The toxicity of X material (open access)

The toxicity of X material

This report addresses toxicity (largely chemical) of Manhattan Project materials from the point of worker protection. Known chemical toxicities of X material (uranium), nitrous fumes, fluorine, vanadium, magnesium, and lime are described followed by safe exposure levels, symptoms of exposure, and treatment recommendations. The report closes with an overview of general policy in a question and answer format.
Date: December 1943
Creator: Ferry, J. L.
System: The UNT Digital Library
Project 9536, metal turnings - fire hazard (open access)

Project 9536, metal turnings - fire hazard

The turnings have proved to be highly inflammable and subject to spontaneous ignition. Several experiments have been conducted at Herring-Hall-Marvin Safe Company, Hamilton, Ohio, and Baker Brothers, Inc., Toledo, Ohio, and in addition there have been a number of accidental fires, of which at least three were spontaneous. Fires of quantities ranging from several pounds to several hundred pounds have been experienced and a number of extinguishers have been tried. Records of this work are available in our files. While the work to date does not constitute an exhaustive survey of the problem, we believe that it is now safe to outline precautionary and protective measures.
Date: August 27, 1943
Creator: unknown
System: The UNT Digital Library
The Production of Uranium Metal by Metal Hydrides Incorporated (open access)

The Production of Uranium Metal by Metal Hydrides Incorporated

Metal Hydrides Incorporated was a pioneer in the production of uranium metal on a commercial scale and supplied it to all the laboratories interested in the original research, before other methods for its production were developed. Metal Hydrides Inc. supplied the major part of the metal for the construction of the first experimental pile which, on December 2, 1942, demonstrated the feasibility of the self-sustaining chain reaction and the release of atomic energy.
Date: January 1, 1943
Creator: Alexander, P. P.
System: The UNT Digital Library
Production of Uranium Metal (open access)

Production of Uranium Metal

Experiments were carried out for the purpose of increasing production, efficiency, and purity of uranium metal. The electrolytic method as described by Driggs and Lilliendahl for the preparation of uranium metal was followed with but little deviation. The yield of metal at the very best was only 50%. The metal powder produced, at times, was very pyrophoric. Methods were found whereby the metal, at least in part, can be made from the oxides with an average yield of about 90%. The small amounts of sludge and slag accumulated in this modified process can readily be re-used in the electrolysis pot and, therefore, an overall yield of 96% can be obtained. Information accumulated from these experiments has been compiled in such a manner as to be readily available for factory use, for patent purposes and for future publication.
Date: February 17, 1943
Creator: Nagy, R.
System: The UNT Digital Library
Production of (Uranium) Tetrafluoride (open access)

Production of (Uranium) Tetrafluoride

Production of tetrafluoride for the month of April was 49,400. New equipment installed late in March operated smoothly and the production was slightly over the rated capacity of the plant. Nickel ends were welded on to the steel reactor tubes to prevent corrosion at the cover joint and possible contamination of the product with iron. The nickel ends will also save considerable repair work on the tube ends. The magnesium trays for some of the reactors are beginning to crack at the sides from frequent straightening. The trays are bent out of shape by the expansion of the product and are reshaped by hammering over a die. Some of the cracks have been repaired by welding but this is not very satisfactory because the welded trays are harder to straighten and often crack again.
Date: May 13, 1943
Creator: Long, K. E. & Swinehart, C. F.
System: The UNT Digital Library
Critical amounts of uranium compounds (open access)

Critical amounts of uranium compounds

None
Date: March 19, 1943
Creator: Konopinski, E.; Metropolis, N.; Teller, E. & Woods, L.
System: The UNT Digital Library
PROGRESS REPORT ON METALLURGY OF TUBALLOY TO UNIVERSITY OF CHICAGO (open access)

PROGRESS REPORT ON METALLURGY OF TUBALLOY TO UNIVERSITY OF CHICAGO

None
Date: July 10, 1943
Creator: unknown
System: The UNT Digital Library
DECONTAMINATION OF PRODUCT BY ADSORPTION ON TAILOR-MADE INORGANIC ADSORBENTS (open access)

DECONTAMINATION OF PRODUCT BY ADSORPTION ON TAILOR-MADE INORGANIC ADSORBENTS

None
Date: March 1, 1943
Creator: Russell, E.R.; Adamson, A.W.; Schubert, J. & Boyd, G.E.
System: The UNT Digital Library
PROGRESS REPORT ON METALLURGY OF TUBALLOY TO UNIVERSITY OF CHICAGO (open access)

PROGRESS REPORT ON METALLURGY OF TUBALLOY TO UNIVERSITY OF CHICAGO

None
Date: June 10, 1943
Creator: unknown
System: The UNT Digital Library
The Electrolytic Reduction-pH Control Method of Separation of U From Contaminants (open access)

The Electrolytic Reduction-pH Control Method of Separation of U From Contaminants

None
Date: July 28, 1943
Creator: Wagner, E. L.
System: The UNT Digital Library
PROCESSING OF AFRICAN ORES (open access)

PROCESSING OF AFRICAN ORES

None
Date: May 1, 1943
Creator: Brimm, E.O.
System: The UNT Digital Library
Metal Hydrides Final Report (open access)

