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Irradiaton of Metallic and Oxide Fuels for Actinide Transmutation in the ATR

Description: Metallic fuels containing minor actinides and rare earth additions have been fabricated and are prepared for irradiation in the ATR, scheduled to begin during the summer of 2007. Oxide fuels containing minor actinides are being fabricated and will be ready for irradiation in ATR, scheduled to begin during the summer of 2008. Fabrication and irradiation of these fuels will provide detailed studies of actinide transmutation in support of the Global Nuclear Energy Partnership. These fuel irradiati… more
Date: September 1, 2007
Creator: MacLean, Heather J. & Hayes, Steven L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Clean-in-Place and Reliability Testing of a Commercial 12.5 cm Annular Centrifugal Contactor at the INL

Description: The renewed interest in advancing nuclear energy has spawned the research of advanced technologies for recycling nuclear fuel. A significant portion of the advanced fuel cycle includes the recovery of selected actinides by solvent extraction methods utilizing centrifugal contactors. Although the use of centrifugal contactors for solvent extraction is widely known, their operation is not without challenges. Solutions generated from spent fuel dissolution contain unknown quantities of undissolved… more
Date: September 1, 2007
Creator: Mann, N. R.; Garn, T. G.; Meikrantz, D. H.; Law, J. D. & Todd, T. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Nitride Fuel Development at the INL

Description: A new method for fabricating nitride-based fuels for nuclear applications is under development at the Idaho National Laboratory (INL). A primary objective of this research is the development of a process that could be operated as an automated or semi-automated technique reducing costs, worker doses, and eventually improving the final product form. To achieve these goals the fabrication process utilizes a new cryo-forming technique to produce microspheres formed from sub-micron oxide powder to i… more
Date: June 1, 2007
Creator: Windes, W. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Impact of Including Higher Actinides in Fast Reactor Transmutation Analyses

Description: Previous fast reactor transmutation studies generally disregarded higher mass minor actinides beyond Cm-246 due to various considerations including deficiencies in nuclear cross-section data. Although omission of these higher mass actinides does not significantly impact the neutronic calculations and fuel cycle performance parameters follow-on neutron dose calculations related to fuel recycling, transportation and handling are significantly impacted. This report shows that including the minor a… more
Date: September 1, 2007
Creator: Forget, B.; Asgari, M.; Ferrer, R. & Bays, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Technologies for the Simultaneous Separation of Cesium and Strontium from Spent Nuclear Fuel as Part of an Advanced Fuel Cycle

Description: As part of the Advanced Fuel Cycle Initiative, two solvent extraction technologies are being developed to simultaneously separate cesium and strontium from dissolved spent nuclear fuel. The first process utilizes a solvent consisting of chlorinated cobalt dicarbollide and polyethylene glycol extractants in a phenyltrifluoromethyl sulfone diluent. Recent improvements to the process include development of a new, non-nitroaromatic diluent and development of new stripping reagents, including a rege… more
Date: April 1, 2005
Creator: Law, Jack D.; HErbst, R. Scott; Meikrantz, David H.; Peterman, Dean R.; Riddle, Catherine L.; Tillotson, Richard D. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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AGC-1 Experiment and Final Preliminary Design Report

Description: This report details the experimental plan and design as of the preliminary design review for the Advanced Test Reactor Graphite Creep-1 graphite compressive creep capsule. The capsule will contain five graphite grades that will be irradiated in the Advanced Test Reactor at the Idaho National Laboratory to determine the irradiation induced creep constants. Seven other grades of graphite will be irradiated to determine irradiated physical properties. The capsule will have an irradiation temperatu… more
Date: August 1, 2006
Creator: Bratton, Robert L. & Burchell, Tim
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of the Use of Synroc to Solidify the Cesium and Strontium Separations Product from Advanced Aqueous Reprocessing of Spent Nuclear Fuel

Description: This report is a literature evaluation on the Synroc process for determining the potential for application to solidification of the Cs/Sr strip product from advanced aqueous fuel separations activities.
Date: March 1, 2006
Creator: Tripp, Julia & Maio, Vince
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Microstructural Characterization of Cast Metallic Transmutation Fuels

