Fluorocarbons and Fluoroorganic Compounds. Section 2 (open access)

Fluorocarbons and Fluoroorganic Compounds. Section 2

None
Date: August 1, 1948
Creator: Gabbard, J. L.; Gibson, J. D.; Faloon, A. V.; Rapp, K. E.; Frey, S. E. & Walker, D. V.
Object Type: Report
System: The UNT Digital Library
Formation of Methyl Borate From the Methyl Borate-Boron Fluoride Complex (open access)

Formation of Methyl Borate From the Methyl Borate-Boron Fluoride Complex

None
Date: September 1, 1945
Creator: McCaulay, D. A. & Rittschof, W. L.
Object Type: Report
System: The UNT Digital Library
Formation of the 50-Year Element 94 from Deuteron Bombardment of U$sup 23$$sup 8$ (open access)

Formation of the 50-Year Element 94 from Deuteron Bombardment of U$sup 23$$sup 8$

None
Date: June 1, 1942
Creator: Kennedy, J.W.; Perlman, M.L.; Segre, E. & Wahl, A.C.
Object Type: Report
System: The UNT Digital Library
Gamma scale chemistry progress report (open access)

Gamma scale chemistry progress report

This report considers the work done during the year ending June 30, 1948, present work being done and future plans on the determination of formulas, methods of preparation, and properties of as many compounds of postum as possible. An experimental approach to such a research problem on the element postum requires that procedures which may be used deal with ultramicro quantities of material. Such procedures on an ultramicro or gamma scale require special techniques by personnel trained in manipulating these small quantities of radioactive material. Equipment which may be used varies with the experiment considered. Often new apparatus must be developed or equipment previously developed and used in some other experiment must be modified. This generalized research problem is subdivided in the {open_quotes}Research Problems Outline{close_quotes}. The presentation of a survey of these research problems with reference to the outline for the year ending June 30, 1948 is a critical review of the work done by the Gamma Scale Chemistry Group as well as a consideration of future plans. The course which these future plans may follow will depend upon information which may be obtained when carrying out planned experiments.
Date: June 1, 1948
Creator: Economides, M.; Estabrook, E. & Joy, E.F.
Object Type: Report
System: The UNT Digital Library
GAS COOLED PEBBLE PILES (open access)

GAS COOLED PEBBLE PILES

None
Date: August 1, 1947
Creator: Amorosi, A.
Object Type: Report
System: The UNT Digital Library
General chemistry progress report (open access)

General chemistry progress report

This document is a de-classified July 1948 General Chemistry Progress Report from Monsanto Chemical`s Mound facility. Detailed discussions of numerous studies of Postum compounds are included in this report, and experimental data on various chemical and physical properties of these compounds are given.
Date: July 1, 1948
Creator: Barth, S.; Ford, M. & Dismore, P.
Object Type: Report
System: The UNT Digital Library
General chemistry progress report (open access)

General chemistry progress report

This document is a de-classified August 1948 General Chemistry progress report from Monsanto Chemical`s Mound facility. General chemical properties of Postum compounds are discussed, and experimental data on these properties are presented.
Date: August 1, 1948
Creator: Barth, S.; Ford, M. & Dismore, P.
Object Type: Report
System: The UNT Digital Library
General chemistry progress report (open access)

General chemistry progress report

Decomposition potentials of bismuth solutions of 1.037 and 0.509 grams of the metal per 100 ml. of 1.5 nitric acid were found to be -0.06 and -0.09 volts to N.C.E. These results confirm previous values and indicate that bismuth will not be reduced from production solutions at the potential of the normal calomel electrode. A summary of research in progress, completed, or anticipated is given.
Date: June 1, 1948
Creator: Barth, S.; Ford, M. & Dismore, P.
Object Type: Report
System: The UNT Digital Library
A GENERAL STUDY OF THE DISTRIBUTION OF IMPURITIES IN REMELTED URANIUM METAL AND RELATED SUBJECTS (open access)

