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The Determination of U²³⁷ and Fission-Product Contamination in Uranium Recovered by the Redox Process

Description: Introduction: "When uranium slugs are irradiated in the Hanford piles, one of the many substances formed is U-237. It arises primarily from the reaction: U-238 (n,2n) U-237. This uranium isotope is a beta and gamma emitter with a half-life of 6.7 days. Because it is isotopic with U-238, it accompanies the uranium recovered by the Redox Process, and its concentration is, of course, not diminished by the fission-product decontamination cycles. As a consequence, the maximum total decontamination … more
Date: October 1, 1952
Creator: Leboeuf, M. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Improved Spectrographic Analysis of Uranium and Plutonium by the Carrier Concentration Method

Description: Introduction: "The carrier (pyroelectric) concentration method is commonly used in the spectrographic analysis of plutonium metal. This report describes work which lead to substantial improvements in accuracy, precision and ease with which the analysis is made. Included are data from analyses of plutonium metal by the original and the improved carrier methods, and the cupferron extraction method."
Date: October 7, 1952
Creator: Daniel, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Americium

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of the Hanford Slave Manipulator for Use in the Multicurie Cells at Hanford

Description: Introduction: "During the early planning of the multicurie cells at Hanford it was decided that a slave type manipulator would be necessary to perform the experiments for which the cells were being designed. The design required steel roofs for installation through a port hole in the face. Technical Services Equipment Development began developing the proposed manipulator in January 1951 by making a study of those existing at that tune. None met the requirements which had been established; theref… more
Date: October 31, 1952
Creator: Field, Richard E. & Gifford, John F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Graphite surface studies

Description: This report discusses the the surface characteristics of virgin and irradiated artificial graphites and the changes which occur upon irradiation.
Date: October 10, 1952
Creator: Spalaris, C. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparison of Diluents for Tributyl Phosphate

Description: From introduction: This report summarizes a study of the composution and physical properties of a number of hydrocarbon diluents together with some generalizations regarding relations between [vapor pressure, density and viscosity] properties.
Date: October 6, 1950
Creator: Burger, L. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Elastic Solution for the Thermal Stresses in a Finite Solid Cylinder Fuel Element

Description: The heat generated by reactor fuel elements create thermal gradiants which cause thermal stresses of considerable magnitude. An elastic solution for these thermal stresses can be calculated with the equations given in Timoshenko's and Goodier's book (1) on elasticity if the fuel element is assumed infinite in length. An exact elastic solution for a finite cylindrical fuel element is given in this report in order to evaluate the effects of fuel element length on the thermal stresses and the effe… more
Date: October 12, 1956
Creator: Cadwell, J. J. & Merckx, K. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Summary of the History of Hanford Redox Plant Solvent

Description: The Redox solvent extraction process for the separation of uranium and plutonium from their fission products and from each other has operated on an over-all basis very successfully for more than four and one-half years. During this time, there have been occasional periods of high product losses and/or poor separation of fission products from uranium or plutonium as well as periods of poor operability due, among other things, to emulsification and entrainment. The search for the cause of these v… more
Date: October 4, 1956
Creator: {{{name}}}
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safe Conditions For Applying Titanium In H.A.P.O Process Equipment

Description: A two and one-half year period of extreme caution where titanium and nitric acid are involved has passed since the occurrence of the last and most serious uncontrolled incident involving titanium and nitric acid. During this period controlled explosions involving titanium and nitric acid have been routinely reproduced, additional laboratory and pilot plant experience has been gained and successful industrial applications have been appraised. Based on laboratory data and the known industrial exp… more
Date: October 6, 1956
Creator: Smith, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reduction off Plutonium (VI) with Hydrogen Peroxides

Description: Hydrogen peroxide has been used to reduce plutonium (VI) in nitric acid solution to the (IV) valence state. However, reduction of plutonium (VI) solutions containing iron has often been incomplete when hydrogen peroxide was used as the reducing agent. Since reduction of plutonium (VI) has been applied in plant solutions containing iron, a study of the plutonium (VI) reduction with hydrogen peroxide was undertaken. Variables tested included plutonium, nitric acid, and iron concentrations.
Date: October 17, 1956
Creator: Myers, M. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Organic Continuous Cartridge for the Purex 2D Column

