UNT Libraries Government Documents Department - 117 Matching Results

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Absorption Characteristics of Long Soil Columns

Description: The purpose of this report is to present the information obtained relative to the characteristic adsorption of radioisotopes in a long (forty feet) laboratory soil column treated with a high salt, process waste of high activity density. The movement of adsorbed cations in a soil column subjected to prolonged leeching by water also was determined.
Date: May 1, 1955
Creator: McHenry, J. R.
open access

Air Leakage Through Labyrinth Seals

Description: This report contains the results of tests which demonstrated the feasibility of using graphite labyrinth type seals, i.e., a bushing machined with alternate grooves and lands on the inside diameter to create a sufficient pressure drop to provide a satisfactory seal.
Date: April 8, 1955
Creator: McCarthy, P. B.
open access

The Alpha Half-Life of the Isotope Pu-241

Description: A plutonium solution of known Pu-241 content was purified by solvent extraction techniques to remove uranium and americium impurities. Portions of this purified solution were then analyzed for U-237 as a function of time. Since the growth of U-237 occurs directly by the alpha decay of Pu-241, these measurements provided sufficient data for calculation of the Pu-241 alpha half-life, which was found to be 2.91 ± 0.50 x 10⁵ years.
Date: February 15, 1955
Creator: Gift, M. W.
open access

Alternate Acid Addition Facility for 100-K

Description: Document HW-33176, "A Proposed Scope of the 100-K Sulfuric Acid Addition Facilities", presented the justification and bases for a sulfuric acid addition facility at the 183-K headhouses and included a system for adding the acid to the raw water. Since the issue of this document several factors to consider in such a system have been brought to light by experience gained both at K and at other areas. The alternate system presented here eliminates several of the troublesome points in the previousl… more
Date: August 23, 1955
Creator: Bainard, W. D.
open access

Analysis of Broadened X-ray Diffraction Peaks

Description: This report is a manual describing the methods developed by Stokes (1) and Warren and Averbach (2) (3) for the determination of the effects of cold work by x-ray diffraction methods. Only the method of mathematical analysis is presented while the method of obtaining the necessary x-ray diffraction patterns is not mentioned. This manual will be used for an experimental study of irradiation damage to uranium.
Date: July 27, 1955
Creator: Merckx, K. R.
open access

Analytical applications of refractive index

Description: Report detailing the refractive index of solutions of uranyl nitrate, nitric acid and aluminum nitrate. This report builds upon preliminary data and a brief discussion that from a previous report. This report covers more accurate and detailed data that had be accumulated following the initial report.
Date: January 9, 1955
Creator: Burger, L. L.
open access

Atmospheric Contamination Associated with Inert-Gas-Shielded, Consumable Electrode Welding

Description: Apparent excessive concentrations of atmospheric contamination which were reported to be associated with an inert-gas-shielded consumable electrode arc wielding operation were studied to evaluate the potential health hazards. A study was made of the concentrations of metal fume and gaseous products of the operation as well as the spectrum of ultraviolet radiation. Recommendations for necessary controls were made.
Date: July 25, 1955
Creator: Adley, F. E. & Gill, W. E.
open access

Automatic In-Line Monitor for pH, Gamma Activity and Uranium in the Metal Recovery Plant

Description: In connection with the development of in-line analytical equipment for monitoring pH, gamma activity and uranium concentration in process streams, experiments and tests were carried out during the past year and a half in the Metal recovery Plant on a pH monitor for the hydrogen ion concentration in neutralized waste, a continuous gamma activity monitor on the RCU, an automatic photometer for uranium in RAF, and an automatic polarograph for uranium in RAW. This letter is written to present up-to… more
Date: February 18, 1955
Creator: Reas, W. H.; Connally, R. E.; Koyama, K.; Michelson, C. E. & Van Meter, W. P.
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.
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.
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.
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.
open access

Comparison of Flame Photometer and Conductivity Meter for the Determination of NaCl from Respirator Testing

Description: periodically the Industrial Hygiene Unit has the occasion to perform efficiency tests on respiratory protective devices and on filter cartridges used with these units. A study of the relative merits of the flame photometer and conductivity meter was made to determine which is more applicable for the determination of NaCl in filter samples.
Date: September 26, 1955
Creator: Baum, J. W. & Gill, W. E.
open access

Concrete Cone Anchor Tests

Description: This study was initiated to determine the minimum safety requirements for safe anchorage of electric pole lines. The objectives were to investigate the suitability of manufactured concrete pole line anchors for use at the Hanford Atomic Products Operation, to design a concrete anchor slug of optimum shape and size for manufacture, to determine by field tests the resistance pullout of the concrete anchor when buried at various depths under the most favorable condition, and to develop a safe desi… more
Date: March 18, 1955
Creator: Buchols, C. S.
open access

Continuous Denitration Status of Development, January 12, 1955

Description: Experimental studies on continuous denitration performed in 321 Building resulted in the development of an agitated-through-type calciner. The performance of a paddle-agitated 4-in.-diameter by 44-in.-long reactor was sufficiently promising to warrant construction of a 16-in.-diameter by 8 ft.-long semi-plant scale model. This progress report summarizes the results of studies to date employing the semi-plant scale calciner.
Date: January 14, 1955
Creator: Szulinski, M. J.
open access

The Coulometric Titration of Plutonium

Description: This work was performed to develop a general chemical method for the determination of small amounts of plutonium in solution. The work showed that a coulometric titration based on the preliminary oxidation of the plutonium to Pu (VI) followed by titration with electrolytically-generated ferrous ion to Pu (IV) was such a general method and was subject to few interferences. The significance of the work is that a chemical determination of plutonium can be made for amounts of plutonium heretofore d… more
Date: September 8, 1955
Creator: Carson, Jr., W. N.; Gile, H. S. & Vanderwater, J. W.
open access

Discussion with WAPD Personnel Regarding Oxide Fuel Materials

Description: R. H. Fillnow and H. Pennington of WAPD visited HAPO on September 14-15, 1955, to discuss HAPO special irradiation facilities and review fuel element problems with HAPO personnel. During their meeting with Metallurgy Research personnel, the progress of the evaluation of UO₂ elements for the PWR and the results of recent HAPO irradiations of oxide type fuel elements were discussed. Although brief, this information exchange was particularly valuable as many of the problems associated with the app… more
Date: September 16, 1955
Creator: Sanderson, M. J.
open access

A Doorway Monitor

Description: The purpose of this work was to produce a reliable, inexpensive instrument for the detection of hard beta contamination on the clothing of personnel. Also, the monitoring was required to be accomplished without interrupting the normal activities of the employees.
Date: April 29, 1955
Creator: Campbell, D. A. & Test, L. D.
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