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in subjects: "Uranium Oxides U3O8"

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Reactivity effect of cross-section processing for moist bulk-oxide criticals

Good multigroup cross-section data is necessary if accurate analyses of critical or slightly sub-critical systems are performed. How the flux spectrum as calculated by the Nordheim method and by a more exact method can ultimately affect the calculated multiplication and/or critical mass of slightly moderated bulk-oxide systems is shown. Self-shielded multigroup cross sections were generated using the Nordheim method as implemented in the NITAWL code and by a more exact method as implemented in … more

Date: January 1, 1979

Creator: Bucholz, J.A. & Westfall, R.M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

High resolution gamma-ray spectroscopy applied to bulk sample analysis

A high resolution Ge(Li) gamma-ray spectrometer has been installed and made operational for use in routine bulk sample analysis by the Bendix Field Engineering Corporation (BFEC) geochemical analysis department. The Ge(Li) spectrometer provides bulk sample analyses for potassium, uranium, and thorium that are superior to those obtained by the BFEC sodium iodide spectrometer. The near term analysis scheme permits a direct assay for uranium that corrects for bulk sample self-absorption effects an… more

Date: January 1, 1980

Creator: Kosanke, K.L.; Koch, C.D. & Wilson, R.D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Microwave enhanced pyrochemical reactions of PuO sub 2 , UO sub 2 , and U sub 3 O sub 8

Experiments in the high level cells at WSRC have established that PuO{sub 2} has an extremely high absorption factor the microwaves: temperatures in excess of 1000{degrees}C were reached in less than 5 minutes with a multi mode, 2450 MHz, 600 watt, microwave oven. In other microwave heating experiments: stoichiometric compositions of PuO{sub 2}-UO{sub 2} were prepared and U{sub 3}O{sub 8} was reduced to U{sub 4}O{sub g}.

Date: January 1, 1990

Creator: Sturcken, E. F. & McCurry, L. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Powder metallurgy at Savannah River Laboratory

Development of a powder metallurgical process for the manufacture of reactor grade fuel tubes is being carried out at the Savannah River Laboratory (SRL). Using the P/M technology, cores were isostatically compacted with 100 wt % U/sub 3/O/sub 8/ and coextruded tubes fabricated which contain up to approx. 80% cores clad with aluminum. Irradiation tests were completed for tubes with up to 59 wt % oxide. Post-irradiation inspection showed no significant swelling for 40% burnup. Thermal testing of… more

Date: December 1, 1978

Creator: Peacock, H.B.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Maintaining the uranium resources data system and assessing the 1991 US uranium potential resources

The Energy Information Administration's (EIA) Uranium Resource Assessment Data (URAD) System contains information on potential resources (undiscovered) of uranium in the United States. The purpose of this report is: (1) to describe the work carried out to maintain and update the URAD system; (2) to assess the 1991 U.S. uranium potential resources in various cost categories; and (3) to describe the progress that has been made to automate the generation of the assessment reports and their subsequ… more

Date: December 31, 1992

Creator: McCammon, R. B. (Geological Survey, Reston, VA (United States)); Finch, W. I.; Grundy, W. D. & Pierson, C. T. (Geological Survey, Denver, CO (United States))

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Environmental control technology for mining and milling low-grade uranium resources

This study examined the type and level of wastes that would be generated in the mining and milling of U/sub 3/O/sub 8/ from four potential domestic sources of uranium. The estimated costs of the technology to control these wastes to different degrees of stringency are presented.

Date: April 1, 1981

Creator: Weakley, S. A.; Blahnik, D. E.; Long, L. W. & Bloomster, C. H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Sequential test procedures for inventory differences

By means of a simulation study, we investigated the appropriateness of Page's and power-one sequential tests on sequences of inventory differences obtained from an example materials control unit, a sub-area of a hypothetical UF/sub 6/-to-U/sub 3/O/sub 8/ conversion process. The study examined detection probability and run length curves obtained from different loss scenarios. 12 refs., 10 figs., 2 tabs.

Date: January 1, 1985

Creator: Goldman, A. S.; Kern, E. A. & Emeigh, C. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Predicted irradiation behavior of U sub 3 O sub 8 -Al dispersion fuels for production reactor applications

Candidate fuels for the new heavy-water production reactor include uranium/aluminum alloy and U{sub 3}O{sub 8}--Al dispersion fuels. The U{sub 3}O{sub 8}--Al dispersion fuel would make possible higher uranium loadings and would facilitate uranium recycle. Research efforts on U{sub 3}O{sub 8}--Al fuel include in-pile irradiation studies and development of analytical tools to characterize the behavior of dispersion fuels at high-burnup. In this paper the irradiation performance of U{sub 3}O{sub 8… more

Date: January 1, 1990

Creator: Cronenberg, A.W. (Engineering Science and Analysis, Albuquerque, NM (USA)); Rest, J. (Argonne National Lab., IL (USA)); Hyder, M.L.; Morin, J.P. & Peacock, H.B. (Westinghouse Savannah River Co., Aiken, SC (USA))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