Description: This document covers work done in 3- and 4-inch-diameter glass columns directed toward the development of improved cartridges for the Purex Plant final uranium cycle extraction column, the 2D column. A nozzle plate cartridge for the extraction section and a mixed plate cartridge containing both stainless steel and fluorothene sieve plates for the scrub section were developed. In 3- and 4-inch-diameter glass columns these cartridges have a uranium extraction efficiency as good as or better than … more
Date: October 16, 1956
Creator: Hesson, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Darex Pilot Plant Studies

Description: The Atomic Energy Commission has assigned the Hanford Atomic Products Operation the responsibility of providing the technology and facilities for the interim reprocessing of slightly enriched uranium fuels discharged from power and propulsion reactors. The fuel from the various reactors vary greatly in physical dimensions and in the composition of the core and cladding. For the purposes of chemical reprocessing, the fuels may be divided into the three main categories of aluminum, Zircaloy or st… more
Date: October 29, 1959
Creator: Shefcik, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final Report, Design Test PR-20 Calandria Characteristics

Description: Design Test Request PR-20 Calandria Characteristics, outlined the need for experimental data concerning the performance of the calandria under transient conditions. Test data was required to confirm that the moderator dump system would drop the level the required 24 inches in less than one second. The original calandria dump chamber design was modified until the criteria was met. This information is recorded in HW-58333, Interim Report, Design Test PR-20, Calandria Characteristics, which lists … more
Date: October 30, 1959
Creator: Gruver, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Neutron Age in Graphite-Water Lattices.

Description: The Fermi age of thermal neutrons in a lattice containing both water and graphite in some sort of weighted average of the age in water and in graphite independently, with correction for volumes of non-moderating elements or voids. The correct weighting function has been in question during design calculations for the NPR. This paper presents a very simple and direct approach to the problem, resulting in a weighting equation which seems to be theoretically sound. Unfortunately, simple theories ca… more
Date: October 28, 1959
Creator: Simpson, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of the PRTR High Pressure Loop on Plutonium Recycle Program Objectives

Description: For purposes of an earlier consideration of the effects of in-reactor test loops on PRTR operation and program, the design of the high pressure, H20 cooled fuel test loop was assumed to be similar to that for the high pressure, gas cooled loop. Detailed design criteria for the H20 loop have recently been completed so that this assumption is no longer necessary. Therefore, to insure that the effects of all proposed in-reactor loops are fully evaluated with respect to Plutonium Recycle Program ob… more
Date: October 29, 1959
Creator: Peterson, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Accuracy of Volume Measurements in a Large Process Vessel

Description: The Non-Production Fuel Reprocessing Program involves the chemical processing of valuable reactor fuels received from privately owned power reactors. It is necessary therefore, to accurately measure the fuel material received in order to insure proper payment to reactor operator and to provide the Atomic Energy Commission with appropriate accountability data. The volume measurement study described herein was conducted in order to determine the limits of accuracy that could be obtained in measur… more
Date: October 19, 1959
Creator: Pleasance, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Report on HAPO Unitized Microfilm Drawing System

Description: This report is being submitted to provide information and data on the planning and installation of a new mechanized drawing system which utilizes a new drawing index system and a 35mm microfilm image in a standard IBM card. The communication of engineering information to date has been primarily the full size contact print produced by exposing and developing light sensitive material. This method produces legible copies; but, it has the following disadvantages : (a) the original drawings are frag… more
Date: October 1, 1959
Creator: Durbin, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Plutonium Oxalate Disk Filter and Filter Media Studies

Description: Presently rotary drum filters are being used for plutonium oxalate slurry filtration in the 234-5 Building. Changing of the filter cloth used on a rotary drum is a time consuming operation which involves ever increasing radiation exposure to maintenance personnel. Consequently, studies were conducted in the 321 Building on a disk type filter which could be adapted for simple and quick ("one-nut") replacement of the filter medium.
Date: October 19, 1959
Creator: Rey, George
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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