121 Matching Results

Search Results

Results: 1 - 24 next
open access

Mound Laboratory Liquid Waste Disposal Research Quarterly Report for April - June, 1950

Description: The following report is a quarterly report conducted by the Monsanto Chemical Company for liquid waste disposal research, covering the period April through June, 1950. This report discusses experiments that were carried out with both neutralized second-cycle wastes and pure isotope which show that, in general, the presence of fluoride ion does not interfere with the removal of fission products from waste solutions.
Date: July 1, 1950
Creator: Monsanto Chemical Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermodynamic Diagrams for Sodium

Description: From abstract: This paper presents temperature-entropy and Mollier charts for sodium, and describes briefly the method used for their construction, based upon data from the literature.
Date: July 13, 1950
Creator: Inatomi, T. H. & Parrish, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Potential of the Pu(III)-Pu(IV) Couple: The Hydrolysis Constant of Pu(IV)

Description: Report discussing an experiment in which the formal potentials of the Pu(III)-Pu(IV) couple in 1M perchloric acid and in 1M hydrochloric acid are determined. The potentials were measured through potentiometric titrations of Pu(III).
Date: July 18, 1950
Creator: Rabideau, Sherman W.; Lemons, Joe F. & Rollefson, G. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Terminal Report on the Radiolanthanum Laboratory

Description: "The purpose of this present document is twofold: (1) To acquaint the reader with the planning of the radiochemical laboratory designed for the analytical control of the Radio-lanthanum Process. (2) To define the terminal status of the design of this laboratory and its equipment."
Date: July 21, 1950
Creator: Figenshau, J. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel by Contact with Fused LiCl-KCl Mixtures

Description: Technical report investigating the distribution of rare earth elements between a liquid bismuth-uranium solution and fused KCI-LiCi mixtures. Report warrants further research on the liquid bismuth-uranium-fused salt system due to the benefit of continuous fission removal processes.
Date: July 1, 1951
Creator: Bareis, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Investigations of Domestic Radioactive Raw Materials, Beryllium, and Other Trace Elements Monthly Report: June 1951

Description: Monthly report of the U.S. Geological Survey's trace element investigations including an outline of field work, laboratory work, and staff activities that have been completed or are in process.
Date: 1951-07~
Creator: Geological Survey (U.S.). Trace Elements Office.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Physics Division Quarterly Progress Report for Period Ending March 20, 1951

Description: Technical report covering classified work of the Critical Experiments Program in the Physics Division for the period December 20, 1950 to March 20, 1951. Report outlines investigations of properties of critical assemblies composed of uranium and various reflectors and moderators, preliminary measurements of the effective energy for fission in the assembly. [From Introduction and Summary]
Date: July 2, 1951
Creator: Bernstein, S.; Snell, A. H. & Wollan, E. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FMPC Solvent Treatment Area - Process Design

Description: This memorandum presents the process design for the solvent reast area of the Feed Materials Production Center. The purpose ofthe transmittal is to provide the basis for the detailed mechanical design and layout of this section of the refinery. Drawings, flowsheets, and specifications are included.
Date: July 6, 1951
Creator: Pfeiffer, Carl & Maerker, John B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Report on Gamma-Ray Logging Activities

Description: Abstract: An evaluation is made of radioactivity logging as applied to exploration drilling on the Colorado Plateau. The compilation of data gives a preliminary insight into the possibilities of the technique being applied.
Date: July 9, 1951
Creator: Comstock, Sherman S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Shielding Reactor Corrosion Studies

Description: Technical report outlining the investigation of corrosion on MTR type fuel elements for the Shielding Reactor in filtered water. Report includes two basic types of protection: element pretreatment by either anodizing or alodizing, and solution control using nitric acid to maintain a pH of 5.5 to 6.5 or the addition of 60 ppm sodium chromate as an inhibitor. [From Abstract]
Date: July 9, 1951
Creator: Olsen, Arnold R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Graphite Sample Boring from Process Channels : Final Report, Production Test 105-389-P

Description: The following report records a total of forty-nine graphite core samples that have been bored from process tube blocks in the Hanford piles with the intention to provide results to indicate that core boring is an entirely practical operation over bore scraping in obtaining powder samples.
Date: July 10, 1951
Creator: Cole, J. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Solvent Extraction Method for Neptunium (237) Analysis

Description: Technical report describing a rapid and quantitative radiochemical method for the analysis of neptunium (237). This method is based on the extraction of neptunium (IV) with thenoyl-trifluoracetone in xylene. Neptunium (237) is separated free from other alpha emitters and from non-radioactive interferences, and the method may be readily adapted to remote control. [From Abstract]
Date: July 10, 1951
Creator: Moore, Fletcher L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Low Voltage Ion Source

Description: Describes the investigation of a particular method of extracting ions from an arc. Experimental results of a low extraction voltage ion source are given in some detail.
Date: July 12, 1951
Creator: Foster, J. S., (John Stuart), 1890-1964 & Martina, Eugene F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Tests on a High Current R.F. Joint in Vacuum

Description: An R.F. joint tester was designed to determine the relative heating and tendency toward arching at high RF current density (100 amps/linear inch) of a 12 inch diameter circular copper butt joint in vacuum with several types of inserts and at various amounts of axial loading, ranging from a very small contact pressure to one of 1400 pounds per linear inch of joint.
Date: July 25, 1951
Creator: Wharton, Charles B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen