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Model for H/sup -/ and D/sup -/ production by hydrogen backscattering

Description: The Marlowe Monte-Carlo backscattering code has been used to calculate particle reflection coefficients and energy distributions for H, D incident upon Li, K, Ni, Cu, Mo, Ag, Cs, Hf, W, Pt, and U surfaces. The backscattered energy and angular distributions are combined with a model for formation and survival probabilities for H/sup -/, D/sup -/ leaving the surface. A least-squares fit of experimental measurements of H/sup -/ yields from the composite surface, Cs/Cu, has been used to obtain two … more
Date: May 27, 1980
Creator: Hiskes, J.R. & Schneider, P.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Formation of hydrogen negative ions by surface and volume processes with application to negative ion sources

Description: During the last few decades interest in negative-hydrogen ion sources has been directed mainly toward synchrotron and other particle accelerator applications, with emphasis on high current densities delivered for short pulses. But within the last several years there has been an awareness in the magnetic fusion program of the future need for negative ions as a means for generating high energy neutral beams, beams with energies above a few hundred keV. Negative ions seem to be the only effective … more
Date: June 27, 1979
Creator: Hiskes, J.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The Separation of Trace Amounts of Radioactive Cs From Macro Quanitites of Sodium and Potassium Salts

Description: Summary: A method for the separation of cesium from macro quantities of sodium and potassium using an ion exchange resin, Dowex 50, has been developed. A 95% recovery of cesium with a reduction of the solid content of 95% was found possible. Curves illustrating the effect of acidity, column length, and flow rate are presented in the report. The sodium form, hydrogen form and ammonium form of Dowex 50 were investigated; the hydrogen form was found to give the best separation.
Date: January 27, 1950
Creator: Thorburn, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Molecular potentials and relaxation dynamics

Description: The use of empirical pseudopotentials, in evaluating interatomic potentials, provides an inexpensive and convenient method for obtaining highly accurate potential curves and permits the modeling of core-valence correlation, and the inclusion of relativistic effects when these are significant. As an example, recent calculations of the chi/sup 1/..sigma../sup +/ and a/sup 3/..sigma../sup +/ states of LiH, NaH, KH, RbH, and CsH and the chi/sup 2/..sigma../sup +/ states of their anions are discusse… more
Date: March 27, 1981
Creator: Karo, A.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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304L stainless steel resistance to cesium chloride

Description: B and W Hanford Company have two Oak Ridge National Laboratory (ORNL) Type 4 canisters filled with cesium chloride (CsCl) originally produced at WESF (Waste Encapsulation and Storage Facility). These canisters are constructed of 304L stainless steel per drawing ORNL 970-294. Instead of removing the CsCl from the Type 4 canisters and repacking into an Inner Capsule, it is intended (for ALARA, schedule and cost purposes) that the Type 4 canisters be decontaminated (scrubbed) and placed [whole] in… more
Date: August 27, 1998
Creator: Graves, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fission product security problem

Description: Reference (2) requested that we review the possibilities that classified information might be revealed by isotopic composition of fission products, and suggest methods of making any such compositions. These questions have been reviewed thoroughly by Hanford Laboratories experts; their analysis confirms earlier conclusions (Reference 1). Based on current classification guides, isotopic compositions of cesium, promethium, and probably other rate earths could reveal secret information. Unless clas… more
Date: February 27, 1964
Creator: Warren, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Hanford Site Tank Waste Remediation System: An update

Description: The U.S. Department of Energy`s Hanford Site, located in southeastern Washington State, has the most diverse and largest amount of highly radioactive waste in the United States. High-level radioactive waste has been stored in large underground tanks since 1944. Approximately 230,000 m{sup 3} (61 Mgal) of caustic liquids, slurries, saltcakes, and sludges have {sup 137}Cs accumulated in 177 tanks. In addition, significant amounts of {sup 90}Sr and were removed from the tank waste, converted to sa… more
Date: January 27, 1994
Creator: Alumkal, W. T.; Babad, H.; Harmon, H. D. & Wodrich, D. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The Separation of Trace Amounts of Radioactive Cs From Macro Quantities of Sodium and Potassium Salts

