Metallurgical Laboratory, Physics and Metallurgy Division, Report for the Month of February 1946 (open access)

Metallurgical Laboratory, Physics and Metallurgy Division, Report for the Month of February 1946

Technical report with short reports from the (A) Crystal Structure Section ; (B) Mass Spectroscopy Section ; and (C) Metallurgy Section.
Date: February 28, 1946
Creator: Zachariasen, William H. (William Houlder), 1906-1979; Dempster, Arthur Jeffrey & Foote, Frank G. (Frank Gale), 1906-
Object Type: Report
System: The UNT Digital Library
Acute Histopathological Effects of Single Doses of Slow Neutrons on Mice (open access)

Acute Histopathological Effects of Single Doses of Slow Neutrons on Mice

The following report provides information conducted during histological observations made on the anatomy of female mice who have been exposed to 400 arbitrary units of slow neutrons.
Date: February 5, 1947
Creator: Snider, R.
Object Type: Report
System: The UNT Digital Library
The Coprecipitation of Thorium and Uranium Peroxides (open access)

The Coprecipitation of Thorium and Uranium Peroxides

From introduction: This report is concerned primarily with the coprecipitation phenomenon and its application to plant problems.
Date: February 20, 1946
Creator: Grieger, P. F. & Larson, C. E.
Object Type: Report
System: The UNT Digital Library
Effect of Radiation on Television Equipment : Final Report (open access)

Effect of Radiation on Television Equipment : Final Report

The following report follows a test with the purpose of determining the effect upon image fidelity by exposing a television camera to high intensity radiation over an extended period. Provided later in the report are notes on the design of the utiliscope camera used for these tests due to notable design features.
Date: February 7, 1950
Creator: White, H. J.
Object Type: Report
System: The UNT Digital Library
Recovery of Uranium From Oil Distillation Residue (open access)

Recovery of Uranium From Oil Distillation Residue

Abstract: The complete development of an effective process for recovery of the uranium in the residues from distillation of used Kinney and diffusion pump oils or similar oils is described. After considerable study and experimentation with several methods, a successful procedure has been developed. The recommended procedure embodies solution of the residues in trichlorethylene followed by extraction with nitric acid. Recovery of uranium is better than 99 percent effective and the method may be applied directly to contaminated oils as well as to their distillation residues.
Date: February 24, 1947
Creator: Lee, J. E.; Aikin, L. M. & Susano, C. D.
Object Type: Report
System: The UNT Digital Library
Laboratory Studies of the Pentaether Process for the Recovery and Decontamination of Uranium (open access)

Laboratory Studies of the Pentaether Process for the Recovery and Decontamination of Uranium

The following document reports the process of the recovery and decontamination of uranium using pentaether as the solvent extraction agent in a continuous flow system.
Date: February 16, 1951
Creator: Hicks, T. E.; Mayer, P. C. & Crandall, Howard William, 1921-1990
Object Type: Report
System: The UNT Digital Library
Separation of Tuballoy From Tantalum by Chlorination Distillation Process (open access)

Separation of Tuballoy From Tantalum by Chlorination Distillation Process

Abstract: Tuballoy can be effectively separated from tantalum filaments by chlorination of the filaments and subsequent distillation and condensation of tantalum chloride. Apparatus for chlorination of filaments and distillation separation in one unit is under consideration. Chemical methods of separation of tuballoy from distillation residues are being tested.
Date: February 6, 1946
Creator: Adams, R. H.; Rogers, J. A.; Wagner, E. L. & Miller, A. J.
Object Type: Report
System: The UNT Digital Library
The Methods of Preparing Anhydrous Tuballoy Tetrachloride (open access)

The Methods of Preparing Anhydrous Tuballoy Tetrachloride

Abstract: "A survey report of the known production and experimental methods for the preparation of anhydrous tuballoy tetrachloride with references of each method."
Date: February 1946
Creator: Wagner, E. L.
Object Type: Report
System: The UNT Digital Library
The Preservation of Fluorescence Standards (open access)

The Preservation of Fluorescence Standards

Report discussing the practice of using methyl methacrylate as a coating for platinium dishes in fluorescence method of uranium analysis. The experimental procedure described in this report to evaluate this practice indicates that the sample would be sufficiently protected from contamination and would not need to be stored in a desiccator.
Date: February 15, 1946
Creator: Grotta, H. M.
Object Type: Report
System: The UNT Digital Library
Specifications for the Freezing Point Method for Determination of the Amount of HF in UF₆ (open access)

Specifications for the Freezing Point Method for Determination of the Amount of HF in UF₆

From introduction: "You will find enclosed the specifications for the freezing point method for determination of the amount of HF in UF₆. The specification for cleaning new shipping containers is also included."
Date: February 26, 1944
Creator: Priest, Homer F.
Object Type: Report
System: The UNT Digital Library
The Probability and Extent of a Fission Product Release From a Power Reactor (open access)

The Probability and Extent of a Fission Product Release From a Power Reactor

Report discussing both the probability of having a reactor accident that would release fission products, as well as the probable extent of the release of the products. This information, along with the contents of the fission products themselves, are based on statistical analysis and educated guesses.
Date: February 4, 1956
Creator: Fleck, Joseph A., Jr.
Object Type: Report
System: The UNT Digital Library
Pump-Down Times for the β⁺ Ray and Felix Experiments (open access)

Pump-Down Times for the β⁺ Ray and Felix Experiments

"The e-folding time for the free-molecule pump-out time of the vacuum tank used for the β⁺ ray experiment (N¹⁹ at 20°C) is found to be of the order of 46 millisec, and that used for the Felix experiment (D₂ at 20°C) of the order of 12 millisec. In the Felix tank a particle bounces off of the walls on the average about 30 times before escaping, hence a "getter" material coated on the walls of the tube should result in a slightly more rapid pump-out time."
Date: February 4, 1958
Creator: Gibson, Gordon & Newcomb, William A.
Object Type: Report
System: The UNT Digital Library
MTA Progress Report for June through November, 1953 (open access)

MTA Progress Report for June through November, 1953

Introduction: "This report covers the contributions of UCRL to MTA research and development program during the period June 1 to November 30, 1953. In this program UCRL continues to work in close collaboration with the California Research and Development Company (CRD)."
Date: February 8, 1954
Creator: Lawrence Radiation Laboratory
Object Type: Report
System: The UNT Digital Library
On the Reaction p + d [right arrow] [mu]⁺ + t (open access)

On the Reaction p + d [right arrow] [mu]⁺ + t

Abstract: "The cross section for this reaction is calculated for three Hulthen deuteron wave functions. A hard core in the deuteron at one-half meson Compton wavelength reduces the total cross section and flattens the angular distribution in the backwards direction in agreement with experiment."
Date: February 5, 1954
Creator: Bludman, Sidney A.
Object Type: Report
System: The UNT Digital Library
A Linear, Transparent Beam Integrator (open access)

A Linear, Transparent Beam Integrator

Abstract: "A fast, linear air-ionization chamber has been developed for integrating and monitoring external heavy-particle beams. It consists of a thin-windowed air chamber in which the beam ionization light is viewed by a photomultiplier whose output is fed directly to a standard electrometer."
Date: February 12, 1954
Creator: Kitchen, Sumner W.
Object Type: Report
System: The UNT Digital Library
Hazards Summary Report for the Reflector-Control Critical-Assembly Experiments (open access)

Hazards Summary Report for the Reflector-Control Critical-Assembly Experiments

This report analyzes the stability and feasibility of a reflector-control system for a boiling heterogeneous reactor.
Date: February 12, 1957
Creator: Jankowski, Francis J.; Hogan, William S.; Redmond, Robert F.; Chastain, Joel W. & Fawcett, Sherwood L.
Object Type: Report
System: The UNT Digital Library
The Effect of Fabrication Variables on the Structure and Properties of UO₂-Stainless Steel Dispersion Fuel Plates (open access)

The Effect of Fabrication Variables on the Structure and Properties of UO₂-Stainless Steel Dispersion Fuel Plates