A GENERAL STUDY OF THE DISTRIBUTION OF IMPURITIES IN REMELTED URANIUM METAL AND RELATED SUBJECTS

None
Date: April 1, 1946
Creator: Oppold, W.A.
Object Type: Report
System: The UNT Digital Library
Graphs Showing Neutron Cross Sections as Functions of A, Z, or N (open access)

Graphs Showing Neutron Cross Sections as Functions of A, Z, or N

None
Date: September 1, 1948
Creator: Haines, G. & Way, K.
Object Type: Report
System: The UNT Digital Library
Group Meeting with Rand and North American Aviation (open access)

Group Meeting with Rand and North American Aviation

None
Date: July 1, 1948
Creator: Plesset, E. H. & Star, C.
Object Type: Report
System: The UNT Digital Library
Hanford Engineer Works technical manual (open access)

Hanford Engineer Works technical manual

The uranium metal, as discharged from the piles in the 100 Areas, contains the alpha emitting product, plutonium, in concentration in the neighborhood of 150--250 grams per metric ton, along with similar amounts of beta and gamma fission elements. It is the purpose of the Separations Plant to effect the separation of this product from the uranium metal and fission elements, and to prepare a concentrated, relatively pure solution of plutonium nitrate as the final product of the Hanford Plant. This section of the manual discusses the chemistry of the separations process, describes the buildings and equipment provided for carrying out the various steps in the operation, and presents the detailed operating procedures used. There are included, in many instances, references to other documents presenting a more detailed view of a specific point in the process.
Date: May 1, 1944
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Health and safety conference (open access)

Health and safety conference

This report provides a summary of the Health and Safety Conference held April 1948 at Chicago, Illinois. Representatives of Argonne National Laboratory, Rochester University, University of California Radiation Laboratory, Los Alamos Scientific Laboratory, New York Memorial Hospital, as well as a Canadian group and an United Kingdom group. Many topics were discussed some of which were plutonium in urine, toxicity of beryllium, and relative toxicity of radioelements.
Date: April 1, 1948
Creator: Rudolph, D.C.
Object Type: Article
System: The UNT Digital Library
THE HEAT TRANSFER AND FLOW FRICTION PERFORMANCE OF THREE COMPACT PLATE-FIN HEAT EXCHANGER SURFACES. Technical Report No. 7 (open access)

THE HEAT TRANSFER AND FLOW FRICTION PERFORMANCE OF THREE COMPACT PLATE-FIN HEAT EXCHANGER SURFACES. Technical Report No. 7

None
Date: December 1, 1949
Creator: Kays, W. M.
Object Type: Report
System: The UNT Digital Library
HIGH FLUX REACTOR FUEL ASSEMBLIES VIBRATION AND WATER FLOW. Problem Assignment No. TX5-12 (open access)

HIGH FLUX REACTOR FUEL ASSEMBLIES VIBRATION AND WATER FLOW. Problem Assignment No. TX5-12

None
Date: May 1, 1948
Creator: Stromquist, W.K. & Sisman, O.
Object Type: Report
System: The UNT Digital Library
High-Frequency Pulse Generator (open access)

High-Frequency Pulse Generator

None
Date: July 1, 1947
Creator: Ohmart, P. E.
Object Type: Report
System: The UNT Digital Library
Impregnation of Graphite With Uranium Compounds for Use as Fuel Rod Materials (open access)

Impregnation of Graphite With Uranium Compounds for Use as Fuel Rod Materials

A process hns been developed for impregnating graphite with U/sub 3/O/ sub 8/ in connection with the proposed use of such material for fuel rod elements in the Daniels' High Temperature Pile. The process as developed consists of five steps: Fabrication of the graphite in the desired shape; Pretreatment of the graphite by boiling in water and then firing in helium at 800 deg C; Impregnating the graphite by first evacuating the pretreated material and then admitting an aqueous uranyl nitrate solution whose concentration is etermined by the final uranium content desired in the raphite; Drying the impregnated graphite slowly under quilibrium conditions; and Conversion of the uranyl itrate to U/sub 3/O/sub 8/ by firing in helium at 800 deg C. By this process fuel rod elements have been made which contain as much as 19% U/sub 3/O/sub 8/ distributed uniformly throughout the graphite. The considerations leading to the choice of this process are discussed in this report, together with the alternate procedures which were investigated. (auth)
Date: February 1, 1948
Creator: Kanter, M.A.
Object Type: Report
System: The UNT Digital Library
Index to Lexington Project Reports (open access)

