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Particle size of particulate matter in the dissolver off-gas stream

Description: This report discusses particle size measurements with a modified cascade impactor of the particulate matter in the dissolver off-gases during the period of maximum gas evolution, and during the air sparge of the dissolver solution after the completion of the dissolving cycle which indicate that the mass-size median of the particles was less than 0.1 micron in both cases. The measurements were made, unfortunately, at a time when the efficiency of the silver reactor upstream to the sampling point was low enough to permit appreciable amounts of iodine through to the cascade impactor. The samples were therefore permitted to decay for thirty-five days before the relative amounts of radioactivity on the stages of the impactor and the follow- up filter paper were evaluated. The size of the particles obtained, 0.1 micron, should be considered primarily as an order of magnitude rather than an absolute value, because the cascade impactor (as well as any other impaction device) can not give an accurate value for the particle size in this size range.
Date: November 1, 1951
Creator: Weidenbaum, B.
Partner: UNT Libraries Government Documents Department

Processing E-metal in the 200 Areas

Description: This report discusses current plans of the Irradiation Processing Department which call for the inauguration of an E-metal (0.94% U-235) replacement program for the C-metal columns now in reactor use. Other reactor planning is considering the use of E-metal for E-N (lithium) nd E-Co (cobalt) loadings, compensation for reactor biological shields, and for the improved production reactor (IPR). Activation of any of these plans will be dependent on results of the test programs and A.E.C. policy decisions. The quantity of E-metal that might require separation processing is estimated and an economic analysis is provided
Date: October 19, 1956
Creator: Platt, A. M. & Tomlinson, R. E.
Partner: UNT Libraries Government Documents Department

FPT-63-27: Dimensional stability, model 1807 shape castings

Description: Due to sluggish transformation rates of metastable phases, unalloyed Pu continues to shrink after casting. Therefore, a pre-machining holding period is required to promote finished part dimensional stability. This test will determine the holding period commensurate with both this requirement for stability and an optimum material inventory level. Four storage periods will be evaluated (9, 8, 7, 6 days) for dimensional changes and related to parts stored for the standard 10-day period.
Date: October 18, 1963
Creator: Walker, C. M.
Partner: UNT Libraries Government Documents Department

Letter to N.T. Saunders NASA-Lewis Research Center

Description: Studies during the last two years have shown that the pneumatic impaction process is a flexible process for the production of cermet fuel elements. However, there is still much basic information to be acquired about the process before the limits of process capability can be established. Development work proposed herein is intended to continue optimization of the process, to establish the process parameters necessary to a pilot plant or production line operation, and to better define the process limitations.
Date: June 28, 1965
Creator: Fawcett, B. L.
Partner: UNT Libraries Government Documents Department

Ingot-dingot comparison

Description: For approximately the past two years, alloyed dingot uranium has been irradiated on a production scale for evaluation of rupture performance relative to ingot uranium. Supplementary data on dimensional behavior and certain pre-irradiation measurements have been accumulated under the Quality Certification Program. This report presents a comparison of ingot and dingot performance based on data obtained to date from this testing program. The discussion consists of three sections: (I) dimensional stability, (II) external bond quality, and (III) reactor rupture performance.
Date: May 21, 1962
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department

Analysis of alternatives: Plutonium button-line improvements

Description: Reduction of Pu nitrate solution to metal is accomplished in the button line portion of the Remote Mechanical Line. Several areas of deficiency exist in the facility, which must be corrected in order to maintain continuity. In December 1963, a study was undertaken to define and evaluate the operational and economic parameters pertinent to deciding to improve or replace the button line. This paper documents the study and presents the conclusions and recommendations.
Date: May 1, 1964
Creator: Johnson, B. M.; Smith, V. W.; Swain, E. O.; Szulinski, M. J. & Zahn, L. L.
Partner: UNT Libraries Government Documents Department

Measurements with an unreflected uranium (93.2%) metal sphere

Description: A near spherical unreflected and unmoderate uranium (93.7) metal configuration had been assembled to delayed criticality at Los Alamos National Laboratory in the 1950`s. Experiments with highly enriched uranium metal spherical shells had also been assembled. Both these experiments have been used to estimate the unreflected and unmoderated highly enriched uranium spherical critical mass. The experiments described in this paper, although originally justified for leakage spectra measurements and to investigate the use of a multiplying booster with a linear accelerator, also can provide estimates of the unreflected and unmoderated, highly enriched uranium spherical metal critical mass.
Date: June 1, 1993
Creator: Mihalczo, J. T.; Lynn, J. J.; Taylor, J. R. & Hansen, G. E.
Partner: UNT Libraries Government Documents Department

Feasibility report installation of the 231 Building Isolation Process in 224-T

Description: The Isolation Process, contained in the 231 Building, has an operational cost of approximately $35,000 per month. The location of this process in the 224-T Building would result in lower manpower requirements and effect an estimated savings of $5,000 per month. This report details study made to determine the feasibility and approximate cost for installing this process in 224-T.
Date: November 14, 1955
Creator: Poucher, F. W. & Ingalls, W. P.
Partner: UNT Libraries Government Documents Department

