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1

Actinide separations conference  

Science Conference Proceedings (OSTI)

This report contains the abstracts for 55 presentations given at the fourteenth annual Actinide Separations Conference. (JDL)

Not Available

1990-01-01T23:59:59.000Z

2

2011 Actinide Separations Conference  

NLE Websites -- All DOE Office Websites (Extended Search)

of actinide chemistry and will play an important role in the future of the nuclear fuel cycle, nuclear medicine, and nuclear nonproliferation activities. The conference also...

3

33rd Actinide Separations Conference  

SciTech Connect

Welcome to the 33rd Actinide Separations Conference hosted this year by the Lawrence Livermore National Laboratory. This annual conference is centered on the idea of networking and communication with scientists from throughout the United States, Britain, France and Japan who have expertise in nuclear material processing. This conference forum provides an excellent opportunity for bringing together experts in the fields of chemistry, nuclear and chemical engineering, and actinide processing to present and discuss experiences, research results, testing and application of actinide separation processes. The exchange of information that will take place between you, and other subject matter experts from around the nation and across the international boundaries, is a critical tool to assist in solving both national and international problems associated with the processing of nuclear materials used for both defense and energy purposes, as well as for the safe disposition of excess nuclear material. Granlibakken is a dedicated conference facility and training campus that is set up to provide the venue that supports communication between scientists and engineers attending the 33rd Actinide Separations Conference. We believe that you will find that Granlibakken and the Lake Tahoe views provide an atmosphere that is stimulating for fruitful discussions between participants from both government and private industry. We thank the Lawrence Livermore National Laboratory and the United States Department of Energy for their support of this conference. We especially thank you, the participants and subject matter experts, for your involvement in the 33rd Actinide Separations Conference.

McDonald, L M; Wilk, P A

2009-05-04T23:59:59.000Z

4

2011 Actinide Separations Conference  

NLE Websites -- All DOE Office Websites (Extended Search)

15th. Click here to access the Registration Form. Conference Fee: 300.00 (includes Banquet)* Student Fee 160.00 (includes Banquet)* Banquet Fee for spouse or guest: 45.00 per...

5

30th Actinide Separations Conference, PNNL-SA-50126  

SciTech Connect

Program booklet for the 30th Actinide Separations Conference. Contains agenda and abstracts for 27 poster and 38 oral presentations to be made during the 3-day meeting, May 23-25, 2006.

Delegard, Calvin H.

2006-05-25T23:59:59.000Z

6

Nineteenth annual actinide separations conference: Conference program and abstracts  

SciTech Connect

This report contains the abstracts from the conference presentations. Sessions were divided into the following topics: Waste treatment; Spent fuel treatment; Issues and responses to Defense Nuclear Facility Safety Board 94-1; Pyrochemical technologies; Disposition technologies; and Aqueous separation technologies.

Bronson, M. [ed.

1995-12-31T23:59:59.000Z

7

2011 Actinide Separations Conference  

NLE Websites -- All DOE Office Websites (Extended Search)

8:00 - 11:30 am: Oral Presentations 1:00 - 5:00 pm: Oral Presentations 6:30 - 9:00 pm: Banquet home contacts hotel register button deadlines seaborg award abstracts button agenda...

8

Separation of actinides from lanthanides  

DOE Patents (OSTI)

An organic extracting solution and an extraction method useful for separating elements of the actinide series of the periodic table from elements of the lanthanide series, where both are in trivalent form is described. The extracting solution consists of a primary ligand and a secondary ligand, preferably in an organic solvent. The primary ligand is a substituted monothio-1,3-dicarbonyl, which includes a substituted 4-acyl-2-pyrazolin-5-thione, such as 4-benzoyl-2,4- dihydro-5-methyl-2-phenyl-3H-pyrazol-3-thione (BMPPT). The secondary ligand is a substituted phosphine oxide, such as trioctylphosphine oxide (TOPO).

Smith, B.F.; Jarvinen, G.D.; Ryan, R.R.

1988-03-31T23:59:59.000Z

9

Actinide separations by supported liquid membranes  

SciTech Connect

The work has demonstrated that actinide removal from synthetic waste solutions using both flat-sheet and hollow-fiber SLM's is a feasible chemical process at the laboratory scale level. The process is characterized by the typical features of SLM's processes: very small quantities of extractant required; the potential for operations with high feed/strip volume ratios, resulting in a corresponding concentration factor of the actinides; and simplicity of operation. Major obstacles to the implementation of the SLM technology to the decontamination of liquid nuclear wastes are the probable low resistance of polypropylene supports to high radiation fields, which may prevent the application to high-level nuclear wastes; the unknown lifetime of the SLM; and the high Na content of the separated actinide solution.