Description: Recent attempts to separate fission products from urine salts in a form suitable for measurement by beta counting have involved the use of ion exchange resins to remove the ions present in macro quantities leaving the trace elements behind as a {open_quotes}thin{close_quotes} sample for counting techniques. The separation of Cs from Na and K was chosen as the starting point because of the relative difficulty of separating these elements with ordinary chemical techniques. This report describes t… more
Date: January 27, 1950
Creator: Thorburn, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility study for use of a germanium detector in the LOFT gamma-ray densitometer

Description: The primary aim of this study is to predict the performance of a gamma-ray densitometer system using computer modeling techniques. The system consists of a collimated /sup 137/Cs source, a pipe containing a variable amount of water absorber, and a shielded and collimated germanium detector system. The gamma-ray energy spectrum (number of photon counts as a function of energy) has been computed for several sources at the detector. The response for combined sourceconfigurations has been obtained … more
Date: April 27, 1976
Creator: Swierkowski, S. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RESULTS OF CESIUM MASS TRANSFER TESTING FOR NEXT GENERATION SOLVENT WITH HANFORD WASTE SIMULANT AP-101

Description: SRNL has performed an Extraction, Scrub, Strip (ESS) test using the next generation solvent and AP-101 Hanford Waste simulant. The results indicate that the next generation solvent (MG solvent) has adequate extraction behavior even in the face of a massive excess of potassium. The stripping results indicate poorer behavior, but this may be due to inadequate method detection limits. SRNL recommends further testing using hot tank waste or spiked simulant to provide for better detection limits. Fu… more
Date: September 27, 2011
Creator: Peters, T.; Washington, A. & Fink, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Demonstration of the Next-Generation Caustic-Side Solvent Extraction Solvent With 2-cm Centrifugal Contractors Using Tank 49H Waste and Waste Simulant

Description: Researchers successfully demonstrated the chemistry and process equipment of the Caustic-Side Solvent Extraction (CSSX) flowsheet using MaxCalix for the decontamination of high level waste (HLW). The demonstration was completed using a 12-stage, 2-cm centrifugal contactor apparatus at the Savannah River National Laboratory (SRNL). This represents the first CSSX process demonstration of the MaxCalix solvent system with Savannah River Site (SRS) HLW. Two tests lasting 24 and 27 hours processed no… more
Date: September 27, 2011
Creator: Pierce, R. A.; Peters, T. B.; Crowder, M. L.; Caldwell, T. D.; Pak, D. J.; Fink, S. D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HIGH ASPECT RATIO ION EXCHANGE RESIN BED - HYDRAULIC RESULTS FOR SPERICAL RESIN BEADS

Description: A principal role of the DOE Savannah River Site is to safely dispose of a large volume of liquid nuclear waste held in many storage tanks. An in-tank ion exchange unit is being considered for cesium removal to accelerate waste processing. This unit is planned to have a relatively high bed height to diameter ratio (10:1). Complicating the design is the need to cool the ion exchange media; therefore, the ion exchange column will have a central cooling core making the flow path annular. To separat… more
Date: September 27, 2007
Creator: Duignan, M; Charles Nash, C & Timothy Punch, T
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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PROCESSING ALTERNATIVES FOR DESTRUCTION OF TETRAPHENYLBORATE

Description: Two processes were chosen in the 1980's at the Savannah River Site (SRS) to decontaminate the soluble High Level Waste (HLW). The In Tank Precipitation (ITP) process (1,2) was developed at SRS for the removal of radioactive cesium and actinides from the soluble HLW. Sodium tetraphenylborate was added to the waste to precipitate cesium and monosodium titanate (MST) was added to adsorb actinides, primarily uranium and plutonium. Two products of this process were a low activity waste stream and a … more
Date: February 27, 2007
Creator: Lambert, D; Thomas Peters, T & Samuel Fink, S
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Multiple Ion Exchange Column Tests for Technetium Removal from Hanford Tank Waste Supernate

Description: Five cycles of loading, elution, and regeneration were performed to remove technetium from a Hanford waste sample retrieved from Tank 241-AW-101 using SuperLig 639 resin. The waste sample was diluted to 4.95 M Na plus and then was processed to remove 137Cs through dual ion exchange columns each containing 15 mL of SuperLig 644. To remove 99Tc, the cesium decontaminated solution was processed downwards through two ion exchange columns, each containing 12 mL of SuperLig 639 resin. The columns, de… more
Date: February 27, 2004
Creator: Hassan, N. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Wastewater Triad Project: Final Summary Report

