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Large-scale low-speed wind-tunnel tests of a model having a 60 degree delta horizontal canard control surface and wing to obtain static-longitudinal-stability and canard surface hinge-moment data

Description: Report presenting a wind-tunnel investigation of a model equipped with a 60 degree delta wing and a 60 degree delta horizontal all-movable canard control surface to determine the stability, control, and canard-surface hinge-moment characteristics at low speeds and at a Reynolds number of 9 x 10(exp 6). Two longitudinal positions of the canard surface were tested. Results regarding lift and pitching moment, drag, and hinge moment are provided.
Date: June 17, 1954
Creator: Burrows, Dale L.
Partner: UNT Libraries Government Documents Department
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Production of Zirconium at Y-12

Description: Abstract: "A general description is given of the permanent zirconium plant at Y-12. Equipment is described and materials of construction are listed. Photographs illustrating principal equipment and reduced construction drawings are also presented. Operating conditions and costs information are listed."
Date: November 17, 1955
Creator: Ramsey, J. W. & Whitson, W. K., Jr.
Partner: UNT Libraries Government Documents Department
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Separation of Zirconium & Hafnium : Proposal for Construction & Operation of Zirconium Production Plant

Description: Abstract: A re-evaluation of the cost of producing essentially hafnium free zirconium as zirconium oxide at a rate of 150,000-200,000 pounds zirconium per year by solvent extraction of the metal thiocyanates in a permanent plant has been made. Using part of the present temporary facilities, the cost, with five year amortization of the plant, will be $3.15 per pound zirconium. A by-product of the mixed oxides of hafnium and zirconium, having at least fifty percent hafnium and perhaps as high as … more
Date: November 17, 1955
Creator: Googin, J. M. & Strasser, G. A.
Partner: UNT Libraries Government Documents Department
open access

Zirconium-Hafnium Separation : Mixer-Settler Studies : Final Report

Description: Abstract: Use of the mixer-settler apparatus as a rapid means of determining improved conditions for plant operation is described including the experimental details. The preparation of highly purified samples of both zirconium oxide and hafnium oxide is discussed. (This document is concerned almost entirely with explorations of small scale continuous systems. Another document dealing with this general problem using small scale batch operations is being published simultaneously. It should prove … more
Date: November 17, 1955
Creator: Waldrop, F. B.; Ward, W. T. & Leaders, W. M.
Partner: UNT Libraries Government Documents Department
open access

Addendum to DC 56-8-167

Description: This document is an addendum to DC 56-8-167 and gives a description of the proposed Navy nuclear seaplane program and the objectives of the X211 engine study program.
Date: September 17, 1956
Creator: Harned, M.S.
Partner: UNT Libraries Government Documents Department
open access

Protective Coatings for Molybdenum

Description: Report discussing studies on various types of protective coatings for a molybdenum sheet. Procedures, materials, and results of each coating are included.
Date: February 17, 1953
Creator: Powell, Carroll F.; Jones, R. P.; Secrest, A. C.; Sherwood, E. M. & Campbell, Ivor E.
Partner: UNT Libraries Government Documents Department
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Removal of cesium from uranium recovery process wastes

Description: The Uranium Recovery Process (TBP Process) at Hanford extracts and decontaminates uranium from the Metal Waste produced in the Bismuth Phosphate Process. Aqueous waste, approximately equal in volume to that of the Metal Waste itself, results from the process. Although of several years' age, these wastes are still sufficiently radioactive that they must be returned to underground tanks for storage. For several years aqueous wastes of low radioactive content have been discharged to ground at Hanf… more
Date: May 17, 1954
Creator: Burns, R. E.; Brandt, R. L. & Clifford, W. E.
Partner: UNT Libraries Government Documents Department
open access

Reaction of Hydrogen With Uranium

Description: Report discussing reaction of hydrogen with uranium in a range of temperatures and pressures. Experimental materials, methods and results are included.
Date: February 17, 1955
Creator: Albrecht, William M. & Mallett, Manley William, 1909-
Partner: UNT Libraries Government Documents Department
open access

Degradation Products of Tributyl Phosphate

Description: Abstract: "A method for determination of dibutyl phosphate in solvent streams containing tributyl phosphate is outlined. The method is based on analysis for total uranium of total phosphate after removal of uranium and phosphate in excess of that present as uranyl dibutyl phosphate. Results on plant solvent samples are presented. Difficulties with precipitation of [...] dibutyl phosphate, when fresh solvents were employed, are discussed. Small amounts of nonphosphate uranium-complexing agents w… more
Date: February 17, 1956
Creator: Ewing, Robert A.; Kiehl, Samuel J. & Bearse, Arthur E.
Partner: UNT Libraries Government Documents Department
open access

Resistance-Welding Methods for End Capping PWR Uranium Oxide Fuel Rods

Description: Report discussing a study of various resistance-welding methods for end capping PWR uranium oxide fuel rods. Flash, upset, and spot welding were all investigated.
Date: October 17, 1955
Creator: Martin, David C.; Kearns, William H. & Pattee, Harry E.
Partner: UNT Libraries Government Documents Department
open access