Metal Hydrides Final Report

None
Date: July 26, 1943
Creator: Alexander, P. P.
System: The UNT Digital Library
Fission Spectrum (open access)

Fission Spectrum

Measurements of the spectrum of the fission neutrons of 25 are described, in which the energy of the neutrons is determined from the ionization produced by individual hydrogen recoils. The slow neutrons producing fission are obtained by slowing down the fast neutrons from the Be-D reaction of the Stanford cyclotron. In order to distinguish between fission neutrons and the remaining fast cyclotron neutrons both the cyclotron current and the pusle amplifier are modulated. A hollow neutron container, in which slow neutrons have a lifetime of about 2 milliseconds, avoids the use of large distances. This method results in much higher intensities than the usual modulation arrangement. The results show a continuous distribution of neutrons with a rather wide maximum at about 0.8 MV falling off to half of its maximum value at 2.0 MV. The total number of netrons is determined by comparison with the number of fission fragments. The result seems to indicate that only about 30% of the neutrons have energies below .8 MV. Various tests are described which were performed in order to rule out modification of the spectrum by inelastic scattering.
Date: August 18, 1943
Creator: Bloch, F. & Staub, H.
System: The UNT Digital Library
Brown Oxide by-product Recovery. Part V (open access)

Brown Oxide by-product Recovery. Part V

None
Date: October 28, 1943
Creator: Barnes, J. W.; Copenhafer, D. R.; Furnas, T. C.; Opie, J. V. & Reid, G. C.
System: The UNT Digital Library
Progress Report on Metallurgy of Tuballoy to University of Chicago (open access)

Progress Report on Metallurgy of Tuballoy to University of Chicago

None
Date: May 10, 1943
Creator: unknown
System: The UNT Digital Library
Brown Oxide by-Product Recovery. Part  I (open access)

Brown Oxide by-Product Recovery. Part I

The objective of this report is to investigate the feasibility of obtaining uranium from the carnotite sludge in such a form as o permit its use in the brown oxide purification process.
Date: July 1, 1943
Creator: Copenhafer, D. & Oppold, W. A.
System: The UNT Digital Library
THE PHYSICAL PROPERTIES OF URANIUM HEXA-FLUORIDE (open access)

THE PHYSICAL PROPERTIES OF URANIUM HEXA-FLUORIDE

None
Date: July 1, 1943
Creator: Kirshenbaum, I.
System: The UNT Digital Library
Investigation of the Photochemical Method for Uranium Isotope Separation (open access)

Investigation of the Photochemical Method for Uranium Isotope Separation

To find a process for successful photochemical separation of isotopes several conditions have to be fulfilled. First, the different isotopes have to show some differences in the spectrum. Secondly, and equally important, this difference must be capable of being exploited in a photochemical process. Parts A and B outline the physical and chemical conditions, and the extent to which one might expect to find them fulfilled. Part C deals with the applicability of the process.
Date: July 10, 1943
Creator: Urey, H.C.
System: The UNT Digital Library
Summarizing Report of Investigations Relating to Uranium Covering the Period September 1, 1942 to April 15, 1943 (open access)

Summarizing Report of Investigations Relating to Uranium Covering the Period September 1, 1942 to April 15, 1943

None
Date: June 1, 1943
Creator: Kraus, C. A.
System: The UNT Digital Library
METALLURGY OF TUBALLOY URANIUM . Progress Report to University of Chicago (open access)

METALLURGY OF TUBALLOY URANIUM . Progress Report to University of Chicago

None
Date: April 10, 1943
Creator: unknown
System: The UNT Digital Library
Density of Solid Hex Uf$Sub 6$ Near the Triple Point, and the Expansivity of the Liquid From the Triple Point to 92 C (open access)

Density of Solid Hex Uf$Sub 6$ Near the Triple Point, and the Expansivity of the Liquid From the Triple Point to 92 C

The report addresses the density of solid hex near the Triple and the expansivity of the liquid from the triple point.
Date: February 25, 1943
Creator: Wechsler, Martin T. & Hoge, Harold J.
System: The UNT Digital Library
Experimental Physics Division of the Los Alamos Project. Progress report No. 4 (open access)

Experimental Physics Division of the Los Alamos Project. Progress report No. 4

Included in this semi-monthly report written in 1943 are progress with neutron beams, neutron absorption in enriched materials, equipment operation and maintenance reports of the cyclotron neutron source facility, and instrumentation maintenance activities of individuals in the cyclotron group. (GHT)
Date: September 1, 1943
Creator: unknown
System: The UNT Digital Library
Project 9336: Hanford-retention basin and effluent dilution (open access)

Project 9336: Hanford-retention basin and effluent dilution

This report discusses effluent dilution of a retention basin at the Hanford Works in 1943. (JL)
Date: September 1, 1943
Creator: Worthington, H.
System: The UNT Digital Library
Retention basins---Building 107, 100 Areas (open access)

Retention basins---Building 107, 100 Areas

None
Date: January 23, 1943
Creator: Lauder, D. H. & Gross, C. N.
System: The UNT Digital Library