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PROCESSES FOR RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE-BASE FUEL ELEMENTS. PART II

Description: Laboratory-scale tests on methods for recovering uranium and thorium from graphite-base reactor fuel elements are reported. The 90% HNO/sub 3/ process, which involves simultaneous disintegration and leaching in 21 M HNO/sub 3/, is applicable to all fuel elenments which do not contain coated fuel particles. Leaching of irradiated (0.001% burnup) fuels containing 3 and 12% uranlum recovered approximates 99.3 and 99.9%, respectively, of the uranium in two 4-hr leaches with boiling acid. The graphi… more
Date: November 30, 1961
Creator: Ferris, L.M.; Kibbey, A.H. & Bradley, M.J.
Partner: UNT Libraries Government Documents Department
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STUDIES OF THE SCINTILLATION PROCESS IN CsI(Tl)

Description: The scintillation response of CsI(Tl) crystals, having various thallium contents, was measured for excitation of the crystals by monoenergetic gamma rays, protons, and alpha particles. The investi gation was made to provide a test of some of the features of a theoretical model of the scintillation process in thallium-activated alkali iodides proposed by Murray and Meyer. In order to insure that the results obtained in this program would provide a critical test of the scintillation model, specia… more
Date: November 30, 1962
Creator: Gwin, R. & Murray, R. B.
Partner: UNT Libraries Government Documents Department
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A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal

Description: From abstract: Results are reported of a study to determine the most economical method of utilizing nuclear heat to gasify a North Dakota lignite and a West Virginia bituminous coal so that the resulting gas is suitable as a source of synthesis gas for fuels and chemicals.
Date: November 30, 1962
Partner: UNT Libraries Government Documents Department
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Status report of confinement studies Douglas United Nuclear operated reactors

Description: Confinement studies on the Hanford Production reactors were started in March at the request of the Richland Operations Office. The confinement studies were then undertaken with the following objectives established: (1) review and reestablish if necessary, the maximum credible accident for the production reactors operated by Douglas United Nuclear (DUN); (2) evaluate the present confinement systems under the Code of Federal Regulation Title 10, Part 100, Reactor Site Criteria, for the maximum cr… more
Date: November 30, 1965
Creator: Spink, J. R. & Fifer, N. F.
Partner: UNT Libraries Government Documents Department
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Monthly record report Research and Engineering N-Reactor Department

Description: This document is a monthly report on the operation and engineering work associated with the N-Reactor department. It summarizes the operating history of the reactor during the month of Nov 1964. Included are brief descriptions of ongoing and planned work on testing and development of reactor components, fuel elements, safety tests, cooling systems, fuel production, materials testing, and other projects to provide safe and efficient plant operation.
Date: November 30, 1964
Creator: Leverett, M. C.
Partner: UNT Libraries Government Documents Department
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Production test IP-333-D, Supplement A: Irradiation of two defected UO{sub 2} fuel element assemblies

Description: To permit either the irradiation of two defected UO{sub 2} four-rod-cluster fuel element assemblies during the same operating period, or the irradiation of the two assemblies singly during two different operating periods in KE Reactor front-to-rear test hole 3865. The density of UO{sub 2} in one fuel element assembly is 90% of theoretical, in the other 87%. In both assemblies the fuel element cladding is Zircaloy and the fuel material natural uranium. An artificial defect will be made in each a… more
Date: November 30, 1960
Creator: Marshall, R. K.
Partner: UNT Libraries Government Documents Department
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Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: November 30, 1963
Creator: Auleta, J. J.
Partner: UNT Libraries Government Documents Department
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Primary Piping Static Test Design Request

Description: It is requested that a design be initiated for the primary piping static test. This test is necessary to provide information as to the reliability of the pipe subjected to reactor operating conditions. The test conditions are as follows: temperature - 2000 F (isothermal), pressure effective - 42 psi, and test time - 10,000 hours. It will be necessary to test two sizes of pipe as shown on the preliminary piping layout (2.250-inch O.D. x .095-inch wall and 3 1/2 SCH. 10 pipe). The test specimens … more
Date: November 30, 1961
Creator: O'Brien, R.W.
Partner: UNT Libraries Government Documents Department
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Request for Design of a Fuel Element Assembly Soak Test

Description: It is requested that the design be completed for a full-scale fuel element soak test. The test assembly must be designed to permit the fuel element test specimen to be submerged in a lithium bath under a pressure of 60 psi. The maximum temperature of the lithium is to be 2000 F. A total of four test units will be required to complete the test program. Two specimens will be exposed to a thermal cycle between 2000 F and 1400 F with the remaining two specimens being exposed to a thermal cycle betw… more
Date: November 30, 1961
Creator: Spahl, R.J.
Partner: UNT Libraries Government Documents Department
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Aluminum Bar-X seal tests. Test series FFL-13

Description: This report is to evaluate a silver plated aluminum Bar-X seal's effectiveness in extending the range of ability to seal such a damaged plug.
Date: November 30, 1964
Creator: Edmiston, J.M.
Partner: UNT Libraries Government Documents Department
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Conoseal Bar-X Seal Tests

Description: On the NRX-A reactors the instrument ports are sealed by a Bar-X seal. Damage to the ports, which are part of the pressure vessel, required machining on the pressure vessel. A new design, using a Marman flanged piece to house the Bar-X seal port separate from the pressure vessel, was proposed. The test program was to determine the torque required to seal and the ability of each seal to hold during thermal shock.
Date: November 30, 1964
Creator: Edmiston, J.M.
Partner: UNT Libraries Government Documents Department
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A Laboratory Gas-Circulating Pump

Description: A pump was developed for pumping carbon dioxide in a closed loop without introducing impurities. This pump will give flow rates of up to 3 liters/min and will develop a working pressure of over 70 mm Hg. No wear was observed after 2000 hr of testing. It is felt that this pump is more desirable for this application than those developed by other experimenters for two reasons: relatively inexpensive construction of the pump and the associated electronic circuit and the low coefficient of friction … more
Date: November 30, 1961
Creator: McNabb, B. Jr. & McCoy, H. E. Jr.
Partner: UNT Libraries Government Documents Department
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Fabrication and Assembly of a Teflon Dropping-Mercury Electrode

Description: ABS>A procedure was developed for fabricating a Teflon dropping-mercury electrode (D.M.E.) that has been shown experimentally to be satisfactory for polarography in glasscorroding media. Because of the lack of a suitable electrode, polarography in such media has not been possible. The electrode consists of a glass-capillary and a Tefloncapillary segment which are attached by guide sleeves to form a unit that behaves as if it were a single segment. Procedures were perfected for precision-lapping… more
Date: November 30, 1962
Creator: Raaen, H. P.; Fox, R. J. & Walker, V. E.
Partner: UNT Libraries Government Documents Department
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Analysis of the Babcock and Wilcox Full-Size Steam Generator for a Sodium-Water Reaction

Description: An analysis of the effects of a sodium-water reaction in The Babcock & Wilcox Full-Size Steam Generator was conducted. A leak in a tube of the unit would cause a sodium-water reaction which would result in the rapid generation of quantities of reaction products, including hydrogen and high temperature
Date: November 30, 1965
Creator: Chase, W.L.; Ford, J.A.; Friedland, A.J.; Green, D.M.; Kovac, L.R. & Meyers, J.E.
Partner: UNT Libraries Government Documents Department
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