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Managing the Nuclear Fuel Cycle: Policy Implications of Expanding Global Access to Nuclear Power

Description: After several decades of widespread stagnation, nuclear power is attracting renewed interest. Expanding global access to nuclear power has the potential to lead to the spread of nuclear technology that could be used for nuclear weapons. This report discusses the issue of nuclear power with regard to nuclear weapons nonproliferation policies, the Global Nuclear Energy Partnership (GNEP) begun under the Bush Administration, the future of the GNEP under the Obama Administration, and four areas of … more
Date: July 1, 2009
Creator: Nikitin, Mary Beth; Andrews, Anthony & Holt, Mark
Partner: UNT Libraries Government Documents Department
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Determination of Basic Structure-Property Relations for Processing and Modeling in Advanced Nuclear Fuel: Microstructure Evolution and Mechanical Properties

Description: The project objective is to study structure-property relations in solid solutions of nitrides and oxides with surrogate elements to simulate the behavior of fuels of inert matrix fuels of interest to the Advanced Fuel Cycle Initiative (AFCI), with emphasis in zirconium-based materials. Work with actual fuels will be carried out in parallel in collaboration with Los Alamos National Laboratory (LANL). Three key aspects will be explored: microstructure characterization through measurement of globa… more
Date: March 1, 2009
Creator: Wheeler, Kirk; Parra, Manuel & Peralta, Pedro
Partner: UNT Libraries Government Documents Department
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The Coming Nuclear Renaissance for Next Generation Safeguards Specialists--Maximizing Potential and Minimizing the Risks

Description: This document is intended to provide an overview of the workshop entitled 'The Coming Nuclear Renaissance for the Next Generation Safeguards Experts-Maximizing Benefits While Minimizing Proliferation Risks', conducted at Oak Ridge National Laboratory (ORNL) in partnership with the Y-12 National Security Complex (Y-12) and the Savannah River National Laboratory (SRNL). This document presents workshop objectives; lists the numerous participant universities and individuals, the nuclear nonprolifer… more
Date: January 1, 2009
Creator: Eipeldauer, Mary D
Partner: UNT Libraries Government Documents Department
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DEMOLISHING A COLD WARE ERA FULE STORAGE BASIN SUPERSTRUCTURE LADEN WITH ASBESTOS

Description: The K East (KE) Basin facilities are located near the north end of the Hanford Site's 100 K area. The facilities were built in 1950 as part of the KE Reactor complex and constructed within 400 meters of the Columbia River, which is the largest river in the Pacific Northwest and by volume the fourth largest river in the United States. The basin, located adjacent to the reactor, was used for the underwater storage of irradiated nuclear fuel discharged from the reactor. The basin was covered by a … more
Date: January 12, 2009
Creator: ER, LLOYD; JM, STEVENS; EB, DAGAN; TK, ORGILL; MA, GREEN; CH, LARSON et al.
Partner: UNT Libraries Government Documents Department
open access

TSUNAMI Primer: A Primer for Sensitivity/Uncertainty Calculations with SCALE

Description: This primer presents examples in the application of the SCALE/TSUNAMI tools to generate k{sub eff} sensitivity data for one- and three-dimensional models using TSUNAMI-1D and -3D and to examine uncertainties in the computed k{sub eff} values due to uncertainties in the cross-section data used in their calculation. The proper use of unit cell data and need for confirming the appropriate selection of input parameters through direct perturbations are described. The uses of sensitivity and uncertai… more
Date: January 1, 2009
Creator: Rearden, Bradley T; Mueller, Don; Bowman, Stephen M; Busch, Robert D. & Emerson, Scott
Partner: UNT Libraries Government Documents Department
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Uncertainty and Sensitivity of Contaminant Travel Times from the Upgradient Nevada Test Site to the Yucca Mountain Area

