Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Period Ending January 15, 1945 (open access)

Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Period Ending January 15, 1945

Technical report with short reports covering (1) Effect of radiation on water and aqueous systems; (2) Effect of neutrons on graphite; (3) Effect of radiation on solid compounds; and (4) Scattering, stopping-power, ion-pair production, etc.
Date: February 1, 1945
Creator: Burton, Milton, 1902- & Allen, A. O. (Augustine O.)
System: The UNT Digital Library
The Determination of Tuballoy in the Presence of Thorium in Peroxide Effluents and Cakes (open access)

The Determination of Tuballoy in the Presence of Thorium in Peroxide Effluents and Cakes

Abstract: "A polarographic method for the determination of tuballoy in thorium peroxide cakes in all sold medium was found to give satisfactory results. Fluorescent analyses on effluents containing thorium gave good results if the thorium content was kept below 1 mg/liter."
Date: February 1, 1946
Creator: Lasko, Wiliam. R. & Susano, C. D.
System: The UNT Digital Library
High Frequency Induction Heating (open access)

High Frequency Induction Heating

Abstract: Equations are given to calculate at least approximately the heating in solid and hollow cylinders, slabs and spheres. Short and long cylinders are treated as well as short and long solenoids. The complicated mathematics used to derive the equations given will be omitted as they may be found in the original references. Heating with a spark gap converter is covered. Equations are given which together with some experimental data should enable the reader to predict the efficiency, heating, or temperature to be expected as the charge or coil is changed. Units and conversion factors are mentioned briefly.
Date: February 1, 1947
Creator: Bromley, LeRoy A.
System: The UNT Digital Library
Ultrasonic Testing of Small-Diameter Tubing (open access)

Ultrasonic Testing of Small-Diameter Tubing

The following report describes the procedure and equipment allowing ultrasonics to be applied successfully to locate flaws in 0.060 in. ID x 0.080 in. OD tubing.
Date: February 1, 1952
Creator: Pardus, A. J.
System: The UNT Digital Library
Dynamics of the Supercritical Water Reactor (open access)

Dynamics of the Supercritical Water Reactor

From introduction: "The work described in this report was carried out as part of the feasibility study (ORNL-117) of a supercritical water reactor (SCWR) for use in nuclear propulsion of aircraft. The object of this work was to study the dynamic behavior of a particular design of supercritical water reactor. Numerical results are presented in Appendix I."
Date: February 1, 1953
Creator: Goertzel, Gerald, 1919-; Shapiro, Mathew M. & Soodak, Harry
System: The UNT Digital Library
A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor (open access)

A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor

From abstract: A conceptual design study has been performed for a sodium cooled, graphite moderated, thermal power-breeder reactor utilizing the Thorium-Uranium 233 breeding cycle. Several aspects of the design of the system are considered but no attempt has been made to supply all the details. It appears that the design presented is feasible and will allow the production of economic power as well as full utilization of thorium resources.
Date: February 1, 1954
Creator: Henrie, J. O. & Weisner, E. F.
System: The UNT Digital Library
The Elimination of Microwave Reflections (open access)

The Elimination of Microwave Reflections

Abstract: "The reflections of microwaves from the walls of a plasma-containing vessel are studied. The probable cause of the reflections is discussed, and several suggestions are made for eliminating the reflections from the waveguide in the vessel and particularly from the pyrex vessel wall and copper tubing surrounding the pyrex. Quarter-wave-thick carbon-filled plastics or glasses having a very low vapor pressure room most promising when placed inside the pyrex cylinder. BaTiO3 appears to be an excellent material when placed outside the vacuum."
Date: February 1, 1955
Creator: Beard, David
System: The UNT Digital Library
Progress Relating to Civilian Applications During January, 1956 (open access)

Progress Relating to Civilian Applications During January, 1956

A report which discusses the response of dilute uranium alloys to heat treatment with the ultimate objective of developing high-strength fuel elements.
Date: February 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
System: The UNT Digital Library
Progress Relating to Civilian Applications During January, 1957 (open access)

Progress Relating to Civilian Applications During January, 1957

A report which investigates the effect of irradiation on the thermal conductivity of uranium. Thermal-conductivity measurements are made on clad uranium specimens prior to irradiation.
Date: February 1, 1957
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
System: The UNT Digital Library
Organic Moderated Reactor Experiment : Safeguards Summary (open access)

Organic Moderated Reactor Experiment : Safeguards Summary

Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.
Date: February 1, 1958
Creator: Sletten, H. L. & Blue, L. R.
System: The UNT Digital Library
Design Analysis of a Prepackaged Nuclear Power Plant: Volume 1, Primary and Secondary System Design (open access)

Design Analysis of a Prepackaged Nuclear Power Plant: Volume 1, Primary and Secondary System Design

