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Progress Report on Waste Concentration Studies: Engineering Results on the BNL Semi-Works Vapor Filtration Vapor Compression Evaporator (open access)

Progress Report on Waste Concentration Studies: Engineering Results on the BNL Semi-Works Vapor Filtration Vapor Compression Evaporator

Report issued by the Brookhaven National Laboratory discussing progress of waste concentration studies. As stated in the introduction, "the present report covers all experimental hot runs up to the time the still was turned over to the Waste Control Section for intermediate handling of laboratory D waste" (p. 1). This report includes tables, illustrations, and photographs.
Date: August 15, 1951
Creator: Horrigan, R. V.; Fried, H. M.; Manowitz, B.; Kuhl, O.; Baranosky, J. A.; Bellanca, S. et al.
Object Type: Report
System: The UNT Digital Library
Final Report to U.S. Atomic Energy Commission: Low-Temperature Heavy Water Plant (open access)

Final Report to U.S. Atomic Energy Commission: Low-Temperature Heavy Water Plant

From purpose of report: The primary purpose of this report and its appendices is to transmit to the AEC the principal results of the experimental and engineering work done on the low-temperature process and to describe the factors which led to the designs finally adopted.
Date: March 15, 1951
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Zirconium Metal Fines Recovery: Interim Technical Report for May 15, 1950 to December 15, 1950 (open access)

Zirconium Metal Fines Recovery: Interim Technical Report for May 15, 1950 to December 15, 1950

This report covers the laboratory and pilot plant investigation of the reclamation of the low hafnium zirconium fines resulting from the manufacture of zirconium sponge and zirconium crystal bar. The process investigated involved recovery of the zirconium as zirconium tetrachloride, by drying the fines in an atmosphere of nitrogen and subsequent chlorination of the fines with anhydrous hydrogen chloride at temperatures above the sublimation point of the product.
Date: January 24, 1951
Creator: Ogburn, S. C., Jr. & Reader, L. J.
Object Type: Report
System: The UNT Digital Library
An Inexpensive, Wide Range Gamma Ray Geiger Survey Meter (open access)

An Inexpensive, Wide Range Gamma Ray Geiger Survey Meter

From abstract: Detailed information is given on the theory, design, parts specifications and assembly data for a new radiation detector for measurement of ionizing radiations.
Date: January 4, 1951
Creator: LeVine, H. D. & DiGiovanni, H. J.
Object Type: Report
System: The UNT Digital Library
Metallurgy Division Quarterly Progress Report for Period Ending October 31, 1950 (open access)

Metallurgy Division Quarterly Progress Report for Period Ending October 31, 1950

Technical report outlining the rate of production of modified MTR type fuel elements for the Bulk Shielding Facility has proceeded. Includes compatibility test that were started as a guide in the selection of materials suitable for fuel-element fabrication. [From Summary]
Date: February 8, 1951
Creator: Frye, J. H.; Miller, E. C. & Bridges, W. H.
Object Type: Report
System: The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1950 (open access)

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1950

Technical report detailing expansion of the Aircraft Nuclear Propulsion at the Oak Ridge National Laboratory. Major facilities completed at this time were the Shielding Rector, the ANP Critical Facility, and the 86-in. Cyclotron. Outlines further need for radiation damage studies. [From Summary]
Date: February 27, 1951
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, W. B.
Object Type: Report
System: The UNT Digital Library
Calorimetric Calibration of a Graphite Walled, Cavity-Type Ionization Chamber (open access)

Calorimetric Calibration of a Graphite Walled, Cavity-Type Ionization Chamber

Technical report outlining cavity-type ionization chambers with graphite walls that are used to measure heat dissipation in the graphite reflector of the MTR mock-up. Studies the relationship between the ionization occurring in the chamber and the heat generated in the surrounding graphite medium. [From Abstract]
Date: January 23, 1951
Creator: Jenks, G. H.; Breazeale, W. M. & Hairston, J. J.
Object Type: Report
System: The UNT Digital Library
Studies on the Removal of Radioisotopes From Liquid Wastes by Coagulation (open access)

Studies on the Removal of Radioisotopes From Liquid Wastes by Coagulation

Technical report covering work completed on the removal of radioisotopes from water using a calcium phosphate floc as a carrier. This research was performed as part of the Health Physics Waste Disposal Research Section work on the removal of small quantities of radioactivity from large volumes of water. [From Abstract]
Date: January 23, 1951
Creator: Lauderdale, Robert A., Jr.
Object Type: Report
System: The UNT Digital Library
The Corrosion of Various Stainless Steels in Synthetic Waste Solutions (open access)