Description: Yucca Mountain (YM), Nevada, has been proposed by the U.S. Department of Energy as the nation’s first permanent geologic repository for spent nuclear fuel and highlevel radioactive waste. In this study, the potential for groundwater advective pathways from underground nuclear testing areas on the Nevada Test Site (NTS) to intercept the subsurface of the proposed land withdrawal area for the repository is investigated. The timeframe for advective travel and its uncertainty for possible radionucl… more
Date: September 10, 2009
Creator: Zhu, J.; Pohlmann, K.; Chapman, J.; Russell, C.; Carroll, R.W.H. & Shafer, D.
Partner: UNT Libraries Government Documents Department
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The Development of Models to Optimize Selection of Nuclear Fuels through Atomic-Level Simulation

Description: Demonstrated that FRAPCON can be modified to accept data generated from first principles studies, and that the result obtained from the modified FRAPCON make sense in terms of the inputs. Determined the temperature dependence of the thermal conductivity of single crystal UO2 from atomistic simulation.
Date: January 26, 2009
Creator: Phillpot, Prof. Simon; Sinnott, Prof. Susan B.; Seifert, Prof. Hans & Tulenko, Prog. James
Partner: UNT Libraries Government Documents Department
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REFERENCE CASES FOR USE IN THE CEMENTITIOUS BARRIERS PARTNERSHIP

Description: The Cementitious Barriers Project (CBP) is a multidisciplinary cross cutting project initiated by the US Department of Energy (DOE) to develop a reasonable and credible set of tools to improve understanding and prediction of the structural, hydraulic and chemical performance of cementitious barriers used in nuclear applications. The period of performance is >100 years for operating facilities and > 1000 years for waste management. The CBP has defined a set of reference cases to provide th… more
Date: January 6, 2009
Creator: Langton, C
Partner: UNT Libraries Government Documents Department
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Integrated process modeling for the laser inertial fusion Energy (LIFE) generation system

Description: A concept for a new fusion-fission hybrid technology is being developed at Lawrence Livermore National Laboratory. The primary application of this technology is base-load electrical power generation. However, variants of the baseline technology can be used to 'burn' spent nuclear fuel from light water reactors or to perform selective transmutation of problematic fission products. The use of a fusion driver allows very high burn-up of the fission fuel, limited only by the radiation resistance of… more
Date: October 22, 2009
Creator: Meier, W. R.; Anklam, T. M.; Erlandson, A. C.; Miles, R. R.; Simon, A. J.; Sawicki, R. et al.
Partner: UNT Libraries Government Documents Department
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Alternative Waste Forms for Electro-Chemical Salt Waste

Description: This study was undertaken to examine alternate crystalline (ceramic/mineral) and glass waste forms for immobilizing spent salt from the Advanced Fuel Cycle Initiative (AFCI) electrochemical separations process. The AFCI is a program sponsored by U.S. Department of Energy (DOE) to develop and demonstrate a process for recycling spent nuclear fuel (SNF). The electrochemical process is a molten salt process for the reprocessing of spent nuclear fuel in an electrorefiner and generates spent salt th… more
Date: October 28, 2009
Creator: Crum, Jarrod V.; Sundaram, S. K.; Riley, Brian J.; Matyas, Josef; Arreguin, Shelly A. & Vienna, John D.
Partner: UNT Libraries Government Documents Department
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Final Report for Monitoring of Reactor Antineutrinos with Compact Germanium Detectors

Description: This 2008 NCMR project has pursued measurement of the antineutrino-nucleus coherent scattering interaction using a low-energy threshold germanium gamma-ray spectrometer of roughly one-half kilogram total mass. These efforts support development of a compact system for monitoring the antineutrino emission from nuclear reactor cores. Such a monitoring system is relevant to nuclear safeguards and nuclear non-proliferation in general by adding a strong method for assuring quantitative material balan… more
Date: July 1, 2009
Creator: Orrell, John L. & Collar, J. I.
Partner: UNT Libraries Government Documents Department
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Non-Proliferative, Thorium-Based, Core and Fuel Cycle for Pressurized Water Reactors

