UNT Libraries Government Documents Department - 909 Matching Results

Search Results

prev Results: 73 - 96 next
open access

Bronze Furnace History 313 Building

Description: This study was started in May 1949 to find methods of reducing the number of element failures in the salt bath bronze furnaces. Determining the cause of the failure and methods of eliminating them is followed to completion.
Date: February 6, 1951
Creator: Correy, Thos. B.
Item Type: Refine your search to only Report
open access

Calcium Uranium(IV) Fluoride; Precipitation and Reduction to Metal

Description: Using ferrous ion in the presence of fluoride for reducing uranium(VI) to the four state, the salt calcium uranium (IV) fluoride can be precipitated from uranyl nitrate solutions. X-ray studies have shown that the precipitate is a true double salt and not a mixture of the two insoluble fluorides of calcium and uranium. The salt settles rapidly and can be either filtered or centrifuged. Waste losses during precipitation and washing were on the order of 2.0 and 0.4 per cent, respectively. These w… more
Date: March 17, 1955
Creator: Tolley, W. B.
Item Type: Refine your search to only Report
open access

Canning depleted uranium : production test 313-110-M, final report

Description: From summary: "Uranium billets deficient in U235 were subjected to the normal successive steps in the slug fabrication process; viz., rolling, machining, and canning. No unusual behavior was observed at any point in the process, thus indicating that the depleted metal from the standpoint of mechanical properties can be considered equivalent to normal uranium."
Date: March 27, 1951
Creator: Jones, T. S.
Item Type: Refine your search to only Report
open access

Caps Clad with Aluminum-Silicon

Description: Approximately 15,000 "P" Process Aluminum caps clad with aluminum-silicon on the face and sides have been successfully canned. These caps were fabricated by the Aluminum Company of America from clad plate stock. An increase in canned slug yield of about two percent was realized from using these caps and no significant process problems indicated that the additional cost of clad plate might be off-set by the elimination of the centerless grinding now required on the side of the cap base. Therefor… more
Date: June 13, 1956
Creator: Farland, D. C.
Item Type: Refine your search to only Report
open access

Carbon Steel Program for High Temperature Reactor Systems

Description: The Reactor Design and Development Unit has just completed a design concept for an intermediate capacity dual purpose reactor plant utilizing carbon steel for the primary loop portion outside the reactor. This design concept is reported in HW-33157 AD (2). The economic and engineering gains are of sufficient magnitude to justify an accelerated and extensive test program to completely evaluate the remaining unknowns in utilizing carbon steel as a stainless steel substitute. It is the purpose of … more
Date: April 27, 1955
Creator: Pearl, W. L.
Item Type: Refine your search to only Report
open access

Centrifugal Casting for Plutonium and Plutonium-Uranium Plates

Description: The objective of this investigation was to determine the feasibility of centrifugal casting to produce fuel element plates suitable for use in a power reactor. Preliminary investigations involving the centrifugal casting of metal plates suitable for use in a power reactor proved to be successful. Lead plates cast at medium speeds contained very few voids and exhibited a surface which conformed very closely to that of the mold.
Date: November 28, 1956
Creator: Quinlan, F. B. & Tverberg, J. C.
Item Type: Refine your search to only Report
open access

Cerium and Plutonium Dioxide - Notes on Reduction to Massive Metal

Description: In reduction reactions of CeO₂, with calcium and a CaCl₂ flux, the use of vibrational energy was shown to have a marked effect on the yield of coalesced metal. Buttons of 40 to 50% theoretical yield were obtained from the vibrated reductions. As the flux concentration is decreased, the slag becomes more viscous containing undissolved CaO. The undissolved CaO present prevents the metal from completely coalescing, but the metal can be recovered from the slag and coalesced under CaCl₂ containing a… more
Date: February 13, 1956
Creator: Tolley, W. B.
Item Type: Refine your search to only Report
open access

Chemical Reactivity of Uranium Monocarbide and Uranium Mononitride with Water at 100°C.

Description: The monocarbide and the mononitride of uranium are potentially useful ceramic nuclear fuel materials. This paper reports the results of exploratory investigations of the reactions of uranium monocarbide and uranium mononitride with boiling water. Uranium dioxide, chemically stable in deoxygenated boiling water, was used as a control.
Date: February 26, 1959
Creator: Newkirk, H. W.
Item Type: Refine your search to only Report
open access

Chemical Stability of Purex and Uranium Recovery Process Solvent

Description: The desirability of operating many of the Purex columns at elevated temperatures, ca. 50-70 C, has made it necessary to obtain data on the stability of the solvent at these higher temperatures. Since the present diluent, Shell Spray Base, will not be entirely safe at the upper temperature limit, a number of diluents with higher flash point have been investigated concurrently with Shell Spray Base. This report presents data covering the first phases of this investigation, namely, the effect of n… more
Date: March 2, 1955
Creator: Moore, R. H.
Item Type: Refine your search to only Report
open access

Chemistry of the "Silver Reactor"

Description: The use of a reactor charged with silver nitrate coated packing for removal of radio-iodine from the waste gases of Hanford chemical processing plants has been successful in removing approximately 99.5 percent of this activity. Studies by the Radiological Sciences Department indicated the desirability of further reducing the amount of radio-iodine released to the atmosphere. Therefore, this study was undertaken with the objectives of better understanding the inherent limitations to iodine remov… more
Date: March 5, 1956
Creator: Barton, G. B. & McClanahan, Jr., E. D.
Item Type: Refine your search to only Report
open access

Chemistry-Separation Processes for Plutonium and Uranium

Description: Attached hereto are copies 1 through 4 of a classified secret report titled "Purex - A Hanford Separations Plant." We are also sending under separate cover a classified confidential report No. HW-36496 titled "Photographs of Purex - A Hanford Separations Plant," which is a counterpart of the above report. These documents are submitted for publication and should be incorporated as a single article.
Date: April 29, 1955
Creator: Mundt, W. J.
Item Type: Refine your search to only Report
open access

Classification of PuO2 Particles

Description: The Biology Operation, Hanford Laboratories, required plutonium dioxide particles in five different micron and sub-micron size ranges. These were to be supplied as a water suspension in small containers. It was necessary to design equipment, suitable for hood operation, which would give a satisfactory separation of these particles.
Date: January 6, 1960
Creator: Burnham, J. B.
Item Type: Refine your search to only Report
open access

A Closed Circuit Television System for In-Well Use -- Interim Report

Description: Wells drilled to date on the Hanford project represent and initial investment of over one million dollars. These nearly six hundred wells have been used and will continue to be used for observation and monitoring purposes of direct interest to ground disposal of radioactive wastes. Through measurement of depth to the water table the changing gradients as a result of large volume waste disposal are determined and direction of ground water flow established. The extent of contamination in ground … more
Date: August 5, 1959
Creator: Ratcliffe, C. A.
Item Type: Refine your search to only Report
open access

Coagulant Aids as Filter Aids

Description: The Hanford water treatment plants were operated for a number of years with alum as a coagulant and activated silica as a coagulant and a polyacrylamide as a filter conditioning agent. (other polyelectrolytes may be used.) Sufficient time has elapsed to make a comparison of the two methods of operation valid and useful. Such a comparison is the purpose of this paper.
Date: July 21, 1960
Creator: Conley, W. R.
Item Type: Refine your search to only Report
Back to Top of Screen