From introduction: "This report deals with a part of the research and development studies which preceded the manufacture of fuel elements for the Gas Cooled Reactor Experiment (GCRE)." The studies evaluate the effects of varying the type and size of UO2 particles, stainless steel matrix powders, blending procedures, compacting pressures, sintering times, temperatures and atmospheres, roll-cladding temperatures and reduction rates, total cold reduction, and heat-treating times and temperatures has been made for UO2 stainless steel dispersion fuel elements."
Date: February 18, 1959
Creator: Paprocki, Stan J.; Keller, Donald L. & Cunningham, G. W.
Object Type: Report
System: The UNT Digital Library
Properties of the System - Uranyl Nitrate - Aluminum Nitrate - Nitric Acid - Water - Hexone. Part VII. Distribution of Uranyl Nitrate, Nitric Acid, Plutonium (IV) and Plutonium (VI) from 0 to 60°C. (open access)

Properties of the System - Uranyl Nitrate - Aluminum Nitrate - Nitric Acid - Water - Hexone. Part VII. Distribution of Uranyl Nitrate, Nitric Acid, Plutonium (IV) and Plutonium (VI) from 0 to 60°C.

This report discusses studies regarding the distribution and other properties of uranyl nitrate, nitric acid, plutonium (IV) and plutonium (VI) as part of the Redox Process that separates plutonium, uranium, and fission products.
Date: February 1, 1952
Creator: Burger, L. L.; Rehn, I. M. & Slansky, C. M.
Object Type: Report
System: The UNT Digital Library
Analytical procedures for the metal fabrication process (open access)

Analytical procedures for the metal fabrication process

From introduction: The present report describes further refinements of the apparatus and the method to meet a need for a sensitive determination of carbon in plutonium.
Date: February 20, 1951
Creator: Leboeuf, M. B.
Object Type: Report
System: The UNT Digital Library
Westinghouse Creep Test of Zirconium-WAPD-M-106; Memorandum (open access)

Westinghouse Creep Test of Zirconium-WAPD-M-106; Memorandum

Basis: "It is desired to test the effect of neutron flux on the creep rate of zirconium. These data will greatly add to the metallurgical information needed for design specifications of reactor components utilizing this metal."
Date: February 12, 1951
Creator: Loeb, L. M.
Object Type: Report
System: The UNT Digital Library
Purex Pulse-Column Studies With Unirradiated Uranium: (Development of Specifications for the O.R.N.L. Pilot Plant) (open access)

Purex Pulse-Column Studies With Unirradiated Uranium: (Development of Specifications for the O.R.N.L. Pilot Plant)

Report summarizing data from Purex tests for pulse column specifications. These test results were used to estimate pilot plant specifications.
Date: February 20, 1951
Creator: Bradley, J. G.
Object Type: Report
System: The UNT Digital Library
Decontamination of Dissolver Vent Gases at Hanford (open access)

Decontamination of Dissolver Vent Gases at Hanford

The preceding report follows an extensive study made at Hanford of methods and equipment to remove effectively the dissolver vent gases.
Date: February 16, 1951
Creator: Blasewitz, A. G.; Carlisle, R. V.; Judson, B. F.; Katzer, M. F.; Kurtz, E. F.; Schmidt, W. C. et al.
Object Type: Report
System: The UNT Digital Library
Effects of Furnance Pressures on Quality of Remelted Uranium : Final Report, Production Test 314-59-M (open access)

Effects of Furnance Pressures on Quality of Remelted Uranium : Final Report, Production Test 314-59-M

The following report follows a test for remelting and casting uranium scrap specified that a pressure of 25 microns or less must be attained within the furnace before a charge is melted. The report was made to evaluate the effect of furnace pressures upon the quality if recast uranium metal.
Date: February 15, 1951
Creator: Kattner, W. T.
Object Type: Report
System: The UNT Digital Library
Development of Techniques for Power Production From Mixed Fission Products (open access)

Development of Techniques for Power Production From Mixed Fission Products

"An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will be capable of fueling practical generators into the kilowatt range using thermoelectric materials available in the same time period. A survey was made on current research and development efforts on waste fixation processes. Studies showed that a wide range of power densities (from 0.002 to 0.2 watts per cubic centimeter) will be available from calcined fission product wasted. An experimental program for the consolidation of low density, Idaho Chemical Processing Plant alumina type wastes is reviewed. Preliminary results indicated that densification factors of three to four are readily obtainable for such wastes."
Date: February 18, 1961
Creator: Eaton, D.
Object Type: Report
System: The UNT Digital Library