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RHEOLOGY OF SETTLED SOLIDS IN THE SMALL COLUMN ION EXCHANGE PROCESS

Description: The Small Column Ion Exchange (SCIX) process is being developed to remove cesium, strontium, and actinides from Savannah River Site (SRS) Liquid Waste using an existing waste tank (i.e., Tank 41H) to house the process. This process adds monosodium titanate (MST) to a waste tank containing salt solution (and entrained sludge solids). While the process is operating, the solid particles will begin to settle at temperatures up to 45 C. Previous testing has shown that sludge-MST slurries that sit fo… more
Date: January 27, 2011
Creator: Poirier, M.; Ferguson, C. & Koopman, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PILOT SCALE TESTING OF MONOSODIUM TITANATE MIXING FOR THE SRS SMALL COLUMN ION EXCHANGE PROCESS - 11224

Description: The Small Column Ion Exchange (SCIX) process is being developed to remove cesium, strontium, and select actinides from Savannah River Site (SRS) Liquid Waste using an existing waste tank (i.e., Tank 41H) to house the process. Savannah River National Laboratory (SRNL) is conducting pilot-scale mixing tests to determine the pump requirements for suspending monosodium titanate (MST), crystalline silicotitanate (CST), and simulated sludge. The purpose of this pilot scale testing is to determine the… more
Date: January 25, 2011
Creator: Poirier, M.; Restivo, M.; Williams, M.; Herman, D. & Steeper, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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INVESTIGATING SUSPENSION OF MST SLURRIES IN A PILOT-SCALE WASTE TANK

Description: The Small Column Ion Exchange (SCIX) process is being developed to remove cesium, strontium, and actinides from Savannah River Site (SRS) Liquid Waste using an existing waste tank (i.e., Tank 41H) to house the process. Savannah River National Laboratory (SRNL) is conducting pilot-scale mixing tests to determine the pump requirements for suspending monosodium titanate (MST), crystalline silicotitanate (CST), and simulated sludge. The purpose of this pilot scale testing is for the pumps to suspen… more
Date: January 24, 2011
Creator: Poirier, M.; Restivo, M.; Steeper, T.; Williams, M. & Qureshi, Z.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FURTHER DEVELOPMENT OF MODIFIED MONOSODIUM TITANATE, AN IMPROVED SORBENT FOR PRETREATMENT OF HIGH LEVEL NUCLEAR WASTE AT THE SAVANNAH RIVER SITE

Description: High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove Cs-137, Sr-90, and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. Separation processes planned at SRS include caustic side solvent extraction, for Cs-137 removal, and sorption of Sr-90 and alpha-emitting radionuclides onto monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline was… more
Date: January 12, 2011
Creator: Taylor-Pashow, K.; Hobbs, D.; Fondeur, F. & Fink, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - Vandellos II Reactor

Description: This report is one of the several recent NUREG/CR reports documenting benchmark-quality radiochemical assay data and the use of the data to validate computer code predictions of isotopic composition for spent nuclear fuel, to establish the uncertainty and bias associated with code predictions. The experimental data analyzed in the current report were acquired from a high-burnup fuel program coordinated by Spanish organizations. The measurements included extensive actinide and fission product da… more
Date: January 1, 2011
Creator: Ilas, Germina & Gauld, Ian C
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FY2010 Annual Report for the Actinide Isomer Detection Project

Description: This project seeks to identify a new signature for actinide element detection in active interrogation. This technique works by exciting and identifying long-lived nuclear excited states (isomers) in the actinide isotopes and/or primary fission products. Observation of isomers in the fission products will provide a signature for fissile material. For the actinide isomers, the decay time and energy of the isomeric state is unique to a particular isotope, providing an unambiguous signature for Spe… more
Date: January 1, 2011
Creator: Warren, Glen A.; Francy, Christopher J.; Ressler, Jennifer J.; Erikson, Luke E.; Miller, Erin A. & Hatarik, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development and Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control

Description: Ultraviolet-Visible Spectroscopy (UV-Visible) and Time Resolved Laser Fluorescence Spectroscopy (TRLFS) optical techniques can permit on-line, real-time analysis of the actinide elements in a solvent extraction process. UV-Visible and TRLFS techniques have been used for measuring the speciation and concentration of the actinides under laboratory conditions. These methods are easily adaptable to multiple sampling geometries, such as dip probes, fiber-optic sample cells, and flow-through cell geo… more
Date: December 29, 2010
Creator: Czerwinski, Ken; Weck, Phil & Poineau, Frederic
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHARACTERIZATION OF MODIFIED MONOSODIUM TITANATE - AN IMPROVED SORBENT FOR STRONTIUM AND ACTINIDE SEPARATIONS