Danesi, P.R.; Horwitz, E.P.; Rickert, P.; Chiarizia, R.

1984-01-01T23:59:59.000Z

10

Actinide and lanthanide separation process (ALSEP)  

DOE Patents (OSTI)

The process of the invention is the separation of minor actinides from lanthanides in a fluid mixture comprising, fission products, lanthanides, minor actinides, rare earth elements, nitric acid and water by addition of an organic chelating aid to the fluid; extracting the fluid with a solvent comprising a first extractant, a second extractant and an organic diluent to form an organic extractant stream and an aqueous raffinate. Scrubbing the organic stream with a dicarboxylic acid and a chelating agent to form a scrubber discharge. The scrubber discharge is stripped with a simple buffering agent and a second chelating agent in the pH range of 2.5 to 6.1 to produce actinide and lanthanide streams and spent organic diluents. The first extractant is selected from bis(2-ethylhexyl)hydrogen phosphate (HDEHP) and mono(2-ethylhexyl)2-ethylhexyl phosphonate (HEH(EHP)) and the second extractant is selected from N,N,N,N-tetra-2-ethylhexyl diglycol amide (TEHDGA) and N,N,N',N'-tetraoctyl-3-oxapentanediamide (TODGA).

Guelis, Artem V.

2013-01-15T23:59:59.000Z

11

Separations and Actinide Science -- 2005 Roadmap  

SciTech Connect

The Separations and Actinide Science Roadmap presents a vision to establish a separations and actinide science research (SASR) base composed of people, facilities, and collaborations and provides new and innovative nuclear fuel cycle solutions to nuclear technology issues that preclude nuclear proliferation. This enabling science base will play a key role in ensuring that Idaho National Laboratory (INL) achieves its long-term vision of revitalizing nuclear energy by providing needed technologies to ensure our nation's energy sustainability and security. To that end, this roadmap suggests a 10-year journey to build a strong SASR technical capability with a clear mission to support nuclear technology development. If nuclear technology is to be used to satisfy the expected growth in U.S. electrical energy demand, the once-through fuel cycle currently in use should be reconsidered. Although the once-through fuel cycle is cost-effective and uranium is inexpensive, a once-through fuel cycle requires long-term disposal to protect the environment and public from long-lived radioactive species. The lack of a current disposal option (i.e., a licensed repository) has resulted in accumulation of more than 50,000 metric tons of spent nuclear fuel. The process required to transition the current once-through fuel cycle to full-recycle will require considerable time and significant technical advancement. INL's extensive expertise in aqueous separations will be used to develop advanced separations processes. Computational chemistry will be expanded to support development of future processing options. In the intermediate stage of this transition, reprocessing options will be deployed, waste forms with higher loading densities and greater stability will be developed, and transmutation of long-lived fission products will be explored. SASR will support these activities using its actinide science and aqueous separations expertise. In the final stage, full recycle will be enabled by advanced reactors and reprocessing methods based on pyrochemical methods and by using different fuel cycles that do not readily produce plutonium. SASR will facilitate the deployment of advanced pyrochemical separation technology and support development of reprocessing of thorium-based reactor fuels.

2005-09-01T23:59:59.000Z

12

Process to remove actinides from soil using magnetic separation  

DOE Patents (OSTI)

A process of separating actinide-containing components from an admixture including forming a slurry including actinide-containing components within an admixture, said slurry including a dispersion-promoting surfactant, adjusting the pH of the slurry to within a desired range, and, passing said slurry through a pretreated matrix material, said matrix material adapted to generate high magnetic field gradients upon the application of a strong magnetic field exceeding about 0.1 Tesla whereupon a portion of said actinide-containing components are separated from said slurry and remain adhered upon said matrix material is provided.

