Expanded Scale Process Development of the Electrolytic Production of Thorium From ThCl$sub 4$ in Externally Heated Electrolytic Cells (open access)

Expanded Scale Process Development of the Electrolytic Production of Thorium From ThCl$sub 4$ in Externally Heated Electrolytic Cells

The commercial feasibility of the electrolytic process for Th production has been demonstrated. The cell produced 7 lb. of good quality metal per hour. A cathode cooling system was developed. The major construction materials, Ni and graphite, were satisfactory. The process yield was 86%. (T.R.H.)
Date: January 15, 1956
Creator: Abraham, L.; Merlub-Sobel, M.; Wyatt, J.L. & Wainer, E.
Object Type: Report
System: The UNT Digital Library
Recommendations for exploration drilling, Lower Wild Horse Point, San Rafael Swell, Emery County, Utah (open access)

Recommendations for exploration drilling, Lower Wild Horse Point, San Rafael Swell, Emery County, Utah

The purpose of the investigation was to locate new uranium ore deposits and sites which are favorable for exploration drilling.
Date: December 15, 1952
Creator: Akright, Robert L.
Object Type: Report
System: The UNT Digital Library
Hanford Laboratories Operation Monthly Activities Report: March 1957 (open access)

Hanford Laboratories Operation Monthly Activities Report: March 1957

This is the monthly report of the Hanford Laboratories Operation, March, 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: April 15, 1957
Creator: Albaugh, E. W.
Object Type: Report
System: The UNT Digital Library
Chemical Research Section Progress Report for January 1950 (open access)

Chemical Research Section Progress Report for January 1950

The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.
Date: February 15, 1950
Creator: Albaugh, F. W.
Object Type: Report
System: The UNT Digital Library
HRT-CP: Results of H{sub 2}O-D{sub 2}O Separation Tests (open access)

HRT-CP: Results of H{sub 2}O-D{sub 2}O Separation Tests

None
Date: July 15, 1957
Creator: Albrecht, W. L.
Object Type: Report
System: The UNT Digital Library
Design Analysis of a Prepackaged Nuclear Power Plant for an Ice Cap Location (open access)

Design Analysis of a Prepackaged Nuclear Power Plant for an Ice Cap Location

Report describing a the design requirements of a proposed nuclear power plant for use on an ice cap.
Date: January 15, 1959
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
Apparent viscosity of neutralized and concentrated raw slurry : TBP HW-no. 4 and HW flowsheet (open access)

Apparent viscosity of neutralized and concentrated raw slurry : TBP HW-no. 4 and HW flowsheet

Report describing how the neutralized aqueous waste from the TBP Metal Recovery Process will be concentrated by evaporation to minimize the requirements for underground storage tank capacity.
Date: August 15, 1950
Creator: Allen, A. W. & Harmon, M. K.
Object Type: Report
System: The UNT Digital Library
Hot-Pressure Bonding of OMR Fuel Plates (open access)

Hot-Pressure Bonding of OMR Fuel Plates

Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Object Type: Report
System: The UNT Digital Library
Effects of Ultraviolet Radiation on Chloroplast Reactions and Plant Metabolism (open access)

Effects of Ultraviolet Radiation on Chloroplast Reactions and Plant Metabolism

This technical report represents a brief survey of work by this project on the effects of ultraviolet radiation (UV) on certain of the photochemical and metabolic properties of rhubarb chard and sugar beet (Beta vulgaris). These plants were selected for this work because for some years they have been used as sources of chloroplasts for Hill reaction studies in this laboratory. Some of this work has appeared as a brief paper.
Date: June 15, 1955
Creator: Anderson, Donald R.; Spikes, John D. & Mayne, Berger C.
Object Type: Report
System: The UNT Digital Library
GAMMA-RAY AND FAST NEUTRON ANNULAR STREAMING EVALUATION THROUGH SODIUM REACTOR EXPERIMENT (SRE)-MARK II CONTROL AND SAFETY ROD ASSEMBLIES (open access)

GAMMA-RAY AND FAST NEUTRON ANNULAR STREAMING EVALUATION THROUGH SODIUM REACTOR EXPERIMENT (SRE)-MARK II CONTROL AND SAFETY ROD ASSEMBLIES