The determination of UO/sub 2/ and UF/sub 4/ in fused fluoride salts

The determination of uranium oxide solubilities in fused fluoride salts is important in the electrolytic preparation of uranium metal. This project was initiated to develop a method for the determination of UO/sub 2/ separately from UF/sub 4/ in UF/sub 4/-CaF/sub 2/-LiF fused salts. Previous methods used for the determination of UO/sub 2/ in fused fluoride salts involved inert gas fusions where oxygen was liberated as CO/sub 2/, and hydrofluorination where oxygen was released as H/sub 2/O; but … more

Date: 1989~

Creator: Batiste, D. J. & Lee, D. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Chapter 2: uranium mines and mills

This chapter will be included in a larger ASCE Committee Report. Uranium mining production is split between underground and open pit mines. Mills are sized to produce yellowcake concentrate from hundreds to thousands of tons of ore per day. Miner's health and safety, and environmental protection are key concerns in design. Standards are set by the US Mine Safety and Health Administration, the EPA, NRC, DOT, the states, and national standards organizations. International guidance and standards a… more

Date: March 1, 1983

Creator: O'Connell, William J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Fabrication of high-uranium-loaded U/sub 3/O/sub 8/-Al developmental fuel plates

A common plate-type fuel for research and test reactors is U/sub 3/O/sub 8/ dispersed in aluminum and clad with an aluminum alloy. There is an impetus to reduce the /sup 235/U enrichment from above 90% to below 20% for these fuels to lessen the risk of diversion of the uranium for nonpeaceful uses. Thus, the uranium content of the fuel plates has to be increased to maintain the performance of the reactors. This paper describes work at ORNL to determine the maximal uranium loading for these fuel… more

Date: December 1, 1980

Creator: Copeland, G. L. & Martin, M. M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Reactions during the processing of U sub 3 O sub 8 -Al cermet fuels

The cermet fuel (U{sub 3}O{sub 8} dispersed in Al) being considered for use in the Savannah River Site reactors is thermodynamically unstable due to the potential for a metallothermic reduction reaction. The exothermic reaction between U{sub 3}O{sub 8} and Al produces approximately 225 calories of heat for every gram of oxide consumed. During processing of the U{sub 3}O{sub 8}-Al cermet fuels by Powder Metallurgy (P/M) techniques, a significant portion of the U{sub 3}O{sub 8} is reduced to U{su… more

Date: January 1, 1990

Creator: Marra, J. E. & Peacock, H. B.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

A review of the U sub 3 O sub 8 -aluminum reaction as a potential heat source in research and test reactor accidents

A critical review of the literature on the U{sub 3}O{sub 8}-aluminum reaction has been conducted. The reaction in fabricated fuel plates is found to be less energetic and much slower than in cold-pressed powder mixtures. The difference is at least partially attributable to conversion of up to 50% of the U{sub 3}O{sub 8} to U{sub 4}O{sub 9} during fabrication. No definitive measurements of the amount and rate of energy release have been made. Data are provided upon which to base calculations of … more

Date: January 1, 1992

Creator: Snelgrove, J.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Dissolution rates of uranium compounds in simulated lung fluid

Maximum dissolution rates of uranium into simulated lung fluid from a variety of materials were measured at 37/sup 0/in the where f/sub i/ is in order to estimate clearance rates from the deep lung. A batch procedure was utilized in which samples containing as little as 10 ..mu..g of natural uranium could be tested. The materials included: products of uranium mining, milling and refining operations, coal fly ash, an environmental sample from a site exposed to multiple uranium sources, and purif… more

Date: January 1, 1981

Creator: Kalkwarf, D. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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SEM and XES in high beta-gamma radiation fields

Techniques were developed for scanning electron microscopy (SEM) and x-ray energy spectrometry (XES) of samples of irradiated nuclear fuel elements with radiation fields of 35 rad/ks (..beta..,..gamma..) and 0.6 r/ks (..gamma..) at 1 dm. Under normal operating conditions, these radiation levels caused considerable deterioration of image quality and jammed the counting system of the XES. Good quality SEM images were obtained by placing a lead shield between the sample and the SEM detector and by… more

Date: January 1, 1975

Creator: Sturcken, E. F.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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High-density reduced-enrichment fuels for Research and Test Reactors

Development and irradiation testing of high-density fuels have been conducted by the US RERTR Program in order to provide the technical means to reduce the enrichment of fuels for research and test reactors. The traditional aluminum dispersion fuel technology has been extended to include the highest practical loadings of uranium-aluminide (UAl/sub x/, 2.3 MgU/m/sup 3/), uranium-oxide (U/sub 3/O/sub 8/, 3.2 MgU/m/sup 3/), and uranium-silicide (U/sub 3/Si/sub 2/, 5.5 MgU/m/sup 3/; U/sub 3/Si, 7.0… more

Date: January 1, 1983

Creator: Snelgrove, J. L.; Hofman, G. L. & Copeland, G. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Decontamination of HEPA filters: January--March 1977

Various leaching agents were tested to determine their capability for dissolving PuO/sub 2/, UO/sub 2/, and U/sub 3/O/sub 8/. The amount of radionuclides retained by the filter media was investigated. Adsorption isotherms for two leaching systems were obtained. A four-stage dissolution process was developed. 10 figures, 2 tables.