Avens, Larry R. (Los Alamos, NM); Hill, Dallas D. (Los Alamos, NM); Prenger, F. Coyne (Los Alamos, NM); Stewart, Walter F. (Las Cruces, NM); Tolt, Thomas L. (Los Alamos, NM); Worl, Laura A. (Los Alamos, NM)

1996-01-01T23:59:59.000Z

13

Citrate based ``TALSPEAK`` lanthanide-actinide separation process  

SciTech Connect

The potential hazard posed to future generations by long-lived radionuclides such as the transuranic elements (TRU) is perceived as a major problem associated with the use of nuclear power. TRU wastes have to remain isolated from the environment for ``geological`` periods of time. The costs of building, maintaining, and operating a ``geological TRU repository`` can be very high. Therefore, there are significant economical advantages in segregating the relatively low volume of TRU wastes from other nuclear wastes. The chemical behavior of lanthanides and actinides, 4f and 5f elements respectively, is rather similar. As a consequence, the separation of these two groups is difficult. The ``TALSPEAK`` process (Trivalent Actinide Lanthanide Separations by Phosphorus-reagent Extraction from Aqueous Complexes) is one of the few means available to separate the trivalent actinides from the lanthanides. The method is based on the preferential complexation of the trivalent actinides by an aminopolyacetic acid. Cold experiments showed that by using citric acid the deleterious effects produced by impurities such as zirconium are greatly reduced.

Del Cul, G.D.; Bond, W.D.; Toth, L.M.; Davis, G.D.; Dai, S.; Metcalf, D.H.

1994-09-01T23:59:59.000Z

14

RAPID SEPARATION METHOD FOR ACTINIDES IN EMERGENCY SOIL SAMPLES  

Science Conference Proceedings (OSTI)

A new rapid method for the determination of actinides in soil and sediment samples has been developed at the Savannah River Site Environmental Lab (Aiken, SC, USA) that can be used for samples up to 2 grams in emergency response situations. The actinides in soil method utilizes a rapid sodium hydroxide fusion method, a lanthanum fluoride soil matrix removal step, and a streamlined column separation process with stacked TEVA, TRU and DGA Resin cartridges. Lanthanum was separated rapidly and effectively from Am and Cm on DGA Resin. Vacuum box technology and rapid flow rates are used to reduce analytical time. Alpha sources are prepared using cerium fluoride microprecipitation for counting by alpha spectrometry. The method showed high chemical recoveries and effective removal of interferences. This new procedure was applied to emergency soil samples received in the NRIP Emergency Response exercise administered by the National Institute for Standards and Technology (NIST) in April, 2009. The actinides in soil results were reported within 4-5 hours with excellent quality.

Maxwell, S.; Culligan, B.; Noyes, G.

2009-11-09T23:59:59.000Z

15

RAPID SEPARATION METHOD FOR ACTINIDES IN EMERGENCY AIR FILTER SAMPLES  

SciTech Connect

A new rapid method for the determination of actinides and strontium in air filter samples has been developed at the Savannah River Site Environmental Lab (Aiken, SC, USA) that can be used in emergency response situations. The actinides and strontium in air filter method utilizes a rapid acid digestion method and a streamlined column separation process with stacked TEVA, TRU and Sr Resin cartridges. Vacuum box technology and rapid flow rates are used to reduce analytical time. Alpha emitters are prepared using cerium fluoride microprecipitation for counting by alpha spectrometry. The purified {sup 90}Sr fractions are mounted directly on planchets and counted by gas flow proportional counting. The method showed high chemical recoveries and effective removal of interferences. This new procedure was applied to emergency air filter samples received in the NRIP Emergency Response exercise administered by the National Institute for Standards and Technology (NIST) in April, 2009. The actinide and {sup 90}Sr in air filter results were reported in {approx}4 hours with excellent quality.

Maxwell, S.; Noyes, G.; Culligan, B.