The Corrosion of Various Stainless Steels in Synthetic Waste Solutions

Technical report describing the tests on types 309, 316, and 347 stainless steel. These steels were tested for a total of 779 to 828 hours in three different synthetic waste solutions. Results shoe that the best all-around corrosion resistance to the test conditions was exhibited by 316 stainless steel, but in one solution 347 stainless steel was more resistant. [From Abstract]
Date: February 12, 1951
Creator: English, James L.
Object Type: Report
System: The UNT Digital Library
Physics Division Quarterly Progress Report for Period Ending September 20, 1950 (open access)

Physics Division Quarterly Progress Report for Period Ending September 20, 1950

Technical report covering experiments to measure the resonance and absorption of neutrons in U238 cylinders. Report also discusses control problems connected to the Bulk Shielding Facility and work on MTR controls.
Date: January 8, 1951
Creator: Sneil, A. H. & Wollan, E. O.
Object Type: Report
System: The UNT Digital Library
Preliminary Study of a Uranium - Bismuth Liquid Fuel Power Reactor L. F. R . 2 (open access)

Preliminary Study of a Uranium - Bismuth Liquid Fuel Power Reactor L. F. R . 2

Technical report and preliminary design calculations describing a type of liquid fuel reactor adaptable for production or breeding on a U-233 cycle based on data at Brookhaven National Laboratory. Describes design calculations for generating significant amounts of power and neutrons by use of uranium-bismuth solutions with fused salts in the reactor system.
Date: April 27, 1951
Creator: Gurinsky, D. H.; Kaplan, I.; Miles, F. T.; Williams, C. & Winsche, W. E.
Object Type: Report
System: The UNT Digital Library
Radioactivity Detected in Precipitation and Settled Dust; April - May 1951 (open access)

Radioactivity Detected in Precipitation and Settled Dust; April - May 1951

Technical report examining the precipitation and obtained samples of settled dust at Brookhaven National Laboratory.
Date: 1951
Creator: Weiss, M. M.
Object Type: Report
System: The UNT Digital Library
A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel by Contact with Fused LiCl-KCl Mixtures (open access)

A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel by Contact with Fused LiCl-KCl Mixtures

Technical report investigating the distribution of rare earth elements between a liquid bismuth-uranium solution and fused KCI-LiCi mixtures. Report warrants further research on the liquid bismuth-uranium-fused salt system due to the benefit of continuous fission removal processes.
Date: July 1, 1951
Creator: Bareis, D. W.
Object Type: Report
System: The UNT Digital Library
Progress Report of Reactor Science and Engineering Department; July 1 - September 30, 1951 (open access)

Progress Report of Reactor Science and Engineering Department; July 1 - September 30, 1951

Technical report covering the classified tests on two types of nuclear reactors of the Department of Reactor Science and Engineering. Outlines tests on heat transfer and hydraulics, fabrication and corrosion studies on the normal water.
Date: 1951
Creator: Brookhaven National Laboratory
Object Type: Report
System: The UNT Digital Library
Plate Efficiency in the Exchange of Deuterium Between Ammonia and Hydrogen (open access)

Plate Efficiency in the Exchange of Deuterium Between Ammonia and Hydrogen

Technical report outlining measurements of the equilibrium in the exchange of deuterium between ammonia and hydrogen and of the kinetics of this reaction. Details a series of tests carried out to measure Murphree plate efficiencies.
Date: December 3, 1951
Creator: Perlman, Morris L. & Bigeleisen, Jacob
Object Type: Report
System: The UNT Digital Library
Reactor Operations Division Monthly Report; November 1951 (open access)

Reactor Operations Division Monthly Report; November 1951

Technical report outlining the downtime given to the Brookhaven National Laboratory nuclear reactor in November compared to previous months.
Date: November 1951
Creator: Powell, R. W.
Object Type: Report
System: The UNT Digital Library
The Concentration of Deuterium by Chemical Exchange Between Hydrogen and Ammonia (open access)