Description: High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove {sup 134,137}Cs, {sup 90}Sr, and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. An inorganic sorbent, monosodium titanate (MST), is currently used to remove {sup 90}Sr and alpha-emitting radionuclides, while a caustic-side solvent extraction process is used for removing {sup 134,137}Cs. A new peroxotitanate material, mo… more
Date: December 21, 2010
Creator: Hobbs, D.; Taylor-Pashow, K. & Missimer, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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PLANTS AS BIO-MONITORS FOR 137CS, 238PU, 239, 240PU AND 40K AT THE SAVANNAH RIVER SITE

Description: The nuclear fuel cycle generates a considerable amount of radioactive waste, which often includes nuclear fission products, such as strontium-90 ({sup 90}Sr) and cesium-137 ({sup 137}Cs), and actinides such as uranium (U) and plutonium (Pu). When released into the environment, large quantities of these radionuclides can present considerable problems to man and biota due to their radioactive nature and, in some cases as with the actinides, their chemical toxicity. Radionuclides are expected to d… more
Date: December 16, 2010
Creator: Caldwell, E.; Duff, M. & Ferguson, C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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SCALING SOLID RESUSPENSION AND SORPTION FOR THE SMALL COLUMN ION EXCHANGE PROCESSING TANK

Description: The Small Column Ion Exchange (SCIX) process is being developed to remove cesium, strontium, and actinides from Savannah River Site (SRS) Liquid Waste using an existing 1.3 million gallon waste tank (i.e., Tank 41H) to house the process. Savannah River National Laboratory (SRNL) is conducting pilot-scale mixing tests to determine the pump requirements for suspending and resuspending Monosodium Titanate (MST), Crystalline Silicotitanate (CST), and simulated sludge. In addition, SRNL will also be… more
Date: December 14, 2010
Creator: Poirier, M. & Qureshi, Z.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Test Plan for Solvent Extraction Data Acquisition to Support Modeling Efforts

Description: This testing will support NEAMS SafeSep Modeling efforts related to droplet simulation in liquid-liquid extraction equipment. Physical characteristic determinations will be completed for the fluids being used in the experiment including viscosity, density, surface tension, distribution coefficients, and diffusion coefficients. Then, experiments will be carried out to provide data for comparison to the simulation’s calculation of mass transfer coefficients. Experiments will be conducted with sol… more
Date: December 1, 2010
Creator: Rutledge, Veronica; Christensen, Kristi; Garn, Troy & Law, Jack
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fabrication of a 238Pu target

Description: Precision neutron-induced reaction data are important for modeling the network of isotope production and destruction within a given diagnostic chain. This network modeling has many applications such as the design of advanced fuel cycle for reactors and the interpretation of radiochemical data related to the stockpile stewardship and nuclear forensics projects. Our current funded effort is to improve the neutron-induced reaction data on the short-lived actinides and the specific goal is to impro… more
Date: November 16, 2010
Creator: Wu, C Y; Chyzh, A; Kwan, E; Henderson, R; Gostic, J & Carter, D
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE HYDROTHERMAL REACTIONS OF MONOSODIUM TITANATE, CRYSTALLINE SILICOTITANATE AND SLUDGE IN THE MODULAR SALT PROCESS: A LITERATURE SURVEY

Description: The use of crystalline silicotitanate (CST) is proposed for an at-tank process to treat High Level Waste at the Savannah River Site. The proposed configuration includes deployment of ion exchange columns suspended in the risers of existing tanks to process salt waste without building a new facility. The CST is available in an engineered form, designated as IE-911-CW, from UOP. Prior data indicates CST has a proclivity to agglomerate from deposits of silica rich compounds present in the alkaline… more
Date: November 11, 2010
Creator: Fondeur, F.; Pennebaker, F. & Fink, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Compact fission counter for DANCE

Description: The Detector for Advanced Neutron Capture Experiments (DANCE) consists of 160 BF{sub 2} crystals with equal solid-angle coverage. DANCE is a 4{pi} {gamma}-ray calorimeter and designed to study the neutron-capture reactions on small quantities of radioactive and rare stable nuclei. These reactions are important for the radiochemistry applications and modeling the element production in stars. The recognition of capture event is made by the summed {gamma}-ray energy which is equivalent of the reac… more
Date: November 6, 2010
Creator: Wu, C. Y.; Chyzh, A.; Kwan, E.; Henderson, R.; Gostic, J.; Carter, D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analyzing Losses: Transuranics into Waste and Fission Products into Recycled Fuel

Description: All mass streams from separations and fuel fabrication are products that must meet criteria. Those headed for disposal must meet waste acceptance criteria (WAC) for the eventual disposal sites corresponding to their waste classification. Those headed for reuse must meet fuel or target impurity limits. A “loss” is any material that ends up where it is undesired. The various types of losses are linked in the sense that as the loss of transuranic (TRU) material into waste is reduced, often the los… more
Date: November 1, 2010
Creator: Piet, Steven J.; Soelberg, Nick R.; Bays, Samuel E.; Cherry, Robert E.; Pincock, Layne F.; Shaber, Eric L. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Filling Knowledge Gaps with Five Fuel Cycle Studies