2010-02-03T23:59:59.000Z

16

Advanced Extraction Methods for Actinide/Lanthanide Separations  

SciTech Connect

The separation of An(III) ions from chemically similar Ln(III) ions is perhaps one of the most difficult problems encountered during the processing of nuclear waste. In the 3+ oxidation states, the metal ions have an identical charge and roughly the same ionic radius. They differ strictly in the relative energies of their f- and d-orbitals, and to separate these metal ions, ligands will need to be developed that take advantage of this small but important distinction. The extraction of uranium and plutonium from nitric acid solution can be performed quantitatively by the extraction with the TBP (tributyl phosphate). Commercially, this process has found wide use in the PUREX (plutonium uranium extraction) reprocessing method. The TRUEX (transuranium extraction) process is further used to coextract the trivalent lanthanides and actinides ions from HLLW generated during PUREX extraction. This method uses CMPO [(N, N-diisobutylcarbamoylmethyl) octylphenylphosphineoxide] intermixed with TBP as a synergistic agent. However, the final separation of trivalent actinides from trivalent lanthanides still remains a challenging task. In TRUEX nitric acid solution, the Am(III) ion is coordinated by three CMPO molecules and three nitrate anions. Taking inspiration from this data and previous work with calix[4]arene systems, researchers on this project have developed a C3-symmetric tris-CMPO ligand system using a triphenoxymethane platform as a base. The triphenoxymethane ligand systems have many advantages for the preparation of complex ligand systems. The compounds are very easy to prepare. The steric and solubility properties can be tuned through an extreme range by the inclusion of different alkoxy and alkyl groups such as methyoxy, ethoxy, t-butoxy, methyl, octyl, t-pentyl, or even t-pentyl at the ortho- and para-positions of the aryl rings. The triphenoxymethane ligand system shows promise as an improved extractant for both tetravalent and trivalent actinide recoveries form high level liquid wastes and a general actinide clean-up procedure. The selectivity of the standard extractant for tetravalent actinides, (N,N-diisobutylcarbamoylmethyl) octylphenylphosphineoxide (CMPO), was markedly improved by the attachment of three CMPO-like functions onto a triphenoxymethane platform, and a ligand that is both highly selective and effective for An(IV) ions was isolated. A 10 fold excess of ligand will remove virtually all of the 4+ actinides from the acidic layer without extracting appreciable quantities of An(III) and Ln(III) unlike simple CMPO ligands. Inspired by the success of the DIAMEX industrial process for extractions, three new tripodal chelates bearing three diglycolamide and thiodiglycolamide units precisely arranged on a triphenoxymethane platform have been synthesized for an highly efficient extraction of trivalent f-element cations from nitric acid media. A single equivalent of ligand will remove 80% of the Ln(III) ion from the acidic layer since the ligand is perfectly suited to accommodate the tricapped trigonal prismatic geometry preferred by the metal center. The ligand is perhaps the most efficient binder available for the heavier lanthanides and due to this unique attribute, the extraction event can be easily followed by 1H NMR spectroscopy confirming the formation of a TPP complex. The most lipophilic di-n-butyl tris-diglycolamide was found to be a significantly weaker extractant in comparison to the di-isopropyl analogs. The tris-thiodiglycolamide derivative proved to be an ineffective chelate for f-elements and demonstrated the importance of the etheric oxygens in the metal binding. The results presented herein clearly demonstrate a cooperative action of these three ligating groups within a single molecule, confirmed by composition and structure of the extracted complexes, and since actinides prefer to have high coordination numbers, the ligands should be particularly adept at binding with three arms. The use of such an extractant permits the extraction of metal ions form highly acidic environment through the ability

Scott, M.J.

2005-12-01T23:59:59.000Z

17

MINOR ACTINIDE SEPARATIONS USING ION EXCHANGERS OR IONIC LIQUIDS  

SciTech Connect

This project seeks to determine if (1) inorganic-based ion exchange materials or (2) electrochemical methods in ionic liquids can be exploited to provide effective Am and Cm separations. Specifically, we seek to understand the fundamental structural and chemical factors responsible for the selectivity of inorganic-based ion-exchange materials for actinide and lanthanide ions. Furthermore, we seek to determine whether ionic liquids can serve as the electrolyte that would enable formation of higher oxidation states of Am and other actinides. Experiments indicated that pH, presence of complexants and Am oxidation state exhibit significant influence on the uptake of actinides and lanthanides by layered sodium titanate and hybrid zirconium and tin phosphonate ion exchangers. The affinity of the ion exchangers increased with increasing pH. Greater selectivity among Ln(III) ions with sodium titanate materials occurs at a pH close to the isoelectric potential of the ion exchanger. The addition of DTPA decreased uptake of Am and Ln, whereas the addition of TPEN generally increases uptake of Am and Ln ions by sodium titanate. Testing confirmed two different methods for producing Am(IV) by oxidation of Am(III) in ionic liquids (ILs). Experimental results suggest that the unique coordination environment of ionic liquids inhibits the direct electrochemical oxidation of Am(III). The non-coordinating environment increases the oxidation potential to a higher value, while making it difficult to remove the inner coordination of water. Both confirmed cases of Am(IV) were from the in-situ formation of strong chemical oxidizers.

Hobbs, D.; Visser, A.; Bridges, N.

2011-09-20T23:59:59.000Z

18

Method for the concentration and separation of actinides from biological and environmental samples  

DOE Patents (OSTI)

A method and apparatus for the quantitative recover of actinide values from biological and environmental sample by passing appropriately prepared samples in a mineral acid solution through a separation column of a dialkyl(phenyl)-N,N-dialylcarbamoylmethylphosphine oxide dissolved in tri-n-butyl phosphate on an inert substrate which selectively extracts the actinide values. The actinide values can be eluted either as a group or individually and their presence quantitatively detected by alpha counting. 3 figs.