Description: Two of the major barriers to the expansion of worldwide adoption of nuclear power are related to proliferation potential of the nuclear fuel cycle and issues associated with the final disposal of spent fuel. The Radkowsky Thorium Fuel (RTF) concept proposed by Professor A. Radkowsky offers a partial solution to these problems. The main idea of the concept is the utilization of the seed-blanket unit (SBU) fuel assembly geometry which is a direct replacement for a 'conventional' assembly in eithe… more
Date: July 12, 2009
Creator: M., Todosow; M., Todosow & Raitses, G. (BNL) Galperin, A. (Ben Gurion University)
Partner: UNT Libraries Government Documents Department
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MDD Status Letter Report (AFCI CETE Milestone)

Description: Current flow sheets for processing used nuclear fuels do not produce separated streams of all of the actinides. These aqueous processing streams must be converted into solid forms suitable for recycle (fuel/target fabrication), storage, or disposal, necessitating co-conversion. A process developed at ORNL in the 1980s to make UO{sub 3} suitable as fuel feedstock was studied for preparation of mixed actinide oxides with similarly favorable ceramic properties. The process, Modified Direct Denitra… more
Date: September 1, 2009
Creator: Vedder, Raymond James & Jubin, Robert Thomas
Partner: UNT Libraries Government Documents Department
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Russian-Origin Highly Enriched Uranium Spent Nuclear Fuel Shipment From Bulgaria

Description: In July 2008, the Global Threat Reduction Initiative and the IRT 2000 research reactor in Sofia, Bulgaria, operated by the Institute for Nuclear Research and Nuclear Energy (INRNE), safely shipped 6.4 kilograms of Russian origin highly enriched uranium (HEU) spent nuclear fuel (SNF) to the Russian Federation. The shipment, which resulted in the removal of all HEU from Bulgaria, was conducted by truck, barge, and rail modes of transport across two transit countries before reaching the final dest… more
Date: July 1, 2009
Creator: Cummins, Kelly; Bolshinsky, Igor; Allen, Ken; Apostolov, Tihomir & Dimitrov, Ivaylo
Partner: UNT Libraries Government Documents Department
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Selective Separation of Trivalent Actinides from Lanthanides by Aqueous Processing with Introduction of Soft Donor Atoms

Description: Implementation of a closed loop nuclear fuel cycle requires the utilization of Pu-containing MOX fuels with the important side effect of increased production of the transplutonium actinides, most importantly isotopes of Am and Cm. Because the presence of these isotopes significantly impacts the long-term radiotoxicity of high level waste, it is important that effective methods for their isolation and/or transmutation be developed. Furthermore, since transmutation is most efficiently done in the… more
Date: September 22, 2009
Creator: Nash, Kenneth L.
Partner: UNT Libraries Government Documents Department
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ENVIRONMENTAL PROBLEMS ASSOCIATED WITH DECOMMISSIONING THE CHERNOBYL NUCLEAR POWER PLANT COOLING POND

Description: Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete cl… more
Date: September 30, 2009
Creator: Farfan, E.
Partner: UNT Libraries Government Documents Department
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Lessons Learned at the Idaho National Laboratory for the Entry into Force of the U.S. Additional Protocol

Description: For a number of years, the Idaho National Laboratory (INL) has been preparing for the entry into force of the U.S. Additional Protocol (AP). These preparations included attending training, participating in tabletop exercises, preparing draft declarations, developing INL-specific guidance documents, preparing for and hosting a mock complementary access visit, and preparing declarations for official submittal. All of these activities, the training materials, and software developed by other U.S. D… more
Date: July 1, 2009
Creator: Joe, Jeffrey C. & Hoiland, Shauna A.
Partner: UNT Libraries Government Documents Department
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Moving toward multilateral mechanisms for the fuel cycle

Description: Multilateral mechanisms for the fuel cycle are seen as a potentially important way to create an industrial infrastructure that will support a renaissance and at the same time not contribute to the risk of nuclear proliferation. In this way, international nuclear fuel cycle centers for enrichment can help to provide an assurance of supply of nuclear fuel that will reduce the likelihood that individual states will pursue this sensitive technology, which can be used to produce nuclear material dir… more
Date: April 17, 2009
Creator: Panasyuk,A.; Rosenthal,M. & Efremov, G. V.
Partner: UNT Libraries Government Documents Department
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Thermal Hydraulics of the Very High Temperature Gas Cooled Reactor

