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Clarification of Redox Feed (1AF) by Filtration : A Semi-Works Study Progress, Redox Technical Data Study No. 8
The following report was made to determine the effective clarity improvement, flow rate characteristics, and operational problems encountered on passing Redox uranium feed solution through sintered, modified Type 304 stainless steel filter elements.
Date:
October 15, 1948
Creator:
Cooper, V. R. & Coleman, E. M.
System:
The UNT Digital Library
Chemical Research Section Progress Report for January 1950
The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.
Date:
February 15, 1950
Creator:
Albaugh, F. W.
System:
The UNT Digital Library
Corrosion of Stellite in Redox Streams
The following report provides results from laboratory tests on the corrosion resistance of various types of stellite facings on astenitic stainless steel T-347 to Redox streams.
Date:
May 15, 1950
Creator:
Koenig, W. W.
System:
The UNT Digital Library
Infrared Measurements on the System Hexone-Water-Uranyl Nitrate
The following report observes infrared measurements in the region of OH bands, the C2O band vicinity, the low frequency end of the spectrum, and the region of the UO2 band on the system hexone - water - uranyl nitrate.
Date:
July 15, 1950
Creator:
Burger, L. L. & Moore, R. H.
System:
The UNT Digital Library
Apparent viscosity of neutralized and concentrated raw slurry : TBP HW-no. 4 and HW flowsheet
Report describing how the neutralized aqueous waste from the TBP Metal Recovery Process will be concentrated by evaporation to minimize the requirements for underground storage tank capacity.
Date:
August 15, 1950
Creator:
Allen, A. W. & Harmon, M. K.
System:
The UNT Digital Library
Electroless Nickel Plating
Summary: "This investigation showed that a sound , weather-resistant coating can be applied to uranium that the surface to be plated is cleaned and etched properly. Using the proposed two-bath plating method at 80 C., a four-mil nickel coat can be deposited in thirteen hours."
Date:
November 15, 1950
Creator:
Groot, C. & Hopkins, H. H.
System:
The UNT Digital Library
Analytical procedures for the plutonium Metal Fabrication Process
A report describing a the results of a fluorimetric and volumetric method for the determination of fluoride. This method was developed for the determination of ionizable fluorine in gases in the range of 1-500ppm. This method was chosen because the determination depends on the generation of a color rather than the bleaching effect or on a change of color.
Date:
January 15, 1951
Creator:
Kendall, L. F.
System:
The UNT Digital Library
Scouting Studies in a 5.05-Inch Diameter Redox Pulse Column
Investigation of principles of pulse-column design and effects of operating variables.
Date:
January 15, 1951
Creator:
Figg, W. S. & Bradley, J. G.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
The Hydrolysis Products of Tributyl Phosphate and Their Effect on the Tributyl Phosphate Process for Uranium Recovery
This report follows an investigation on how hydrolysis products of tributyl phosphate (such as dibutyl and monobutyl phosphoric acids, orthophosphoric acid and butanol) effect the tributyl phosphate process for uranium recovery.
Date:
April 15, 1951
Creator:
Wagner, R. M.
System:
The UNT Digital Library
Recovery of Plutonium From Slag and Crucible
Report evaluating different methods of preparing nitric acid solution and different methods of separating plutonium from this nitric acid solution of slag and crucible. Methods are explained and experimental data is given.
Date:
June 15, 1951
Creator:
Groot, C.; Hopkins, H. H. & Schulz, W. W.
System:
The UNT Digital Library
Retention of Iodine in Process Solutions by Mercuric Salts
Report discussing a study of various types of mercuric salts in order to determine which salt prevents the evolution of iodine which results from sparging.
Date:
June 15, 1951
Creator:
Holm, C. H.
System:
The UNT Digital Library
Laboratory Demonstration of Redox Feed Head-End Treatment ; Ruthenium Volatilization and Manganese Dioxide Scavenging
From introduction: "The prime motive behind the experiments described in this report and in those preceding it in this series is the desire to reduce the number of Redox cycles necessary for decontamination from fission products of the plutonium and uranium streams sufficient to allow final disposition of these two products...This report deals with the mechanics of manganese dioxide handing, laboratory development of manganese dioxide scavenging, and a series of experiments at multicurie level combining ruthenium volatilization and manganese dioxide scavenging in stainless steel equipment."
