Search Results

Advanced search parameters have been applied.
open access

Evaluation of neutron absorbers for the melt-dilute treatment of aluminum-based spent fuel

Description: Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors is being consolidated at the Savannah River Site (SRS) for ultimate disposal in the Mined Geologic Disposal System (MGDS). Most of the aluminum-based fuel material contains highly enriched uranium (HEU) (greater than 20 percent {sup 235}U), which poses a proliferation risk and challenges the preclusion of criticality events for disposal periods exceeding 10,000 years.
Date: March 31, 2000
Creator: Vinson, D.W.
Partner: UNT Libraries Government Documents Department
open access

Conversion and Blending Facility Highly enriched uranium to low enriched uranium as uranium hexafluoride. Revision 1

Description: This report describes the Conversion and Blending Facility (CBF) which will have two missions: (1) convert surplus HEU materials to pure HEU UF{sub 6} and a (2) blend the pure HEU UF{sub 6} with diluent UF{sub 6} to produce LWR grade LEU-UF{sub 6}. The primary emphasis of this blending be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The chemical and isotopic concentrations… more
Date: July 5, 1995
Partner: UNT Libraries Government Documents Department
open access

Characterization of airborne uranium from test firing of XM774 ammunition

Description: Pacific Northwest Laboratory conducted experiments at Aberdeen Proving Grounds, Maryland, to characterize the airborne depleted uranium (DU) resulting from the test firings of 105-mm, APFSDS-T XM774 ammunition. The goal was to obtain data pertinent to evaluations of human inhalation exposure to the airborne DU. Data was desired concerning the following: (1) size distribution of airborne DU; (2) quantity of airborne DU; (3) dispersion of airborne DU from the target vicinity; (4) amount of DU dep… more
Date: November 1, 1979
Creator: Glissmeyer, J. A. & Mishima, J.
Partner: UNT Libraries Government Documents Department
open access

Gamma-ray line intensities for depleted uranium

Description: Measurements of the gamma-ray line intensities from depleted uranium allowed us to determine which of two conflicting previous experiments was correct. For the 1001-keV line we obtain a branching ratio of 0.834 +- 0.007, in good agreement with one of the previous experiments. A table compares our intensities for several lines with those obtained in previous experiments. 5 refs., 2 figs., 1 tab.
Date: January 1, 1985
Creator: Moss, C.E.
Partner: UNT Libraries Government Documents Department
open access

CHARACTERISTICS OF NEXT-GENERATION SPENT NUCLEAR FUEL (SNF) TRANSPORT AND STORAGE CASKS

Description: The design of spent nuclear fuel (SNF) casks used in the present SNF disposition systems has evolved from early concepts about the nuclear fuel cycle. The reality today is much different from that envisioned by early nuclear scientists. Most SNF is placed in pool storage, awaiting reprocessing (as in Russia) or disposal at a geologic SNF repository (as in the United States). Very little transport of SNF occurs. This paper examines the requirements for SNF casks from today's perspective and atte… more
Date: October 3, 2004
Creator: Haire, M. J.; Forsberg, C. W.; Matveev, V. Z. & Shapovalov, V. I.
Partner: UNT Libraries Government Documents Department
open access

RADIOACTIVE WASTE STREAMS FROM VARIOUS POTENTIAL NUCLEAR FUEL CYCLE OPTIONS

Description: Five fuel cycle options, about which little is known compared to more commonly known options, have been studied in the past year for the United States Department of Energy. These fuel cycle options, and their features relative to uranium-fueled light water reactor (LWR)-based fuel cycles, include: • Advanced once-through reactor concepts (Advanced Once-Through, or AOT) – intended for high uranium utilization and long reactor operating life, use depleted uranium in some cases, and avoid or minim… more
Date: November 1, 2010
Creator: Soelberg, Nick & Piet, Steve
Partner: UNT Libraries Government Documents Department
open access

Comparison of accelerator technologies for use in ADSS

Description: Accelerator Driven Subcritical (ADS) fission is an interesting candidate basis for nuclear waste transmutation and for nuclear power generation. ADS can use either thorium or depleted uranium as fuel, operate below criticality, and consume rather than produce long-lived actinides. A case study with a hypothetical, but realistic nuclear core configuration is used to evaluate the performance requirements of the driver proton accelerator in terms of beam energy, beam current, duty factor, beam dis… more
Date: March 28, 2011
Creator: Weng, W. T.; Ludewig, H.; Raparia, D.; Trbojevic, D.; Todosow, M.; McIntyre, P. et al.
Partner: UNT Libraries Government Documents Department
open access

Radiological assessment of cartridge 120-mm, APFSDS-T, XM829 ammunition

Description: The components of the XM829 round effectively shield out nonpenetrating beta radiation emitted by the depleted uranium; however, photons cna penetrate the components of the round and are therefore the predominant emission. The radiation levels associated with the XM829 ammunition are low. The maximum emissions measured from a cartridge are not likely to result in exposure to military personnel above the maximum permissible nonoccupational dose limits listed in Army Regulation (AR) 40-14. Based … more
Date: December 1, 1983
Creator: Hooker, C. D.; Hadlock, D. E.; Soldat, K. L. & Gilchrist, R. L.
Partner: UNT Libraries Government Documents Department
open access

