234-5 Building RM line equipment tests, Task III mixer (open access)

234-5 Building RM line equipment tests, Task III mixer

Several operations that are important to the process as carried out in Task III (Reduction) are performed by the mixer. In order to specify the process certain tests were made to study these operations and are discussed in this report. They include: Mixing Time, Mixer Discharge Rate, Mixer Holdup, and Mixer Capacity. A description of the test, conclusions and recommendations is provided.
Date: April 10, 1952
Creator: Collins, P. E.
Object Type: Report
System: The UNT Digital Library
CORROSION OF STAINLESS STEELS BY HNO$sub 3$-HF-Al(NO$sub 3$)$sub 3$ MIXTURES DURING EVAPORATION OF PLUTONIUM PRODUCT STREAMS (open access)

CORROSION OF STAINLESS STEELS BY HNO$sub 3$-HF-Al(NO$sub 3$)$sub 3$ MIXTURES DURING EVAPORATION OF PLUTONIUM PRODUCT STREAMS

None
Date: November 10, 1952
Creator: Arehart, T. A. & Runion, T. C.
Object Type: Report
System: The UNT Digital Library
The Densities of Uranyl Sulfate Solutions Between 20° and 90°C (open access)

The Densities of Uranyl Sulfate Solutions Between 20° and 90°C

The densiies of uranyl sulfate water solutions were measure or 12 concentrations between the temperatures of 20° and 90°C. The density range at 20°C is 1.0539 grams per cubic centimeter at 0.17 molal to 2.0059 grams per cubic centimeter at 3.9 molal.
Date: October 10, 1952
Creator: Jegart, J.S.; Heiks, J.R. & Orban, E.
Object Type: Report
System: The UNT Digital Library
First Quarterly Report on the Reductions of Uranium Oxides (open access)

First Quarterly Report on the Reductions of Uranium Oxides

The preliminary results of a program designed to evaluate methods for preparing uranium hydride from the various oxides of uranium are presented. The apparatus has been designed and constructed for the purpose of carrying out batch reductions under a variety of conditions employing calcium hydride, calcium metal and magnesium metal as the reducing agents. Since the separation of the alkaline earth oxides, present as by-products in the furnace products, promises to be the most difficult problem encountered in this investigation, a major portion of thetime during this past quarterly period has been directed toward the development of a suitable leach method. No investigation of the reduction methods has been possible to date because of the inability to obtain SF materials. A brief outline of the future work is included. (auth)
Date: October 10, 1952
Creator: Bragdon, R. W.
Object Type: Report
System: The UNT Digital Library
The Fluidized Condenser (open access)

The Fluidized Condenser

None
Date: May 10, 1952
Creator: Beck, Curt B.; Canby, Thomas D. & Zonis, Irwin S.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
Graphite development pile graphite technical activities report June 1952 (open access)

Graphite development pile graphite technical activities report June 1952

Graphite burnout and chemical studies include: carbon dioxide - graphite reaction, controlled gas atmospheres, cyclotron irradiation, graphite - carbon dioxide - helium reaction kinetics. Physical properties studies include: hot test hole irradiation, surface studies, stored energy, physical expansion annealing. The experimental graphite program is discussed to include thermal conductivity and thermal expansion measurements. Also reported are: pile sampling, thermal conductivity of gases, irradiations in the MTR at Arco, in-pile controlled atmosphere program, heat generation in graphite, induction heater, mechanical properties programs and damage mechanism studies.
Date: July 10, 1952
Creator: Music, J. F. & Zuhr, H. F.
Object Type: Report
System: The UNT Digital Library
PHYSICAL PROPERTIES OF URANYL SULFATE SOLUTIONS AT ATMOSPHERIC PRESSURE (open access)

PHYSICAL PROPERTIES OF URANYL SULFATE SOLUTIONS AT ATMOSPHERIC PRESSURE

None
Date: March 10, 1952
Creator: Roarty, J.D.; Kaplan, S.I.; Powers, W.D. & Redmond, R.F.
Object Type: Report
System: The UNT Digital Library
RDA DC-6 -- Design criteria for reactor water plant at Coyote Rapids site. Instruction letter number 1 (open access)

RDA DC-6 -- Design criteria for reactor water plant at Coyote Rapids site. Instruction letter number 1

The design will be based on one reactor with a potential capacity of 1,300 megawatts. For the time being this reactor will be designated ``X``. The water plant will be designed to supply 100,000 gpm initially. The design shall provide, however, for the ultimate capacity of 140,000 gpm; i.e., underground process piping, space in river pump house, and other items which would be difficult to enlarge after initial construction, will be sized for the ultimate capacity and provision shall be made for future enlargement of filter plants, etc. to provide the required increase in capacity.
Date: January 10, 1952
Creator: Pilkey, O. H.
Object Type: Report
System: The UNT Digital Library
REPORT FOR RESEARCH ON URANIUM SALTS, NOVEMBER 5, 1951 TO FEBRUARY 5, 1952 (open access)

REPORT FOR RESEARCH ON URANIUM SALTS, NOVEMBER 5, 1951 TO FEBRUARY 5, 1952

None
Date: March 10, 1952
Creator: Orban, E.
Object Type: Report
System: The UNT Digital Library
University of California, Los Angeles Campus School of Medicine Atomic Energy Project quarterly progress report for period ending March 31, 1952 (open access)

University of California, Los Angeles Campus School of Medicine Atomic Energy Project quarterly progress report for period ending March 31, 1952

The fifteenth quarterly report being submitted for Contract No. AT04-1-GEN-12 is issued in accordance with Service Request Number 1 except for the report of the Alamogordo Section, Code 91810, which is submitted in accordance with the provisions of Service Request Number 2. Work is in progress on continuing existing projects. In addition, new projects have been initiated including the Kinetics and Mechanism of Protein Denaturation (10018); The Effect of Irradiation on the Constituents of Embryonic Serum (30033); and The Use of Controlled Atmospheres for Spectrographic Excitation Sources (40053). Many of the Project units are either wholly or partially completed and the following initial reports are available: Identification of Ferritin in Blood of Dogs Subjected to Radiation from an Atomic Detonation (UCLA-180); The Nutritional Value of Intravenous Tapioca Dextrin in Normal and Irradiated Rabbits (UCLA-181); The-Decarboxylation and Reconstitution of Linoleic Acid (UCLA-183); Preparation and Properties of Thymus Nucleic Acid (UCLA-184); The Radiation Chemistry of Cysteine Solutions Part II. (a) The Action of Sulfite on the Irradiated Solutions; (b) The Effect on Cystine (UCLA-185); A Revolving Specimen Stage for the Electron Microscope (UCLA-178); An Automatic Geiger-Mueller Tube Tester (UCLA-186); The Value of Gamma Radiation Dosimetry in Atomic Warfare Including a Discussion of …
Date: April 10, 1952
Creator: Warren, S.L.
Object Type: Report
System: The UNT Digital Library