An experimental program was initiated io determine the extent of fast neutron and gamma ray streaming through the SRL Mark II control and safety rods and to evaluate the adequacy of the shielding provided in these control and safety rods. The methods and procedures used to evaluate these problems are routine and proven for determining gamma-ray and fast neutron dosages using radiation sensitive films and gold foils. The final experimental results indicated that no excessive streaming of either gamma rays or fast neutrons is present above or around the SHE Mark II control and safety rods. The analytical attenuation methods used to calculate the fast neutron and gamma-ray streaming dose rates gave results that compared favorably with the experimental data. Even ihough the agreement was favorable, it cannot be concluded that these analyical methods would be equally valid for other annular geometries. Additional experimental work will be necessary in order to establish the validity for performing similar analysis, but the favorable agreement encourages the use of such methods until other methods are determined. (auth)
Date: October 15, 1959
Creator: Anderson, F. D.
Object Type: Report
System: The UNT Digital Library
Investigation of an NACA Submerged Inlet at Mach Numbers from 1.17 to 1.99 (open access)

Investigation of an NACA Submerged Inlet at Mach Numbers from 1.17 to 1.99

Memorandum presenting an investigation conducted with an NACA submerged inlet at Mach numbers from 1.17 to 1.99. Total-pressure ratio, mass-flow ratio, and static pressure distribution along the ramp and main body were obtained at angles of attack of 0 and 6 degrees for a side inlet location. The results showed that the maximum total-pressure ratio attainable with the submerged inlet decreased from 0.83 at a Mach number of 1.17 to 0.52 at a Mach number of 1.99.
Date: September 15, 1952
Creator: Anderson, Warren E. & Frazer, Alson C.
Object Type: Report
System: The UNT Digital Library
HAZARDS SUMMARY REPORT FOR 2-MEGAWATT OPERATION OF THE BATTELLE RESEARCH REACTOR. Special Report (open access)

HAZARDS SUMMARY REPORT FOR 2-MEGAWATT OPERATION OF THE BATTELLE RESEARCH REACTOR. Special Report

The Battelle Research Reactor is a modified pool reactor located in a sparsely settled 500-acre tract owned by Battelle 13 miles west of Columbus, Ohio. The reactor has been operating since October 29, 1956, at power levels up to 1 megawatt. More than 300 megawattdays have been logged on the reactor with most of this operation at a power level of 1 megawatt. No serious incidents have occurred during the operation of the reactor. With only a few modifications the reactor will operate continuously at a power level of 2 megawatts. First, interlock will be added to the safety instrumentation to scram the reactor in the event of significant reduction in the flow rate of the primary coolant. Second, to provide additional margin of safety against the possibility of local boiling occurring in the core, the primary flow rate will be increased to greater than 1500 gpm. Third, a 700-gallon holdup tank will be added to the primary coolant system to allow for decay of the nitrogen16 formed in the coolant as it passes through the core. Holdup will reduce the dose rate at the surface of the pool to 4 mr per hr or less during routine 2-megawatt operation. …
Date: August 15, 1958
Creator: Anno, J. N., Jr.; Plummer, A. M. & Chastain, J. W., Jr.
Object Type: Report
System: The UNT Digital Library
Interim report on the development of a plastic bonded explosive (open access)

Interim report on the development of a plastic bonded explosive

The purpose of this work was to investigate the possibilities of producing a plastic bonded explosive having greater mechanical strength than that of presently existing plastic bonded explosives. This interim report details activities and progress through July 15, 1957.
Date: July 15, 1957
Creator: Archibald, P. B.
Object Type: Report
System: The UNT Digital Library
Reactor Engineering Division Quarterly Report : December 1, 1952 Through February 28, 1953 (open access)

Reactor Engineering Division Quarterly Report : December 1, 1952 Through February 28, 1953

Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, research, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: March 15, 1953
Creator: Argonne National Laboratory. Reactor Engineering Division
Object Type: Report
System: The UNT Digital Library
Reactor Engineering Division Quarterly Report: December 1, 1953 Through March 30, 1954 (open access)

Reactor Engineering Division Quarterly Report: December 1, 1953 Through March 30, 1954

Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: April 15, 1954
Creator: Argonne National Laboratory. Reactor Engineering Division.
Object Type: Report
System: The UNT Digital Library
Reactor Engineering Division Quarterly Report March 1, 1953 through May 31, 1953 (open access)

