Uranium Possibilities in Arizona Exclusive of the Colorado Plateau (open access)

Uranium Possibilities in Arizona Exclusive of the Colorado Plateau

From introduction: This report represents an effort to assemble, relate, and evaluate available information about possible primary uranium mineralization in the state of Arizona. This is the initial step in preparation for a system ratio field study of the state.
Date: December 1949
Creator: Wright, Robert J.
System: The UNT Digital Library
Fast Neutron Irradiation Procedure (open access)

Fast Neutron Irradiation Procedure

This report discusses a series of investigations for biological and biochemical study of chronic exposures of animals to neutrons through an irradiation procedure.
Date: 1949
Creator: McDonald, Ellice, 1876-
System: The UNT Digital Library
Flow Meter for Measuring Air-Flow through Special Hoods : Final Report (open access)

Flow Meter for Measuring Air-Flow through Special Hoods : Final Report

This report describes the flow meter for measuring air-flow rate through special hoods that allow the decrease in flow rate.
Date: March 24, 1949
Creator: McEwen, M.
System: The UNT Digital Library
Homogeneous Reactor Preliminary Process Design Report (open access)

Homogeneous Reactor Preliminary Process Design Report

"The following report is meant to serve a two fold purpose. First, it is the quarterly report of the homogeneous reactor project for the Technical Division of Oak Ridge National Laboratory. Secondly, it is a description and general feasibility discussion of a 200-1000 K.W. pilot model, homogeneous reactor."
Date: December 28, 1949
Creator: Graham, C. B.; Secoy, C. H.; Spiewak, Irving; Taylor, E. H.; Weinberg, Alvin Martin, 1915-2006; Winters, C. E. et al.
System: The UNT Digital Library
Design of a Bubble-Cap Column to Replace Nitric Acid Concentrator (open access)

Design of a Bubble-Cap Column to Replace Nitric Acid Concentrator

The following document presents designs and blueprints to the bubble-cap column built to replace a nitric acid concentrator.
Date: August 22, 1949
Creator: Wallingford, H.
System: The UNT Digital Library
Mound Laboratory Liquid Waste Disposal Research Quarterly Report for April 1 - June 30, 1949 (open access)

Mound Laboratory Liquid Waste Disposal Research Quarterly Report for April 1 - June 30, 1949

The following report is a quarterly report by the Monsanto Chemical Company for liquid waste disposal research, covering the period between April 1 to June 30, 1949.
Date: July 1, 1949
Creator: Monsanto Chemical Company
System: The UNT Digital Library
Investigation of Cementitious Materials for Possible Use in Concretes for Pile Shielding (open access)

Investigation of Cementitious Materials for Possible Use in Concretes for Pile Shielding

From introduction: "The present report reviews the work conducted on the development of new cements other than magnesium oxychloride during the period from August, 1943, to October 1949. As in the previous reports, the total water contents reported represent the hydrogen combined as water and that which may be combined as a compound other than water."
Date: September 1949
Creator: Synder, M. J.; Burkart, C. A. & Clegg, John W.
System: The UNT Digital Library
Magnesium Oxychloride Cements and Concretes for Pile Shielding (open access)

Magnesium Oxychloride Cements and Concretes for Pile Shielding

From introduction: "The present report covers the results of an extended investigation of magnesium oxychloride cements and concretes. In this study the effects of the composition of the cement or concrete on its physical and mechanical properties were determined. In addition, the stability of the mixes was observed."
Date: August 1949
Creator: Snyder, M. J. & Pavlish, A. E.
System: The UNT Digital Library
Power Recovery at Brookhaven ; Report No. 1 (open access)

Power Recovery at Brookhaven ; Report No. 1

From introduction: "This is the first report on the study made of the possible power recovery without excessive cost, from the operation of the Brookhaven reactor."
Date: June 16, 1949
Creator: Lucke, Charles Edward
System: The UNT Digital Library
Dissolution of Uranium Tetrafluoride (open access)

Dissolution of Uranium Tetrafluoride

"Five new dissolution processes for uranium tetrafluoride are discussed-the NH4OH-H2O2 method, the H2SC4 - (NH4)2S2O8 method, the AlCl3 method, the NaAlcl method, and the Al (NO3)3.9E2O method. It is concluded that NaAlCl4 and Al(NO3)3.9H2O are preferable to the other agents, especially with regard to rate of dissolution and ease of manipulation."
Date: 1949
Creator: Calkins, V. P. & Susano, C. D.
System: The UNT Digital Library
Progress Report on Carnotite Studies; Carbonate Processes: September 1949 (open access)

Progress Report on Carnotite Studies; Carbonate Processes: September 1949

This is a progress report on the carbonate process, compiled by the chemical development department of the Carbide and Carbon Chemicals Corporation's Y-12 plant, covering the month of September, 1949. In the previous month, the problem of immediate interest to the Monticello operation were listed. Projects that were left incomplete during that time were continued during this month, as well as a brief investigation of the process in which raw ore is leached with sodium carbonate, the sands and slime separated, the sands leached with acid, and the slimes roasted in a pellitized form.
Date: October 6, 1949
Creator: Brown, K. B. & Coleman, C. F.
System: The UNT Digital Library
Level and Leak Indicators (open access)

Level and Leak Indicators

The following report provides results taken from a sodium level indicator developed at Sacandaga using electrical resistance as the principle.
Date: December 20, 1949
Creator: Vandenberg, L. B.
System: The UNT Digital Library
Direct Current Electromagnetic Pumps (open access)