Index to Lexington Project Reports

None
Date: November 1, 1948
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Interaction of Neutrons with Electrons in Bismuth (open access)

Interaction of Neutrons with Electrons in Bismuth

None
Date: December 1, 1948
Creator: Rainwater, L. J.; Rabi, I. I. & Havens, W. W., Jr.
Object Type: Report
System: The UNT Digital Library
Interium Report on An Exact Analysis of a Limited Plane Plasma in a Magnetic Field (open access)

Interium Report on An Exact Analysis of a Limited Plane Plasma in a Magnetic Field

Prior analyses of a plasma in a magnetic field have been limited, as far as the writer is aware, to cases in which the relative change in field over the orbital distance and the relative change in ion concentration are both small, or in which the relations have been viewed in a purely hydrodynamical way. The first approach excludes cases which can be of considerable interest, for it fails for a plasma edge. The second loses all sight of the structure imposed by the orbital motions.
Date: January 1, 1947
Creator: Tonka, Lewi
Object Type: Report
System: The UNT Digital Library
An Interpretation of the Isotopic Separation in the Distillation of Methyl Ether-Boron Fluoride Complex (open access)

An Interpretation of the Isotopic Separation in the Distillation of Methyl Ether-Boron Fluoride Complex

None
Date: October 1, 1945
Creator: McCaulay, D. A.
Object Type: Report
System: The UNT Digital Library
AN INVESTIGATION OF METHODS FOR THE RECOVERY OF URANIUM FROM RESIDUES OBTAINED DURING THE MANUFACTURE OF PURE URANIUM DIOXIDE (open access)

AN INVESTIGATION OF METHODS FOR THE RECOVERY OF URANIUM FROM RESIDUES OBTAINED DURING THE MANUFACTURE OF PURE URANIUM DIOXIDE

None
Date: April 1, 1946
Creator: Reid, G.C.
Object Type: Report
System: The UNT Digital Library
Investigation of the System Methyl Ether and Methyl Borate-Boron Fluoride Complex (open access)

Investigation of the System Methyl Ether and Methyl Borate-Boron Fluoride Complex

None
Date: August 1, 1945
Creator: McCaulay, D. A. & Rittschof, W. L.
Object Type: Report
System: The UNT Digital Library
Investigation of the use of a recycle stream to mediate hydrogen transfer to improve the conversion of eastern oil shale to liquid products (open access)

Investigation of the use of a recycle stream to mediate hydrogen transfer to improve the conversion of eastern oil shale to liquid products

The processing of eastern oil shale has long been known to require the addition of hydrogen to increase the oil yield. Several researchers, have investigated the use of both high pressure hydrogen and hydrogen donor solvents. Much of the donor solvent work has used pure,compounds such as tetralin and has not addressed the use of-a more realistic solvent such as one derived from the production process itself. The work reported herein is for the research Task 1.2.2, Process Studies, in the Annual Project Plan, October l, 1990--September 30, 1991, of the Cooperative Agreement. In the study, a shale oil-derived, recycle oil was used to mediate the transfer of hydrogen to eastern oil shale. The work was divided into two main parts which correspond to the two main portions of the Hydrogen-Extraction (H-E{trademark}) process: (1) the shale oil extraction which involves the use of a donor solvent to aid in the extraction of the shale oil and (2) the regeneration of the donor solvent to a hydrogen-rich state ready for recycle. The results of the investigation to evaluate shale oil extraction using a shale oil-derived donor solvent suggest that temperature had the, greatest effort on organic conversion. At a temperature of …
Date: June 1, 1944
Creator: Barbour, F. A.; Guffey, F. D.; Thomas, K. P. & Blake, R. F.
Object Type: Report
System: The UNT Digital Library