Description: As part of the Global Nuclear Energy Partnership (GNEP) and the Advanced Fuel Cycle Initiative (AFCI), the US Department of Energy (DOE) is participating in an international collaboration to irradiate prototypic actinide-bearing transmutation fuels in the French Phenix fast reactor (FUTURIX-FTA experiment). The INL has contributed to this experiment by fabricating and characterizing two compositions of metallic fuel; a non-fertile 48Pu-12Am-40Zr fuel and a low-fertile 35U-29Pu-4Am-2Np-30Zr fuel… more
Date: September 1, 2007
Creator: Cole, J. I.; Keiser, D. D. & Kennedy, J. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Characterization of Monolithic Fuel Foil Properties and Bond Strength

Description: Understanding fuel foil mechanical properties, and fuel / cladding bond quality and strength in monolithic plates is an important area of investigation and quantification. Specifically, what constitutes an acceptable monolithic fuel – cladding bond, how are the properties of the bond measured and determined, and what is the impact of fabrication process or change in parameters on the level of bonding? Currently, non-bond areas are quantified employing ultrasonic determinations that are challeng… more
Date: March 1, 2007
Creator: Burkes, D E; Keiser, D D; Wachs, D M; Larson, J S & Chapple, M D
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The Ceramic Waste Form Process at Idaho National Laboratory

Description: The treatment of spent nuclear fuel for disposition using an electrometallurgical technique results in two high-level waste forms: a ceramic waste form (CWF) and a metal waste form. Reactive metal fuel constituents, including all the transuranic metals and the majority of the fission products remain in the salt as chlorides and are processed into the CWF. The solidified salt is containerized and transferred to the CWF process where it is ground in an argon atmosphere. Zeolite 4A is ground and t… more
Date: May 1, 2007
Creator: Priebe, Stephen
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Monolithic Fuel Fabrication Process Development

Description: The pursuit of a high uranium density research reactor fuel plate has led to monolithic fuel, which possesses the greatest possible uranium density in the fuel region. Process developments in fabrication development include friction stir welding tool geometry and cooling improvements and a reduction in the length of time required to complete the transient liquid phase bonding process. Annealing effects on the microstructures of the U-10Mo foil and friction stir welded aluminum 6061 cladding are… more
Date: May 1, 2006
Creator: Clark, C. R.; Hallinan, N. P.; Jue, J. F.; Keiser, D. D. & Wight, J. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Strain-Rate Effects on Microstructural Deformation in Irradiated 316 SS

Description: A series of studies have been performed to investigate the post-irradiation deformation and failure behavior of 12% cold-worked 316 stainless steel following irradiation to variety of doses and temperatures in the outer rows of the experimental breeder reactor II (EBR-II). In the current phase of these studies, three sets of samples with different radiation induced microstructures have been characterized with transmission electron microscopy (TEM) following tensile testing to failure at a ‘fast… more
Date: February 1, 2005
Creator: Cole, James I.; Allen, Todd R.; Akasaka, Naoaki; Tsai, Hanchung; Yoshitake, Tsunemitsu; Yamagata, Ichiro et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Lessons Learned From Gen I Carbon Dioxide Cooled Reactors

Description: This paper provides a review of early gas cooled reactors including the Magnox reactors originating in the United Kingdom and the subsequent development of the Advanced Gas-cooled Reactors (AGR). These early gas cooled reactors shared a common coolant medium, namely carbon dioxide (CO2). A framework of information is provided about these early reactors and identifies unique problems/opportunities associated with use of CO2 as a coolant. Reactor designers successfully rose to these challenges. A… more
Date: April 1, 2004
Creator: Shropshire, David E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Impact of Nuclear Energy Futures on Advanced Fuel Cycle Options

Description: The Nuclear Waste Policy Act requires the Secretary of Energy to inform Congress before 2010 on the need for a second geologic repository for spent nuclear fuel. By that time, the spent fuel discharged from current commercial reactors will exceed the statutory limit of the first repository (63,000 MTiHM commercial, 7,000 MT non-commercial). There are several approaches to eliminate the need for another repository in this century. This paper presents a high-level analysis of these spent fuel man… more
Date: October 1, 2004
Creator: Dixon, Brent W. & Piet, Steven J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Criticality Analysis for Proposed Maximum Fuel Loading in a Standardized SNF Canister with Type 1a Baskets

Description: This document represents a summary version of the criticality analysis done to support loading SNF in a Type 1a basket/standard canister combination. Specifically, this engineering design file (EDF) captures the information pertinent to the intact condition of four fuel types with different fissile loads and their calculated reactivities. These fuels are then degraded into various configurations inside a canister without the presence of significant moderation. The important aspect of this study… more
Date: February 1, 2007
Creator: Pope, Chad; Taylor, Larry L. & Kim, Soon Sam
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safeguards and Non-proliferation Issues as Related to Advanced Fuel Cycle and Advanced Fast Reactor Development with Processing of Reactor Fuel

