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The Preparation of Aluminium Nitrate from Hydrated Aluminum Oxides

Description: This report discusses methods of producing aluminum nitrate for the Redox process. Large amounts of aluminum nitrate are consumed during the Redox process, so this report explores preparation of this material through the dissolution of hydrated aluminum oxide in nitric acid.
Date: October 5, 1949
Creator: Harmon, M. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Clarification of Redox Feed (1AF) by Filtration : A Semi-Works Study Progress, Redox Technical Data Study No. 8

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Report on Existing Active Particle Hazard-200 Areas

Description: "Recent surveys by the Health Instrument Section have disclosed the presence of many small radioactive spots on ground surfaces in the T and B plant areas. Investigation has shown that representative samples of the spots when mechanically separated invariably end in a single radioactive particle."
Date: October 22, 1947
Creator: Mickelson, M. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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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"Crud" Scrubbing with a Purex-Type Zebra Cartridge

Description: Entrained solids have in the past been one of the major factors limiting solvent extraction fission product decontamination. These solids are known to be surface active, to absorb fission products, and to form interfacial films or "cruds". A major step in eliminating these cruds was taken when the Purex columns were modified to operate with the interfaces at the waste ends of the columns rather than the product ends. This type of operation tended to flush the solids out with the waste rather th… more
Date: October 17, 1961
Creator: Richardson, G. L
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
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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
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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
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