" (p. 6). This report includes tables, and illustrations.
Date: May 25, 1951
Creator: Briggs, R. B.; Haubenreich, P. N.; Sanders, J. P.; Aven, R. E.; Zapp, F. C.; Segaser, C. L. et al.
Object Type: Report
System: The UNT Digital Library
Review of Radioisotopes Program, 1964 (open access)

Review of Radioisotopes Program, 1964

Report issued by the Oak Ridge National Laboratory discussing a review of the Radioisotopes Program during 1964. Research and experimental projects conducted during 1964 is presented. This report includes tables, illustrations, and photographs.
Date: May 1965
Creator: Gillette, J. H.
Object Type: Report
System: The UNT Digital Library
Research and Development Studies on Waste Storage Process (open access)

Research and Development Studies on Waste Storage Process

Report documenting "the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide" (p. 4).
Date: May 19, 1961
Creator: Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
Object Type: Report
System: The UNT Digital Library
Completion Report for Contracts AT(10-1)-1054, AT(10-1)-1122 : Drilling, Casing and Cementing Observation Wells at the National Reactor Testing Station, Idaho (open access)

Completion Report for Contracts AT(10-1)-1054, AT(10-1)-1122 : Drilling, Casing and Cementing Observation Wells at the National Reactor Testing Station, Idaho

Report that "summarizes the costs, experience and results of contracts AT(10-1)-1054 and AT(10-1)-1122 for drilling, casing and cementing observation wells at the National Reactor Testing Station, Idaho" (p. [11]).
Date: May 1, 1963
Creator: Keys, W. S.
Object Type: Report
System: The UNT Digital Library
Chemical and Physical Character of Ground Water in the National Reactor Testing Station, Idaho (open access)

Chemical and Physical Character of Ground Water in the National Reactor Testing Station, Idaho

Report documenting "the chemical and physical properties of the ground water beneath the National Reactor Testing Stations (NRTS), Idaho. The chemical properties described are chiefly the concentration and proportions of the dissolved constituents" (p. 1).
Date: May 1962
Creator: Olmsted, F. H.
Object Type: Report
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959 (open access)

Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Date: May 25, 1959
Creator: Aerojet-General Corporation
Object Type: Report
System: The UNT Digital Library
The High Flux Isotope Reactor: Volume 1, A Functional Description (open access)

The High Flux Isotope Reactor: Volume 1, A Functional Description

Report containing a description of the Oak Ridge National Laboratory's High-Flux Isotope Reactor (HFIR) and its operation.
Date: May 1964
Creator: Binford, F. T. & Cramer, E. N.
Object Type: Report
System: The UNT Digital Library
The Expulsion of Liquid from a Rapidly Heated Channel (open access)

The Expulsion of Liquid from a Rapidly Heated Channel

Report documenting experiments in order to determine the "behavior of a partially confined liquid in contact with a rapidly heated surface" (p. 7). These liquids include water, methanol, ethylene bromide, and acetone.
Date: May 1967
Creator: Singer, Ralph M.
Object Type: Report
System: The UNT Digital Library
UT-4: An Automatic Ultrasonic Tester for Closures of Hanford I&E Fuels (open access)

UT-4: An Automatic Ultrasonic Tester for Closures of Hanford I&E Fuels

Report that "describes the equipment, technologies of use, and reliability of an ultrasonic tester - designated UT-4 - capable of detecting very small defects in the brazed closures of reactor fuel elements" (p. 2).
Date: May 1963
Creator: Hunter, D. O. & Zeutschel, M. F.
Object Type: Report
System: The UNT Digital Library
Corrosion Studies in Simulated N-Reactor Secondary System Water Environment (open access)

Corrosion Studies in Simulated N-Reactor Secondary System Water Environment

Report containing the procedures and results of tests made to determine the corrosion resistance of materials in a simulation of Hanford Laboratories' N-Reactor secondary system water environment.
Date: May 1963
Creator: Larrick, A. P.
Object Type: Report
System: The UNT Digital Library
Gas-Metal Reactions with Iron- and Nickel-Base Heat Resistant Alloys: An Interpretive Literature Survey (open access)

Gas-Metal Reactions with Iron- and Nickel-Base Heat Resistant Alloys: An Interpretive Literature Survey

Report reviewing literature that concerns "the compatibility of stainless steels and nickel-base alloys with various gases which might be present in or around a high temperature nuclear reactor" (p. 2).
Date: May 1963
Creator: Jones, D. A.
Object Type: Report
System: The UNT Digital Library
Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process (open access)

Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process

Report documenting the process of decontaminating low-activity fuel waste water via the Scavenging-Precipitation Ion-Exchange process. This includes analyses of the costs of the process as well as a description of the operation of the pilot plant.
Date: May 27, 1963
Creator: Brooksbank, R. E.; Browder, F. N.; Holcomb, R. R. & Whitson, W. R.
Object Type: Report
System: The UNT Digital Library
The ML-1 Design Report (open access)

The ML-1 Design Report

From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."
Date: May 16, 1960
Creator: Linenberger, G. A.
Object Type: Report
System: The UNT Digital Library
Hydrology of Subsurface Waste Disposal, National Reactor Testing Station, Idaho : Annual Progress Report, 1963 (open access)

Hydrology of Subsurface Waste Disposal, National Reactor Testing Station, Idaho : Annual Progress Report, 1963

From introduction: "The present report indicates additional preliminary progress in the interpretation of the geology of the area on the basis of preliminary gravity and magnetic surveys and sketches the progress made in operational phases of the study of the hydrology of waste disposal."
Date: May 1964
Creator: Morris, D. A.
Object Type: Report
System: The UNT Digital Library
Determination of the Effect of High Excess H2SO4 Concentrations on the Radiation-Induced Corrosion of Zirconium and Titanium Alloys in 0.17 m UO2SO4 (open access)

Determination of the Effect of High Excess H2SO4 Concentrations on the Radiation-Induced Corrosion of Zirconium and Titanium Alloys in 0.17 m UO2SO4

Study of the effects on Zircaloy-2 radiation corrosion of a high concentration of excess H2SO4 in a uranyl sulfate test solution using an in-pile loop experiment.
Date: May 1, 1962
Creator: Jenks, G. H.
Object Type: Report
System: The UNT Digital Library
In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C (open access)

In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C

One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.
Date: May 5, 1962
Creator: Jenks, G. H.
Object Type: Report
System: The UNT Digital Library
Thermonuclear Division Semiannual Progress Report, January 31, 1961 (open access)

Thermonuclear Division Semiannual Progress Report, January 31, 1961

Report describing ongoing progress made at the Oak Ridge National Laboratory's Thermonuclear Division.
Date: May 31, 1961
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures

Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
Date: May 15, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment: Operation and Testing of a Nonnuclear Liquid-Metal System (open access)

Liquid Metal Fuel Reactor Experiment: Operation and Testing of a Nonnuclear Liquid-Metal System

Extensive experimental program undertaken to provide data on the operation and testing of a bismuth-to-bismuth dual-loop system.
Date: May 1960
Creator: unknown
Object Type: Report
System: The UNT Digital Library