Description: The goal of this work is to establish basic data and techniques to enable safeguards appropriate to a new generation of nuclear power systems that will be based on fast spectrum reactors and mixed actinide fuels containing significant quantities of "minor" actinides, possibly due to reprocessing, and determination of what new radiation signatures and parameters need to be considered. The research effort focuses on several problems associated with the use of fuel having significantly different a… more
Date: October 1, 2006
Creator: Aryaeinejad, Rahmat; Cole, Jerry D.; Drigert, Mark W. & Vaden, Dee E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Scaling studies and conceptual experiment designs for NGNP CFD assessment

Description: The objective of this report is to document scaling studies and conceptual designs for flow and heat transfer experiments intended to assess CFD codes and their turbulence models proposed for application to prismatic NGNP concepts. The general approach of the project is to develop new benchmark experiments for assessment in parallel with CFD and coupled CFD/systems code calculations for the same geometry. Two aspects of the complex flow in an NGNP are being addressed: (1) flow and thermal mixin… more
Date: November 1, 2004
Creator: McEligot, D. M. & McCreery, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Modeling the Nuclear Fuel Cycle

Description: The Advanced Fuel Cycle Initiative is developing a system dynamics model as part of their broad systems analysis of future nuclear energy in the United States. The model will be used to analyze and compare various proposed technology deployment scenarios. The model will also give a better understanding of the linkages between the various components of the nuclear fuel cycle that includes uranium resources, reactor number and mix, nuclear fuel type and waste management. Each of these components … more
Date: July 1, 2005
Creator: Jacobson, Jacob J.; Yacout, A. M.; Matthern, G. E.; Piet, S. J. & Moisseytsev, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Next Generation Nuclear Plant Materials Research and Development Program Plan

Description: The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. T… more
Date: September 1, 2004
Creator: Hayner, G. O. & Shaber, E.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Update On Monolithic Fuel Fabrication Development

Description: Efforts to develop a viable monolithic research reactor fuel plate have continued at Idaho National Laboratory. These efforts have concentrated on both fabrication process refinement and scale-up to produce full sized fuel plates. Advancements have been made in the production of U-Mo foil including full sized foils. Progress has also been made in the friction stir welding and transient liquid phase bonding fabrication processes resulting in better bonding, more stable processes and the ability … more
Date: November 1, 2005
Creator: Clark, C. R; Wight, J. M.; Knighton, G. C.; Moore, G. A. & Jue, J. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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University Reactor Conversion Lessons Learned Workshop for Texas A&M University Nuclear Science Center Reactor

Description: The objectives of this meeting were to capture the observations, insights, issues, concerns, and ideas of those involved in the Texas A&M University Nuclear Science Center (TAMU NSC) TRIGA Reactor Conversion so that future efforts can be conducted with greater effectiveness, efficiency, and with fewer challenges. This workshop was held in conjunction with a similar workshop for the University of Florida Reactor Conversion. Some of the generic lessons from that workshop are included in this repo… more
Date: April 1, 2007
Creator: Woolstenhulme, Eric C. & Meyer, Dana M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHARACTERIZATION OF AN ADVANCED GADOLINIUM NEUTRON ABSORBER ALLOY BY MEANS OF NEUTRON TRANSMISSION

Description: Neutron transmission experiments were performed on samples of an advanced nickel-chromium-molybdenum-gadolinium (Ni-Cr-Mo-Gd) neutron absorber alloy. The primary purpose of the experiments was to demonstrate the thermal neutron absorbing capability of the alloy at specific gadolinium dopant levels. The new alloy is to be deployed for criticality control of highly enriched DOE SNF. For the transmission experiments, alloy test samples were fabricated with 0.0, 1.58 and 2.1 wt% natural gadolinium … more
Date: September 1, 2007
Creator: Wachs, Gregg W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Disposition of Unirradiated Sodium Bonded EBR-II Driver Fuel Elements and HEU Scrap: Work Performed for FY 2007

Description: Specific surplus high enriched uranium (HEU) materials at the Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) will be transferred to a designated off-site receiving facility. The DOE High Enriched Uranium Disposition Program Office (HDPO) will determine which materials, if any, will be prepared and transferred to an off-site facility for processing and eventual fabrication of fuel for nuclear reactors. These surplus HEU materials include approximately 7200 kg unirradiated sodi… more
Date: April 1, 2007
Creator: Moore, Karen A
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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