Description: During FY 2010, five studies were conducted of technology families’ applicability to various fuel cycle strategies to fill in knowledge gaps in option space and to better understand trends and patterns. Here, a “technology family” is considered to be defined by a type of reactor and by selection of which actinides provide fuel. This report summarizes the higher-level findings; the detailed analyses and results are documented in five individual reports, as follows: • Advanced once through with u… more
Date: November 1, 2010
Creator: Piet, Steven J.; Gehin, Jess; Halsey, William & Taiwo, Temitope
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FLUX SENSOR EVALUATIONS AT THE ATR CRITICAL FACILITY

Description: The Advanced Test Reactor (ATR) and the ATR Critical (ATRC) facilities lack real-time methods for detecting thermal neutron flux and fission reaction rates for irradiation capsules. Direct measurements of the actual power deposited into a test are now possible without resorting to complicated correction factors. In addition, it is possible to directly measure minor actinide fission reaction rates and to provide time-dependent monitoring of the fission reaction rate or fast/thermal flux during t… more
Date: November 1, 2010
Creator: Unruh, Troy; Rempe, Joy; Nigg, David; Imel, George; Harris, Jason & Bonebrake, Eric
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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HTGR Technology Family Assessment for a Range of Fuel Cycle Missions

Description: This report examines how the HTGR technology family can provide options for the once through, modified open cycle (MOC), or full recycle fuel cycle strategies. The HTGR can serve all the fuel cycle missions that an LWR can; both are thermal reactors. Additional analyses are warranted to determine if HTGR “full recycle” service could provide improved consumption of transuranic (TRU) material than LWRs (as expected), to analyze the unique proliferation resistance issues associated with the “pebbl… more
Date: November 1, 2010
Creator: Piet, Steven J.; Bays, Samuel E. & Soelberg, Nick R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Implications of Fast Reactor Transuranic Conversion Ratio

Description: Theoretically, the transuranic conversion ratio (CR), i.e. the transuranic production divided by transuranic destruction, in a fast reactor can range from near zero to about 1.9, which is the average neutron yield from Pu239 minus 1. In practice, the possible range will be somewhat less. We have studied the implications of transuranic conversion ratio of 0.0 to 1.7 using the fresh and discharge fuel compositions calculated elsewhere. The corresponding fissile breeding ratio ranges from 0.2 to 1… more
Date: November 1, 2010
Creator: Piet, Steven J.; Hoffman, Edward A. & Bays, Samuel E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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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
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A Study of Fast Reactor Fuel Transmutation in a Candidate Dispersion Fuel Design

Description: Dispersion fuels represent a significant departure from typical ceramic fuels to address swelling and radiation damage in high burnup fuel. Such fuels use a manufacturing process in which fuel particles are encapsulated within a non-fuel matrix. Dispersion fuels have been studied since 1997 as part of an international effort to develop and test very high density fuel types for the Reduced Enrichment for Research and Test Reactors (RERTR) program.[1] The Idaho National Laboratory is performing r… more
Date: November 1, 2010
Creator: DeHart, Mark; Zhang, Hongbin; Shaber, Eric & Jesse, Matthew
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Sustained Recycle in Light Water and Sodium-Cooled Reactors

Description: From a physics standpoint, it is feasible to sustain recycle of used fuel in either thermal or fast reactors. This paper examines multi-recycle potential performance by considering three recycling approaches and calculating several fuel cycle parameters, including heat, gamma, and neutron emission of fresh fuel; radiotoxicity of waste; and uranium utilization. The first recycle approach is homogeneous mixed oxide (MOX) fuel assemblies in a light water reactor (LWR). The transuranic portion of t… more
Date: November 1, 2010
Creator: Piet, Steven J.; Bays, Samuel E.; Pope, Michael A. & Youinou, Gilles J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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TALSPEAK CURVE: AN ILLUSTRATION OF A SEE-SAW EFFECT IN SEPARATIONS

Description: A superbly balanced thermodynamic struggle for metal ion coordination by aqueous aminopolycarboxylate reagent, DTPA, and non-aqueous organophosphorous phase transfer reagent, HDEHP, affords the separation of trivalent actinides from trivalent lanthanides under the umbrella of the Talspeak liquid-liquid distribution process. This thermodynamic relationship has been linked to an analogous “see-saw” behavior, where the balance is distorted when either of the key complexing players is subject to ad… more
Date: November 1, 2010
Creator: Zalupski, Peter & Martin, Leigh
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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THERMAL MODELING ANALYSIS OF CST MEDIA IN THE SMALL COLUMN ION EXCHANGE PROJECT

Description: Models have been developed to simulate the thermal characteristics of Crystalline Silicotitanate (CST) ion exchange media fully loaded with radioactive cesium in a column configuration and distributed within a waste storage tank. This work was conducted to support the Small Column Ion Exchange (SCIX) program which is focused on processing dissolved, high-sodium salt waste for the removal of specific radionuclides (including Cs-137, Sr-90, and actinides) within a High Level Waste (HLW) storage t… more
Date: November 1, 2010
Creator: Lee, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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