Description: The U.S Department of Energy (DOE) is conducting research on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core will be either a prismatic graphite block type core or a pebble bed core. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, … more
Date: October 1, 2009
Creator: Oh, Chang; Kim, Eung; Schultz, Richard; Patterson, Mike & Petti, Davie
Partner: UNT Libraries Government Documents Department
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Modeling acid-gas generation from boiling chloride brines

Description: This study investigates the generation of HCl and other acid gases from boiling calcium chloride dominated waters at atmospheric pressure, primarily using numerical modeling. The main focus of this investigation relates to the long-term geologic disposal of nuclear waste at Yucca Mountain, Nevada, where pore waters around waste-emplacement tunnels are expected to undergo boiling and evaporative concentration as a result of the heat released by spent nuclear fuel. Processes that are modeled incl… more
Date: November 16, 2009
Creator: Zhang, Guoxiang; Spycher, Nicolas; Sonnenthal, Eric & Steefel, Carl
Partner: UNT Libraries Government Documents Department
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Fast Reactor Fuel Type and Reactor Safety Performance

Description: Fast Reactor Fuel Type and Reactor Safety Performance R. Wigeland , Idaho National Laboratory J. Cahalan, Argonne National Laboratory The sodium-cooled fast neutron reactor is currently being evaluated for the efficient transmutation of the highly-hazardous, long-lived, transuranic elements that are present in spent nuclear fuel. One of the fundamental choices that will be made is the selection of the fuel type for the fast reactor, whether oxide, metal, carbide, nitride, etc. It is likely that… more
Date: September 1, 2009
Creator: Wigeland, R. & Cahalan, J.
Partner: UNT Libraries Government Documents Department
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Model of a Generic Natural Uranium Conversion Plant? Suggested Measures to Strengthen International Safeguards

Description: This is the final report that closed a joint collaboration effort between DOE and the National Nuclear Energy Commission of Brazil (CNEN). In 2005, DOE and CNEN started a collaborative effort to evaluate measures that can strengthen the effectiveness of international safeguards at a natural uranium conversion plant (NUCP). The work was performed by DOE s Oak Ridge National Laboratory and CNEN. A generic model of a NUCP was developed and typical processing steps were defined. Advanced instrument… more
Date: November 1, 2009
Creator: Raffo-Caiado, Ana Claudia; Begovich, John M & Ferrada, Juan J
Partner: UNT Libraries Government Documents Department
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Application of Self-Propagating High Temperature Synthesis to the Fabrication of Actinide Bearing Nitride and Other Ceramic Nuclear Fuels

Description: The project uses an exothermic combustion synthesis reaction, termed self-propagating high-temperature synthesis (SHS), to produce high quality, reproducible nitride fuels and other ceramic type nuclear fuels (cercers and cermets, etc.) in conjunction with the fabrication of transmutation fuels. The major research objective of the project is determining the fundamental SHS processing parameters by first using manganese as a surrogate for americium to produce dense Zr-Mn-N ceramic compounds. The… more
Date: April 30, 2009
Creator: John J. Moore, Marissa M. Reigel, Collin D. Donohoue
Partner: UNT Libraries Government Documents Department
open access

REVIEW OF MECHANISTIC UNDERSTANDING AND MODELING AND UNCERTAINTY ANALYSIS METHODS FOR PREDICTING CEMENTITIOUS BARRIER PERFORMANCE

Description: Cementitious barriers for nuclear applications are one of the primary controls for preventing or limiting radionuclide release into the environment. At the present time, performance and risk assessments do not fully incorporate the effectiveness of engineered barriers because the processes that influence performance are coupled and complicated. Better understanding the behavior of cementitious barriers is necessary to evaluate and improve the design of materials and structures used for radioact… more
Date: November 30, 2009
Creator: Langton, C. & Kosson, D.
Partner: UNT Libraries Government Documents Department
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