Date: July 22, 1977

Creator: Luthy, Don F. & Lewis, Edward L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Summary history of domestic uranium procurement under US Atomic Energy Commission contracts. Final report

During the period 1947 through 1970, the Atomic Energy Commission (AEC) fostered the rapid development and expansion of the domestic uranium mining and milling industry by providing a market for uranium. Some thirty-two mills were constructed during that period to produce U/sub 3/O/sub 8/ concentrates for sale to the AEC. In addition, there were various pilot plants, concentrators, upgraders, heap leach, and solution mining facilities that operated during the period. The purpose of this report … more

Date: September 1, 1982

Creator: Albrethsen, H. Jr. & McGinley, F.E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Influence of steam on the behavior of U/sub 3/O/sub 8/ aerosols. [PWR; BWR]

A project is being conducted in the Nuclear Safety Pilot Plant (NSPP), located at the Oak Ridge National Laboratory (ORNL), to study the behavior of aerosols assumed to be generated during LWR reactor accident sequences and released into containment. This project, which is part of the ORNL Aerosol Release and Transport (ART) Program, is sponsored by the Nuclear Regulatory Commission and its purpose is to provide experimental qualification for LWR aerosol behavioral codes being developed indepen… more

Date: January 1, 1982

Creator: Adams, R. E.; Tobias, M. L. & Kress, T. S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Irradiation performance of low-enriched uranium fuel elements

The status of the testing and evaluation of full-sized experimental low- and medium-enriched uranium fuel elements in the Oak Ridge Research Reactor is presented. Medium-enriched elements containing oxide and aluminide have been completely evaluated at burnups up to 75%. A low-enriched U/sub 3/Si/sub 2/ element has been evaluated at 41% burnup. Other silicide and oxide elements have completed irradiation satisfactorily to burnups of 75% and are now being evaluated. All results to date confirm t… more

Date: October 14, 1984

Creator: Copeland, G. L.; Hofman, G. L. & Snelgrove, J. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Fuel development activities of the US RERTR Program. [Reduced Enrichment Research and Test Reactor]

Progress in the development and irradiation testing of high-density fuels for use with low-enriched uranium in research and test reactors is reported. Swelling and blister-threshold temperature data obtained from the examination of miniature fuel plates containing UAl/sub x/, U/sub 3/O/sub 8/, U/sub 3/Si/sub 2/, or U/sub 3/Si dispersed in an aluminum matrix are presented. Combined with the results of metallurgical examinations, these data show that these four fuel types will perform adequately … more

Date: January 1, 1983

Creator: Snelgrove, J. L.; Domagala, R. F.; Wiencek, T. C. & Copeland, G. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Nuclear carrier business volume projections, 1980-2000

The expected number of shipments of commodities in the nuclear fuel cycle are projected for the years 1980 thru 2000. Projections are made for: yellowcake (U/sub 3/O/sub 8/); natural, enriched and reprocessed uranium hexafluoride (UF/sub 6/); uranium dioxide powder (UO/sub 2/); plutonium dioxide powder (PuO/sub 2/); fresh UO/sub 2/ and mixed oxide (MOX) fuel; spent UO/sub 2/ fuel; low-level waste (LLW); transuranic (TRU) waste; high-activity TRU waste; high-level waste (HLW), and cladding hulls… more

Date: May 1, 1980

Creator: Lebo, R.G.; McKeown, M.S. & Rhyne, W.R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Experimental comparison of the active well coincidence counter with the random driver

A direct comparison has been made between the IAEA Active Well Coincidence Counter (AWCC) and the CMB-8 Random Driver. The comparison included an experimental evaluation of precision, counting rate, accuracy, penetrability, stability, and the effect of sample inhomogeneity. Samples used in the evaluation included highly enriched U/sub 3/O/sub 8/, U/sub 3/O/sub 8/ mixed withe qgraphite, highly enriched uranium metal discs, and depleted uranium metal. These materials are typical of the samples of… more

Date: June 1, 1979

Creator: Menlove, H. O.; Ensslin, N. & Sampson, T. E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Cost and availability of nuclear fuel in the 1980's

Due to the decrease in expected nuclear reactor capacity growth, all portions of the fuel cycle can fulfill reactor needs throughout the 1980's with no expansion required except for fuel fabrication, where such expansion is already in the permit and regulatory system. As a result, fuel cycle costs should not increase faster than the rate of inflation with the possible exception of enrichment costs. It is likely that uranium will remain very competitive with coal as a fuel on a dollars per milli… more

Date: January 1, 1980

Creator: Kelly, M. J.; Baldwin, J. S. & Martin, S. C.

Item Type: Article

Partner: UNT Libraries Government Documents Department