Reactor Engineering Division Quarterly Report March 1, 1953 through May 31, 1953

Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: June 15, 1953
Creator: Argonne National Laboratory. Reactor Engineering Division.
Object Type: Report
System: The UNT Digital Library
Reactor Engineering Division Quarterly Report September 1, 1952 through November 30, 1952 (open access)

Reactor Engineering Division Quarterly Report September 1, 1952 through November 30, 1952

Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: December 15, 1952
Creator: Argonne National Laboratory. Reactor Engineering Division.
Object Type: Report
System: The UNT Digital Library
Reactor Engineering Division Quarterly Report September 1, 1953 through November 30, 1953 (open access)

Reactor Engineering Division Quarterly Report September 1, 1953 through November 30, 1953

Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: December 15, 1953
Creator: Argonne National Laboratory. Reactor Engineering Division.
Object Type: Report
System: The UNT Digital Library
Reactor Engineering Division Quarterly Report June 1, 1953 through August 31, 1953 (open access)

Reactor Engineering Division Quarterly Report June 1, 1953 through August 31, 1953

Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs (including the Power Breeder Reactor (PBR) and the Central Station Water Reactor (CSWR)), designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: September 15, 1953
Creator: Argonne National Laboratory. Reactor Enginneering Division.
Object Type: Report
System: The UNT Digital Library
Graphical Aids in the Calculation of the Shielding Requirements for Spent U²³⁵ Fuel (open access)

Graphical Aids in the Calculation of the Shielding Requirements for Spent U²³⁵ Fuel

Abstract: The data presented herein, in the form of graphs, can be used to obtain the value of this energy.
Date: November 15, 1957
Creator: Ashley, R. L.
Object Type: Report
System: The UNT Digital Library
Effects on the Inhour Equation for Reactors Fueled with Mixtures of Fissionable Material (open access)

Effects on the Inhour Equation for Reactors Fueled with Mixtures of Fissionable Material

The determination of various parameters such as thermal utilization, resonance escape probability, control rod calibrations and etc. is often accomplished by the measurement of the pile period due to some given perturbation. With the present thoughts being directed towards plutonium fueled reactors, it was felt worthwhile to discuss a few of the basic differences in pile neutron behavior due to the smaller fraction of delayed neutrons per fission of Pu239 and the larger fraction of delayed neutrons per fast fission of U238 than occurs from fission of U235 alone.
Date: June 15, 1956
Creator: Astley, E. R.
Object Type: Report
System: The UNT Digital Library
Some Heat Removal Considerations of The HRT Pressure Vessel During Operation (open access)

Some Heat Removal Considerations of The HRT Pressure Vessel During Operation

None
Date: July 15, 1955
Creator: Aven, R. E.
Object Type: Report
System: The UNT Digital Library
The inhalation of radioactive materials as related to hand contamination (open access)

The inhalation of radioactive materials as related to hand contamination

Tests performed to determine the hazard associated with the inhalation of radioactive materials as the result of smoking with contaminated hands indicate that for dry uranium compounds adhering to the palmar surfaces of the hands, approximately 1.0% of the material may be transferred to a cigarette, and that of this approximately 0.2% may appear in the smoke which is inhaled. Most of the contamination originally placed in a cigarette was found in the ash, and only 11% of the material was not recovered following burning; approximately half of this loss may be attributed to normal losses inherent in the analytical process, the recovery efficiency for which was found by supplementary experiments to be 95%.
Date: September 15, 1953
Creator: Bailey, J.C. & Rohr, R.C.
Object Type: Report
System: The UNT Digital Library
An Investigation at Subsonic Speeds of the Rolling Effectiveness of a Small Perforated Spoiler on a Wing Having 45 Degrees of Sweepback (open access)

An Investigation at Subsonic Speeds of the Rolling Effectiveness of a Small Perforated Spoiler on a Wing Having 45 Degrees of Sweepback

Memorandum presenting an investigation of the rolling effectiveness of a partial-span, perforated spoiler on a wing with 45 degrees of sweepback at Mach numbers from 0.25 to 0.96. The effects of the spoiler on the lift, drag, and pitching moment were also determined. Results regarding Reynolds number, Mach number, and predicted rate of roll are provided.
Date: September 15, 1952
Creator: Bandettini, Angelo
Object Type: Report
System: The UNT Digital Library