A New Anionic Solvent Extraction Technique

Description: From abstract: "The extraction of acids with long-chain amines is described. Preliminary results on the extraction of the amine salts of polonium, plutonium and uranium are given."
Date: July 17, 1952
Creator: Moore, F. L.; Kelley, M. T. & Susano, C. D.
Partner: UNT Libraries Government Documents Department
open access

Analysis of Bulk Shielding Facility Neutron Dosimeter Data

Description: Technical report calculating "effective removal cross sections" for Pb, Fe and O from measurements of fast neutron does in the water surrounding the BSF reactor. The values for Pb and Fe agree quite well with those previously determined from Lid tank data, whereas that for O is somewhat lower. [From Abstract]
Date: July 17, 1952
Creator: Podgor, S.
Partner: UNT Libraries Government Documents Department
open access

Pile Temperature Study

Description: Regarding heat transfer studies of annular spaces around the process tube, there is general agreement among all concerned, that high graphite temperatures are essential at the initial startup. Pile Technology, in studying graphite damage, has developed information that shows little or no expansion occurring when temperatures are maintained at 275{degrees}C. Stored energy levels are less than 5% and K/Ko has saturated in the region of 3.5 to 4. Badly expanded samples (1% increase in length) have… more
Date: January 17, 1950
Creator: Jaske, R. T.
Partner: UNT Libraries Government Documents Department
open access

Uranium blending

Description: No Description Available.
Date: May 17, 1954
Creator: Smith, A. E.
Partner: UNT Libraries Government Documents Department
open access

Hydrofluosilicic acid as a cap and can etchant

Description: Aluminum caps and cans are thoroughly cleaned, before being used to can slugs, to insure wetting of the metal surfaces by molten AlSi in the canning pot. An acid bath is used, as part of the cleaning operations to remove surface oxide and other surface films from the metal. Two acid solutions are authorized in the standard operating procedure; a 20% phosphoric acid solution for etching both caps and cans, and a 1% hydrofluosilicic acid solution to be used for caps only. It is desired to determi… more
Date: March 17, 1953
Creator: Dixon, D. S.
Partner: UNT Libraries Government Documents Department
open access

Scattering of Zero-Energy Neutrons by a Spheroidal Square Well

Description: From abstract: "Scattering cross sections have been computed for zero-energy neutrons incident upon a square well of spheroidal symmetry, depth 42 Mev, and volume equal to that of a sphere of radius 1.45 x 10⁻¹³ ^1/3 cm."
Date: December 17, 1956
Creator: Uretsky, Jack Leon
Partner: UNT Libraries Government Documents Department
open access

Summary of Recent External Neutron-Yield Measurements by the MnSO₄ Tank Method

Description: Report that summarizes unreported neutron-yield data for the MnSO₄ tank method. Other yield measurements had been reported in other quarterly reports prior to the completion of this one.
Date: September 17, 1954
Creator: Crandall, Walter E. & Millburn, George P.
Partner: UNT Libraries Government Documents Department
open access

Design basis for proposed separations facility, for use in preliminary project proposal

Description: Members of the Working Committees for RDA DC-4 and RDA DC-7 (KE and KW Reactors) have reviewed and approved the design basis being used for the preparation of the 200 Area portion of the Program X preliminary project proposal. This design basis includes the following: plant capacity of 275 tons per month, average flow rate; the basic chemical process used will be the Purex process; the plant will be located in the Southeast Quadrant of the 200 East Area; the plant will contain a double line of … more
Date: March 17, 1952
Partner: UNT Libraries Government Documents Department
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Waste disposal criteria existing reactor expansion study

Description: This document discusses waste disposal criteria were established on the basis that the occurrence of river flow rates which were 72 cents of normal would not cause the effects of waste disposal to exceed limits. Since even the base case exceeds the criterion for the average body burden of phosphorus-32, provision to reduce the output of this radioisotope must be included in any expansion program. Provision to reduce the output of other radioisotopes will be required for most cases where the bul… more
Date: November 17, 1959
Creator: Hall, R. B.
Partner: UNT Libraries Government Documents Department
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HAPO irradiation of capsules containing UO{sub 2} specimens

Description: A knowledge of the effect of reactor irradiation on the properties of UO{sub 2} is relevant to the design and evaluation of UO{sub 2} fuel elements for the PRTR. Of particular interest is the effect of reactor irradiation on the thermal conductivity of sintered UO{sub 2} and the type, mechanism, and extent of radiation damage in sintered UO{sub 2}. In the latter case the study of fractured surfaces of irradiated UO{sub 2} specimens is a method of determining the extent of radiation damage. It i… more
Date: February 17, 1958
Creator: Newkirk, H. W.; Millhollen, M. K. & Brite, D. W.
Partner: UNT Libraries Government Documents Department
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Radiation intensity at center 42 inch riser on waste storage tank (MJ-4)

Description: It is recommended that the actual intensity existing today above the liquid be measured before recommendations are made on cutting through the concrete seal. A detailed statement of work on this problem follows. The calculations have been filed. In the study of the feasibility of cutting through the concrete seal on the center riser of the waste storage tank the radiation intensity that would be encountered is critical because director operator contact would be required. The question of the rad… more
Date: February 17, 1950
Creator: Weeks, J. L.
Partner: UNT Libraries Government Documents Department
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