Date:
July 15, 1951
Creator:
Hicks, H. G.; McCormack, C. G. & Roake, W. E.
System:
The UNT Digital Library
The Application of Nuclear Track Emulsions to the Analysis of Urine for very Low Level Plutonium
The following document analyzes plutonium in urine which uses nuclear track film for evaluation of the quantity of separated plutonium.
Date:
November 15, 1951
Creator:
Schwendiman, L. C.; Healy, John W. & Reid, D. L.
System:
The UNT Digital Library
A Report of Particle Contamination, October-December 1951
Report discussing a study on the number of radioactive particles in the atmosphere by Hanford Works. The study's l procedures and results are included.
Date:
February 15, 1952
Creator:
Paas, H. J. & Thomas, C. W.
System:
The UNT Digital Library
The Mechanism of Carrying Pu(III) on Lanthanum Fluoride
From introduction: "Analytical procedures for the determination of plutonium samples from the extraction and concentration plants utilize the carrying of the hydroxylamine-reduced trivulent plutonium by coprecipitation on lanthanum fluoride. Most other plutonium procedures also take advantage of the efficient carrying on lanthanum fluoride."
Date:
April 15, 1952
Creator:
Ralphs, Delbert Lloyd
System:
The UNT Digital Library
The Determination of Americium in Plutonium Product Solutions
The following report describes the process to determine the method for determination of americium in the presence of plutonium and uranium.
Date:
August 15, 1952
Creator:
Chetham-Strode, A., Jr.
System:
The UNT Digital Library
High Amperage Slug Welding : Final Report [on] 313-120-M
This report presents data recorded during a program made to improve uranium slug quality in January, 1952, to determine what improvements could be made in the welding process.
Date:
August 15, 1952
Creator:
Lingafelter, J. W.
System:
The UNT Digital Library
Determination of Americium
The following report describes a successful procedure used for the determination of americium in the presence of plutonium. Provided are articles listed that describe the research done in developing the method.
Date:
October 15, 1952
Creator:
Schmidt, H. R.
System:
The UNT Digital Library
Irradiated Process Slug Film Sampling Apparatus
"An apparatus was designed and fabricated to obtain film samples from irradiated process slugs. This apparatus has been used to obtain film samples from slugs of the sodium dichromate elimination test."
Date:
October 15, 1952
Creator:
Wilson, C. D.
System:
The UNT Digital Library
The Spontaneous Fission of Plutonium-240
The spontaneous fission rate of plutonium-240 has been redetermined and found to be 1.51 X 106 events/g/hr.
Date:
April 15, 1953
Creator:
Kinderman, E. M.
System:
The UNT Digital Library
The Identification of the Angular Inclusions Present in Rolled Uranium
Hanford uranium contains minute angular inclusions which affect the microstructure, reactivity, and other important factors controlling the serviceability of the metal. Small quantities of the inclusions have been isolated by chemical means, and the x-ray diffraction patterns and chemical analyses of the isolated materials have been determined. As a first step in the identification of the inclusions present in rolled uranium, a search was made for a chemical method of separating the inclusions from the matrix metal.
Date:
May 15, 1953
Creator:
Scott, F. A.
System:
The UNT Digital Library
Production of Xe135 for Laboratory Purposes. Irradiation of Uranium Hydroxide: Final Report on Production Test 305-15-P
The construction and operation of a fission gas generator, containing about 25 grams of uranium in the form of a powder with a high specific surface, are described in detail. The purpose of the work discussed in this report was to examine the feasibility of producing, separating, and assaying samples of Xe135 in preparation for a proposed measurement of the neutron cross section of this isotope. Krypton and xenon are separated by selective adsorption on charcoal at reduced temperature while iodine is removed by charcoal sorption at room temperature.
Date:
July 15, 1953
Creator:
Culvahouse, J. W.; Finnigan, J. W.; Lefevre, H. W. & Peterson, R. E. (Russell Edwin), 1927-
System:
The UNT Digital Library
The Hanford Remote Pipetter
The Hanford Remote Pipetter has developed into a very useful tool for routine pipetting by semi-skilled non-technical personnel. Radiation exposure to the operators has decreased to normal background levels as proper shielding exists between the sample and the operator. The results achieved by the pipetter have demonstrated its flexibility and simplicity of operation.
Date:
January 15, 1954
Creator:
Hammill, K. H.
System:
The UNT Digital Library