Direct Current Electromagnetic Pumps

Abstract: "A number of direct current conduction type electromagnetic pumps for liquid metals were constructed. Pumping capacities of over 400 gpm and efficiencies of over 50 percent were obtained. NaK alloy at temperatures up to 400 C was used in the test. The large currents required were obtained from rectifiers or from a homopolar generator constructed for the purpose."
Date: October 25, 1949
Creator: Barnes, A. H.; Smith, F. A. & Whitham, G. K.
System: The UNT Digital Library
The Densities of Tributyl Phosphate - Carbon Tetrachloride Solutions Containing Uranium and Nitric Acid (open access)

The Densities of Tributyl Phosphate - Carbon Tetrachloride Solutions Containing Uranium and Nitric Acid

The following report provides the analysis of a large number of unreported data--taken during a study described in report HW-15230--containing density values obtained for solutions of uranium and nitric acid in tributyl phosphate-carbon tetrachloride solutions.
Date: December 20, 1949
Creator: Moore, Robert Lee
System: The UNT Digital Library
Bare Beryllium Extrusion Using Graphite Introductory Cones (open access)

Bare Beryllium Extrusion Using Graphite Introductory Cones

The following document describes the process of rare beryllium extrusion using graphite introductory cones with the purpose of finding a lubricant which would decrease excessive friction between the billet and prose parts.
Date: June 28, 1949
Creator: Arnold, Samuel V.
System: The UNT Digital Library
Extrusion at Revere Copper and Brass Inc., March 1, 1949 (open access)

Extrusion at Revere Copper and Brass Inc., March 1, 1949

The following report discusses the process of several sections of beryllium where 3.018" squares 40" in length can be machined, and six sound 8.0" diameter billets and three trial billets containing casting defects can be extruded.
Date: 1949
Creator: Arnold, Samuel V.
System: The UNT Digital Library
Materials Testing Reactor Project: Coffins and Coffin Handling, Design Report No. 21 (open access)

Materials Testing Reactor Project: Coffins and Coffin Handling, Design Report No. 21

The following report discusses special shielded containers, called coffins, that are used for removing beam hole plugs from the reactor, transporting them to plug storage and inserting them therein. This report focuses on the handling of dummy and experimental beam hole plugs.
Date: December 5, 1949
Creator: Paleczny, M. P.
System: The UNT Digital Library
Materials Testing Reactor Project : Addendum to Reactor Building Report, Design Report No. 26A (open access)

Materials Testing Reactor Project : Addendum to Reactor Building Report, Design Report No. 26A

"Changes, corrections and additions to the original report are included in this addendum. These are brought about by further development of the design by Blaw-Knox, ANL and ORNL. The changes are listed in accordance with the main headings, pages and paragraphs to which they apply."
Date: November 17, 1949
Creator: Link, L. E. & Guzik, R. F.
System: The UNT Digital Library
Materials Testing Reactor Project : Reactor Building Wing, Design Report No. 27 (open access)

Materials Testing Reactor Project : Reactor Building Wing, Design Report No. 27

The following report describes the design and construction of the reactor building wing, designed to attach to the reactor building for the Argonne National Laboratory.
Date: October 12, 1949
Creator: Guzik, R. F. & Link, L. E.
System: The UNT Digital Library
Materials Testing Reactor Project : Addendum to Reactor Building Wing Report, Design Report No. 27A (open access)

Materials Testing Reactor Project : Addendum to Reactor Building Wing Report, Design Report No. 27A

"Changes, corrections and additions to the original report are included in this addendum. These are brought about by further development of the design by Blaw-Knox, AHL and ORNL. The changes in the original wiritings are listed below in accordance with the main headings, pages and paragraphs to which they apply. Following this is a list of the contemplated personnel in the MTR program. This listing sets out the number of offices and the office furniture requirements. Also numbers for lockers, showers, toilets and rest rooms are set forth. Although the listing includes all major buildings planned for the site, it is included here since the reactor building wing is more markedly influenced by office requirements."
Date: November 25, 1949
Creator: Link, L. E. & Guzik, R. F.
System: The UNT Digital Library
Materials Testing Reactor Project : Reactor Building, Design Report No. 26 (open access)

Materials Testing Reactor Project : Reactor Building, Design Report No. 26

The following report discusses the building design and development of the reactor building, Building 1105, for Argonne National Laboratory, that is meant to house the reactor.
Date: October 10, 1949
Creator: Guzik, R. F. & Link, L. E.
System: The UNT Digital Library
Optical Properties of Three Uranium Phosphates (open access)

Optical Properties of Three Uranium Phosphates

Abstract: "Crystal system, crystal habit, and principal refractive indices, of uranyl hydrogen phosphate tetrahydrate, uranyl ammonium phosphate trihydrate, and uranyl phosphate tetrahydrate are reported. A procedure for differentation of these three compounds using this data was developed."
Date: September 30, 1949
Creator: Harris, W. W. & Scott, Roberta H.
System: The UNT Digital Library
Two Year Feeding Test (open access)

Two Year Feeding Test

The following report presents the results of the second year of the two-year feeding tests of uranium compounds to 50 male and 50 female rats.
Date: 1949
Creator: Maynard, Elliott A.; Downs, William L. & Hodge, Harold C.
System: The UNT Digital Library
Uranium Tetrafluoride (UF₄) (open access)

Uranium Tetrafluoride (UF₄)

The following report analyzes the effects of uranium tetrafluoride on male and female rats within a two-year period.
Date: 1949
Creator: Maynard, Elliott A.
System: The UNT Digital Library