Design analysis of a prepackaged nuclear power plant.
Date: February 1, 1959
Creator: unknown
System: The UNT Digital Library
Design Analysis of a Prepackaged Nuclear Power Plant: Volume 2, Reactor Design Analysis (open access)

Design Analysis of a Prepackaged Nuclear Power Plant: Volume 2, Reactor Design Analysis

Design analysis of a prepackaged nuclear power plant.
Date: February 1, 1959
Creator: unknown
System: The UNT Digital Library
Mechanical Properties of Zircaloy-2 (open access)

Mechanical Properties of Zircaloy-2

Abstract: The mechanical and physical properties of Zircaloy-2 were determined as a function of five test variables: temperature, grain size, direction to rolling, hydrogen content, and the presence or absence of a notch.
Date: February 1, 1961
Creator: Mehan, R. L. & Wiesinger, F. W.
System: The UNT Digital Library
Boiling Nuclear Superheater (BONUS) Power Station : Final Hazards Summary Report (open access)

Boiling Nuclear Superheater (BONUS) Power Station : Final Hazards Summary Report

Summary report of final hazards for the Boiling Nuclear Superheater (BONUS) Power Station with illustrations.
Date: February 1, 1962
Creator: unknown
System: The UNT Digital Library
Hazards Report for Step Transient Loading Tests on the SM-1 : Task XII (open access)

Hazards Report for Step Transient Loading Tests on the SM-1 : Task XII

Abstract: This technical report evaluates hazards involved with SM- 1 plant response and system performance tests (Task XII), to determine the response of the SM-1 plant to step electrical and steam load changes. The report describes the changes in plant equipment and operating procedures for this task and evaluates these changes for possible additional hazards to those described in APAE No. 2, Revision 1, "Hazards Summary Report for the Army Package Power Reactor SM-1."
Date: February 1, 1962
Creator: Pomeroy, D. L.
System: The UNT Digital Library
Salt Bath Heat Transfer Rates for Uranium Plate (open access)

Salt Bath Heat Transfer Rates for Uranium Plate

Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Date: February 1, 1962
Creator: Burditt, R. B.
System: The UNT Digital Library
Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits (open access)

Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits

Introduction: The purpose of this experiment is to determine the loss of electrical power output due to operating many unequally-heated cesium diodes, connected in series and parallel circuits.
Date: February 1, 1963
Creator: Holland, J. W.
System: The UNT Digital Library
An Experimental Approach to a Simplified Band Structure of the Rare Earth Metals (open access)

An Experimental Approach to a Simplified Band Structure of the Rare Earth Metals

Technical report. From Abstract : "A number of the physical properties from which we can obtain both direct and indirect information concerning the band structures of metals, have been measured for most of the rare earth metals. It was thought that it would be desirable to review ans examine these data and try to tie them together. For this purpose the very low and room temperature heat capacities, Hall coefficients, magnetic susceptibilities, spectral data and electrical resistivities were examined."
Date: February 1, 1964
Creator: Gschneider, Karl A., Jr.
System: The UNT Digital Library
Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL) (open access)

Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL)

Abstract: This report describes in detail two designs of a nominal 6-kwe Nuclear Power Plant (NPP), one using thermoelectrics for power conversion and the other using the Mercury-Rankine cycle NPP.
Date: February 1, 1965
Creator: Botts, W. V.; Marko, M.; McCourt, P. E.; Keshishian, V.; Piccot, A. R. & Budney, G. S.
System: The UNT Digital Library
Final Design of Sodium-Heated, Modular, Steam Generators for the SCTI (open access)

Final Design of Sodium-Heated, Modular, Steam Generators for the SCTI

Abstract: The following report covers the final design of the modular steam generators.
Date: February 1, 1965
Creator: Casey, D. F.; Hammer, J. J.; Logan, D. & Williams, M. C.
System: The UNT Digital Library
Flux Control for Irradiation Experiments (open access)

Flux Control for Irradiation Experiments

Abstract: This report reviews various means which have been used to control experimental conditions in irradiation experiments, and presents the concept of local flux control.
Date: February 1, 1965
Creator: McCarty, W. K.
System: The UNT Digital Library
Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U-10 wt % Mo Fuel Alloy (open access)

Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U-10 wt % Mo Fuel Alloy

Abstract: A fuel development program has been conducted, to investigate the behavior of U-10 wt% Mo alloy at the fission rates and temperatures anticipated in Core I of the Hallam Nuclear Power Facility.
Date: February 1, 1965
Creator: Willard, R. M. & Schmitt, A. R.
System: The UNT Digital Library
The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1 (open access)

The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1

Abstract: Atomics International conducted a fuel irradiation program to investigate and define the behavior of U-10 Mo fuel at the temperatures and fission rates anticipated in Hallam Nuclear Power Facility (HNPF) Core I.
Date: February 1, 1965
Creator: Schmitt, A. R.; Willard, R. M. & Magnus, D. K.
System: The UNT Digital Library