Laboratory project for isolation of plutonium

Description: Construction of proposed facilities to be operated under Technical Division supervision for research with plutonium is discussed. An attempt is made in this memorandum to visualize the research program for such a facility for the next five years, to aid in determining whether the cost of providing such facilities is justified.
Date: July 25, 1955
Creator: Jenkins, W. A.
Partner: UNT Libraries Government Documents Department

Remote fabrication of nuclear fuel pellets

Description: The equipment for remote fabrication of pellet fuels is in various stages of design, testing and evaluation. A pellet gaging system specifically designed to be maintained remotely has been demonstrated and is currently being interfaced with a programmable electro-mechanical manipulator to demonstrate completely automatic and remote disassembly and reassembly of the inspection unit. Pulsed magnetic welding of fuel rod end closures have been demonstrated. The solid-state welding technique allows the use of ultrasonics for weld inspection in place of traditional x-radiography. This welding and inspection method provides an attractive alternative for remote fuel fabrication. A new batch sintering furnace concept based upon aerospace technology is being developed. The furnace will have five to ten times the through-put of conventional batch furnaces and is easier to maintain than the horizontal furnaces in use today. Two high-speed mechanical press concepts (anvil and rotary) are currently being evaluated for remote operation and maintenance. The anvil press is especially attractive for remote fabrication due to its simplicity in set up and die change methods. All pellet fuel fabrication operations will be developed for remote operation and maintenance and representative fabrication rates will be demonstrated.
Date: June 1, 1978
Creator: Nyman, D.H.; Dahl, R.E. & Claudson, T.T.
Partner: UNT Libraries Government Documents Department


Description: This memorandum discusses the problems associated with the production and use of Uranium 233 for an early test shot.
Date: October 22, 1963
Creator: Smith, A. E.
Partner: UNT Libraries Government Documents Department

A combined experimental and modeling approach to uranium casting

Description: U casting was studied using a combined experimental and modeling approach; the U is cast into graphite molds using vacuum induction melting. Mold design and process parameters were varied. FLOW-3D and ABAQUS codes were used. Temperature predictions were compared with experimental data from thermcouples in the mold; initial metal and mold temperatures were used in input to FLOW-3D. Fluid flow predictions were validated using static and dynamic radiographic data. Dynamic radiographic videos of gold castings were compared to 3D simulations.
Date: August 1, 1994
Creator: Korzekwa, D. & Dunn, P.
Partner: UNT Libraries Government Documents Department

Revised requirements for continuous birch recovery at Redox

Description: The process criteria proposed use of the existing organic wash column, 10, as a stripping column for the neptunium accumulation and isolation cycles. It is now proposed to employ a new processing concept which will permit the use of the scrub section of the neptunium extraction column, 1S, for neptunium stripping thereby obviating the use of the 10 Column. This proposed new scheme will provide increased neptunium stripping efficiency and greater processing flexibility for the 1S Column. The revision will require four new jumpers, but will permit the deletion of eight jumpers required for the original proposal. This document discusses the technical bases and incentives for the proposed change and presents revised flow diagrams and jumper routings.
Date: February 2, 1961
Creator: Barnes, R. G.
Partner: UNT Libraries Government Documents Department

The potential of squeeze casting for the production of near net shape uranium parts

Description: This report was written to provide a detailed summary of a literature survey on the near net shape squeeze casting process. Squeeze casting was evaluated as a possible method for achieving the goals of the LANL program titled Near Net Shape Casting of Uranium for Reduced Environmental, Safety, and Health Impact. In this report the squeeze casting process is reviewed and an assessment of its ability to achieve the near net shape and waste minimization goals of the LANL program is made. It is concluded that although squeeze casting is capable of producing near net shaped parts and reducing the amount of subsequent machining (thereby decreasing wastes), to use the process with uranium would require the design of a unique piece of equipment capable of performing the melting, pouring and squeezing operations in close proximity and in a vacuum.
Date: November 1, 1993
Creator: Robertson, E.
Partner: UNT Libraries Government Documents Department

Fuel element recovery and its relationship to uranium scrap

Description: At the request of the manager of Process Engineering, a study was made of the fuel element recovery operation and its relationship to the HAPO uranium scrap losses. Three fundamental questions formed the basis for this study. They are: What is the amount of the yearly uranium scrap loss at HAPO? What contribution does the existing fuel element recovery process make to this loss? What should be done to reduce this loss? The purpose of this report is to answer these questions and make specific recommendations aimed at reducing these scrap losses. The basis for these recommendations will be explained in the DISCUSSION section of this report.
Date: July 10, 1958
Creator: Wells, E. N.
Partner: UNT Libraries Government Documents Department
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