Idaho National Engineering and Environmental Laboratory Site Report on the Production and Use of Recycled Uranium

Description: Recent allegations regarding radiation exposure to radionuclides present in recycled uranium sent to the gaseous diffusion plants prompted the Department of Energy to undertake a system-wide study of recycled uranium. Of particular interest, were the flowpaths from site to site operations and facilities in which exposure to plutonium, neptunium and technetium could occur, and to the workers that could receive a significant radiation dose from handling recycled uranium. The Idaho National Engine… more
Date: September 1, 2000
Creator: Lewis, L. C.; Barg, D. C.; Bendixsen, C. L.; Henscheid, J. P.; Wenzel, D. R. & Denning, B. L.
Partner: UNT Libraries Government Documents Department
open access

Air sampler performance at Ford's farm range

Description: An air-sampling system for a large-caliber depleted uranium (DU) penetrator firing range was tested. The objectives of the test were: to determine the bias between the monitoring readings and DU concentrations; and to determine if the target bay real-time monitor (RTM) tracks the decaying dust concentration. The test procedure was to operate total and respirable airborne particle samplers adjacent to the target bay monitors. A series of air samples was also taken after the test firings adjacent… more
Date: July 1, 1984
Creator: Glissmeyer, J. A. & Johnston, J. W.
Partner: UNT Libraries Government Documents Department
open access

ZPR-6 Assembly 7 High {Sup 240} Pu Core : A Cylindrical Assemby With Mixed (Pu, U)-Oxide Fuel and a Central High {Sup 240} Pu Zone.

Description: Over a period of 30 years more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited to form the basis for criticality safety benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineeri… more
Date: October 1, 2007
Creator: Lell, R. M.; Schaefer, R. W.; McKnight, R. D.; Tsiboulia, A.; Rozhikhin, Y.; Division, Nuclear Engineering et al.
Partner: UNT Libraries Government Documents Department
open access

The ultimate disposition of depleted uranium

Description: Significant amounts of the depleted uranium (DU) created by past uranium enrichment activities have been sold, disposed of commercially, or utilized by defense programs. In recent years, however, the demand for DU has become quite small compared to quantities available, and within the US Department of Energy (DOE) there is concern for any risks and/or cost liabilities that might be associated with the ever-growing inventory of this material. As a result, Martin Marietta Energy Systems, Inc. (En… more
Date: December 1, 1990
Partner: UNT Libraries Government Documents Department
open access

Energetic neutron spectrometry. Final report, December 1, 1967--March 31, 1972

Description: A research program in energetic-neutron spectrometry was carried out under Contracts AT(30-1)-3914 and AT(11-1)-5255 with Clarkson College of Technology during the period from 1 December 1967 through 31 March 1972. Accomplishments under this program include the development of a self-contained time-of-flight spectrometer for neutrons from 1 to 500 MeV and the measurement of neutron spectra from a thick target. Basically, the spectrometer measures the time-of-flight of a neutron scattered between… more
Date: November 1, 1973
Creator: Madey, R. & Waterman, F.M.
Partner: UNT Libraries Government Documents Department
open access

Prototype Air Cleaning System for a Firing Range

Description: This report recommends air cleaning system components for the US Army Ballistics Research Laboratory's new large-caliber firing range, which is used for testing depleted uranium (DU) penetrators. The new air cleaning system has lower operating costs during the life of the system compared to that anticipated for the existing air cleaning system. The existing system consists of three banks of filters in series; the first two banks are prefilters and the last are high-efficiency particulate air (H… more
Date: January 1, 1985
Creator: Glissmeyer, J. A.; Mishima, J. & Bamberger, J. A.
Partner: UNT Libraries Government Documents Department
open access

DUF6 Materials Use Roadmap

Description: The U.S. government has {approx}500,000 metric tons (MT) of surplus depleted uranium (DU) in various chemical forms stored at U.S. Department of Energy (DOE) sites across the United States. This DU, most of which is DU hexafluoride (DUF{sub 6}) resulting from uranium enrichment operations, is the largest amount of nuclear material in DOE's inventory. On July 6, 1999, DOE issued the ''Final Plan for the Conversion of Depleted Uranium Hexafluoride as required by Public Law 105-204'', in which DOE… more
Date: September 4, 2002
Creator: Haire, M.J.
Partner: UNT Libraries Government Documents Department
open access

Determination of Actinide Isotope Ratios Using Glow Discharge Optogalvanic Spectroscopy

Description: Diode-laser excited optogalvanic spectroscopy (OGS) of a glow discharge has been utilized to measure U-235/U-235 + U-238 isotope ratios. This ``optical mass spectrometric`` measurement has been demonstrated for a number of samples including uranium oxide, fluoride, and metal. Various diode-laser accessible atomic transitions in the 775 to 835 nm region have been evaluated; these transitions were chosen by considering OGS sensitivity and isotope shift. Using the 831.84 nm uranium line, for examp… more
Date: August 1, 1997
Creator: Young, J. P.; Shaw, R. W.; Barshick, C. M. & Ramsey, J. M.
Partner: UNT Libraries Government Documents Department
open access