The Concentration of Deuterium by Chemical Exchange Between Hydrogen and Ammonia

Technical report describing the results of the chemical reaction between potassium amide and liquid ammonia and the exchange of hydrogen between hydrogen gas and liquid ammonia. This report finds that the reactions may be sufficiently rapid to be useful for isotope separations on a larger scale.
Date: December 15, 1951
Creator: Perlman, M. L. & Bigeleisen, J.
Object Type: Report
System: The UNT Digital Library
Reactor Operations Division Monthly Report; December 1951 (open access)

Reactor Operations Division Monthly Report; December 1951

Technical report analyzing the down time of the Brookhaven National Laboratory nuclear reactor and resulting changes in reactivity.
Date: December 1951
Creator: Powell, R. W.
Object Type: Report
System: The UNT Digital Library
Criticality Calculations for Hydrogen Moderated Reactors From Microscopic Data (open access)

Criticality Calculations for Hydrogen Moderated Reactors From Microscopic Data

From abstract: "The probability for a fission neutron to escape fast leakage from bare, hydrogen moderated reactors is calculated by a method utilizing only the microscopic cross section of the materials. These results can be employed to determine the effectiveness of other substances in preventing fast neutron leakage. These calculations are carried out for aluminum and iron."
Date: November 29, 1951
Creator: Shapiro, Mathew; Preiser, Stanley & Young, Gale
Object Type: Report
System: The UNT Digital Library
Surface to Mass Dependence of Effective Resonance Integrals for Uranium 238 Cylinders (open access)

Surface to Mass Dependence of Effective Resonance Integrals for Uranium 238 Cylinders

Technical report outlining the determination of the effective resonance integral for U238 as a function of the mass ratio for cylinders of 5/8" to 3" diameter. Also gives a linear approximation of the effective resonance integral with infinite shielding in the form of a function. [From Abstract]
Date: March 20, 1951
Creator: Risser, J. R.; Arfken, G. B., Jr.; Cuykendall, T. R.; Stephenson, R. J. & Caldwell, D. O.
Object Type: Report
System: The UNT Digital Library
A Solvent Extraction Method for Neptunium (237) Analysis (open access)

A Solvent Extraction Method for Neptunium (237) Analysis

Technical report describing a rapid and quantitative radiochemical method for the analysis of neptunium (237). This method is based on the extraction of neptunium (IV) with thenoyl-trifluoracetone in xylene. Neptunium (237) is separated free from other alpha emitters and from non-radioactive interferences, and the method may be readily adapted to remote control. [From Abstract]
Date: July 10, 1951
Creator: Moore, Fletcher L.
Object Type: Report
System: The UNT Digital Library
Chemical Technology Division Pilot Plant Section Report for November, 1950- January, 1951 (open access)

Chemical Technology Division Pilot Plant Section Report for November, 1950- January, 1951

Technical report presenting a summary of the flowsheets, equipment, and progress for the Oak Ridge National Laboratory (ORNL) pilot plant development of the Purex Process and of the ORNL Metal Recovery Program. As of this report, conversion of the Purex pilot plant equipment in Buildings 3019 and 3503 is 90% complete. The building structure for the ORNL Waste Metal Recovery plant had been completed, and 15% of the process equipment had been installed. The first hot runs for this plant were scheduled for June, 1951. [From Abstract; Introduction]
Date: March 8, 1951
Creator: Jackson, H. K.
Object Type: Report
System: The UNT Digital Library
Shielding Reactor Corrosion Studies (open access)

Shielding Reactor Corrosion Studies

Technical report outlining the investigation of corrosion on MTR type fuel elements for the Shielding Reactor in filtered water. Report includes two basic types of protection: element pretreatment by either anodizing or alodizing, and solution control using nitric acid to maintain a pH of 5.5 to 6.5 or the addition of 60 ppm sodium chromate as an inhibitor. [From Abstract]
Date: July 9, 1951
Creator: Olsen, Arnold R.
Object Type: Report
System: The UNT Digital Library
Dry Fluoride Process Status Report (open access)

Dry Fluoride Process Status Report

Technical report outlining how uranium hexaflouride was prepared be the direct combination of irradiated uranium metal with elemental fluorine and subsequently decontaminated by adsorption, filtration, and sublimation on a laboratory scale. Report proposes a survey of other methods of preparing UF6 from uranium metal, a study of adsorption techniques for removing plutonium from UF6, and an investigation of fractional distillation for removing the volatile fission product fluorides from UF6. [From Abstract, Summary]
Date: March 27, 1951
Creator: Leuse, R. E.
Object Type: Report
System: The UNT Digital Library