Description: The U.S. Department of Energy (DOE) facilities have performed nuclear energy research and radiochemical production since the early 1940s. Currently, millions of gallons of legacy radioactive liquid and sludge wastes are contained in over 300 large underground storage tanks, located primarily at Hanford, the Savannah River Site (SRS), Idaho National Engineering and Environmental Laboratory (INEEL), and Oak Ridge National Laboratory (ORNL). Plans for tank waste retrieval, treatment, and immobiliz… more
Date: December 27, 2001
Creator: Walker, J.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Model for Predicting Fission Product Activities in Reactor Coolant: Application of Model for Estimating I-129 Levels in Radioactive Waste

Description: A general model was developed to estimate the activities of fission products in reactor coolant and hence to predict a value for the I-129/Cs-137 scaling factor; the latter can be applied along with measured Cs-137 activities to estimate I-129 levels in reactor waste. The model accounts for fission product release from both defective fuel rods and uranium contamination present on in-core reactor surfaces. For simplicity, only the key release mechanisms were modeled. A mass balance, considering … more
Date: February 27, 2003
Creator: Lewis, B. J. & Husain, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The isolation and packaging of fission products at Hanford

Description: Research and development work on the removal of specific fission products from aqueous wastes has been in progress at the Hanford Atomic Products operation for several years. Initially, the primary incentive lay in the safe and economic disposal of these wastes. Scavenging techniques were developed which permitted the precipitation of the long-lived and biologically hazardous fission products cesium and strontium and the subsequent discharge of the supernates to the soil. Recently, interest has… more
Date: June 27, 1956
Creator: Tomlinson, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Testing of stripping columns for the removal of benzene from aqueous radioactive salt solution

Description: Radioactive high level wastes (HLW) generated from production of special nuclear materials at the Savannah River Site (SRS) are held in interim storage in 51 underground, million gallon tanks. Radioactive cesium ({sup 137}Cs) is segregated by evaporation of aqueous waste solution for interim storage in a salt matrix comprised of Na and K salts or in concentrated salt solution. The saltcake will be dissolved and {sup 137}Cs will be separated from the nonradioactive salts in solution in the In-Ta… more
Date: June 27, 1995
Creator: Georgeton, G. K.; Taylor, G. A. & Gaughan, T. P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Program overview: Remedial actions at Oak Ridge National Laboratory

Description: Research on and development of civilian and defense uses of nuclear materials and technologies have occurred at Oak Ridge National Laboratory (ORNL) since its creation as part of the World War II Manhattan Project in 1943. A diverse legacy of contaminated inactive facilities, research areas, and waste management areas exists; many are candidates for remedial action. Most attention is focused on waste management sites which contain the bulk of ORNL's environmental contamination. A wide variety o… more
Date: July 27, 1988
Creator: Bates, L.D. & Trabalka, J.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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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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Significant volume reduction of tank waste by selective crystallization: 1994 Annual report

Description: The objective of this technology task plan is to develop and demonstrate a scaleable process of reclaim sodium nitrate (NaNO{sub 3}) from Hanford waste tanks as a clean nonradioactive salt. The purpose of the so-called Clean Salt Process is to reduce the volume of low level waste glass by as much as 70%. During the reporting period of October 1, 1993, through May 31, 1994, progress was made on four fronts -- laboratory studies, surrogate waste compositions, contracting for university research, … more
Date: September 27, 1994
Creator: Herting, D. L. & Lunsford, T. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Ion Exchange Modeling for Removal of Cesium from Hanford Waste Using Hydrous Crystalline Silicotitanate Material

Description: For the current pretreatment facility design of the River Protection Project (RPP) Waste Treatment Plant (WTP), the removal of cesium from low activity waste (LAW) is achieved by ion-exchange technology based on SuperLig(R) 644 resin. Due to recent concerns over potential radiological and chemical degradation of SuperLig(R) 644 resin and increased pressure drops observed during pilot-scale column studies, an increased interest in developing a potential backup ion-exchanger material has resulted… more
Date: July 27, 2004
Creator: HAMM, LUTHER L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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