Corrective Action Investigation Plan for Corrective Action Unit 409: Other Waste Sites, Tonopah Test Range, Nevada (Rev. 0)

Description: This Corrective Action Investigation Plan contains the U.S. Department of Energy, Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 409 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 409 consists of three Corrective Action Sites (CASs): TA-53-001-TAB2, Septic Sludge Disposal Pit No.1; TA-53-002-TAB2, Septic Sludge Disposal Pit No.2; and RG-24-001… more
Date: October 5, 2000
Creator: United States. Department of Energy. Nevada Operations Office.
Partner: UNT Libraries Government Documents Department
open access

Radioactive particulate release associated with the DOT specification 6M container under hypothetical accident conditions

Description: A testing program was conducted to determine the leakage of depleted uranium dioxide powder (DUO) from the inner containment components of the US Department of Transportation's (DOT) specification 6M container under hypothetical accident conditions. Depleted uranium dioxide was selected as a surrogate for plutonium oxide because of the similarities in the powder characteristics, density and particle size, and because of the special handling and special facilities required for plutonium oxide. T… more
Date: February 1, 1986
Creator: Taylor, J. M. & Raney, P.J.
Partner: UNT Libraries Government Documents Department
open access

User Guide for VISION 3.4.7 (Verifiable Fuel Cycle Simulation) Model

Description: The purpose of this document is to provide a guide for using the current version of the Verifiable Fuel Cycle Simulation (VISION) model. This is a complex model with many parameters and options; the user is strongly encouraged to read this user guide before attempting to run the model. This model is an R&D work in progress and may contain errors and omissions. It is based upon numerous assumptions. This model is intended to assist in evaluating 'what if' scenarios and in comparing fuel, rea… more
Date: July 1, 2011
Creator: Jacobson, Jacob J.; Jeffers, Robert F.; Matthern, Gretchen E.; Piet, Steven J. & Hintze, Wendell D.
Partner: UNT Libraries Government Documents Department
open access

Spent fuel sabotage aerosol test program :FY 2005-06 testing and aerosol data summary.

Description: This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program has been underway for several years. This program provides source-term data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated… more
Date: October 1, 2006
Creator: Gregson, Michael Warren; Brockmann, John E.; Nolte, O.; Loiseau, O.; Koch, W.; Molecke, Martin Alan et al.
Partner: UNT Libraries Government Documents Department
open access

Objectives, Strategies, and Challenges for the Advanced Fuel Cycle Initiative

Description: This paper will summarize the objectives, strategies, and key chemical separation challenges for the Advanced Fuel Cycle Initiative (AFCI). The major objectives are as follows: Waste management - defer the need for a second geologic repository for a century or more, Proliferation resistance - be more resistant than the existing PUREX separation technology or uranium enrichment, Energy sustainability - turn waste management liabilities into energy source assets to ensure that uranium ore resourc… more
Date: April 1, 2005
Creator: Piet, Steven; Dixon, Brent; Shropshire, David; Hill, Robert; Wigeland, Roald; Schneider, Erich et al.
Partner: UNT Libraries Government Documents Department
open access

Melt-Dilute Treatment of Spent Nuclear Fuel Assemblies from Research and Test Reactors

Description: The Savannah River Site is the US Department of Energy''s preferred site for return and treatment of all aluminum-base, spent, research and test reactor fuel assemblies. There are over 20,000 spent fuel assemblies now stored in different countries around the world, and by 2035 many will be returned to SRS for treatment and interim storage, in preparation for disposal in a geologic repository. The early fuel assemblies for research and test reactors were made using aluminum clad plates that were… more
Date: September 29, 1999
Creator: Peacock, H.B.
Partner: UNT Libraries Government Documents Department
open access

Proof-of-Concept Assessment of a Photofission-Based Interrogation System for the Detection of Shielded Nuclear Material

Description: A photonuclear interrogation method was experimentally assessed for the detection of shielded nuclear materials. Proof-of-Concept assessment was performed at the Los Alamos National Laboratory (LANL) TA-18 facility and used the INEEL VARITRON electron accelerator. Experiments were performed to assess and characterize the delayed neutron emission responses for different nuclear materials with various shield configurations using three ''nominal'' electron beam energies; 8-, 10-, and 11-MeV. With … more
Date: November 1, 2000
Creator: Jones, J. L.; Yoon, W. Y.; Harker, Y. D.; Hoggan, J. M.; Haskell, K. J. & VanAusdeln, L. A.
Partner: UNT Libraries Government Documents Department
open access

Solid0Core Heat-Pipe Nuclear Batterly Type Reactor

Description: This project was devoted to a preliminary assessment of the feasibility of designing an Encapsulated Nuclear Heat Source (ENHS) reactor to have a solid core from which heat is removed by liquid-metal heat pipes (HP).
Date: September 30, 2008
Creator: Greenspan, Ehud
Partner: UNT Libraries Government Documents Department
Back to Top of Screen