Horwitz, E.P.; Dietz, M.L.

1989-05-30T23:59:59.000Z

19

Method for the concentration and separation of actinides from biological and environmental samples  

DOE Patents (OSTI)

A method and apparatus for the quantitative recover of actinide values from biological and environmental sample by passing appropriately prepared samples in a mineral acid solution through a separation column of a dialkyl(phenyl)-N,N-dialylcarbamoylmethylphosphine oxide dissolved in tri-n-butyl phosphate on an inert substrate which selectively extracts the actinide values. The actinide values can be eluted either as a group or individually and their presence quantitatively detected by alpha counting.

Horwitz, E. Philip (Naperville, IL); Dietz, Mark L. (Tucson, AZ)

1989-01-01T23:59:59.000Z

20

Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation  

E-Print Network (OSTI)

Albright, D. , Plutonium and highly enriched uranium, 1996 :and swelling in uranium-plutonium mixed nitride fuels.products and to extract plutonium or any other actinide from

Heidet, Florent

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Organophosphorus reagents in actinide separations: Unique tools for production, cleanup and disposal  

Science Conference Proceedings (OSTI)

Interactions of actinide ions with phosphate and organophosphorus reagents have figured prominently in nuclear science and technology, particularly in the hydrometallurgical processing of irradiated nuclear fuel. Actinide interactions with phosphorus-containing species impact all aspects from the stability of naturally occurring actinides in phosphate mineral phases through the application of the bismuth phosphate and PUREX processes for large-scale production of transuranic elements to the development of analytical separation and environment restoration processes based on new organophosphorus reagents. In this report, an overview of the unique role of organophosphorus compounds in actinide production, disposal, and environment restoration is presented. The broad utility of these reagents and their unique chemical properties is emphasized.

Nash, K. L.

2000-01-12T23:59:59.000Z

22

Development and validation of process models for minor actinide separations processes using centrifugal contactors  

Science Conference Proceedings (OSTI)

As any future spent fuel treatment facility is likely to be based on intensified solvent extraction equipment it is important to understand the chemical and mass transfer kinetics of the processes involved. Two candidate minor actinide separations processes have been examined through a programme of modeling and experimental work to illustrate some of the issues to address in turning these technologies in to fully optimized processes suitable for industrialization. (authors)

Fox, O.D.; Carrott, M.J.; Gaubert, E.; Maher, C.J.; Mason, C.; Taylor, R.J.; Woodhead, D.A. [British Technology Centre, Nexia Solutions, Sellafield, Seascale, CA20 1PG (United Kingdom)

2007-07-01T23:59:59.000Z

23

Actinide Chemistry  

NLE Websites -- All DOE Office Websites (Extended Search)

sites. * Modeling actinide transport in subsurface environments. Enhancing the nuclear fuel cycle. Developing new separation processes to recycle waste. Better understanding...

24

Actinides-1981  

Science Conference Proceedings (OSTI)

Abstracts of 134 papers which were presented at the Actinides-1981 conference are presented. Approximately half of these papers deal with electronic structure of the actinides. Others deal with solid state chemistry, nuclear physic, thermodynamic properties, solution chemistry, and applied chemistry.

Not Available

1981-09-01T23:59:59.000Z

25

Sigma Team for Minor Actinide Separation: PNNL FY 2011 Status Report  

SciTech Connect

This report summarizes work conducted in FY 2011 at PNNL to investigate new methods of separating the minor actinide elements (Am and Cm) from the trivalent lanthanide elements, and separation of Am from Cm. For the former, work focused on a solvent extraction system combining an acidic extractant (HDEHP) with a neutral extractant (CMPO) to form a hybrid solvent extraction system referred to as TRUSPEAK (combining the TRUEX and TALSPEAK processes). For the latter, ligands that strongly bing uranyl ion were investigated for stabilizing corresponding americyl ion.

Lumetta, Gregg J.; Braley, Jenifer C.; Sinkov, Sergey I.; Levitskaia, Tatiana G.; Carter, Jennifer C.; Warner, Marvin G.; Pittman, Jonathan W.

2011-08-13T23:59:59.000Z

26

Sigma Team for Minor Actinide Separation: PNNL FY 2010 Status Report  

SciTech Connect

Work conducted at Pacific Northwest National Laboratory (PNNL) in FY 2010 addressed two lines of inquiry. The two hypotheses put forth were: 1. The extractants from the TRUEX( ) process (CMPO)( ) and from the TALSPEAK( ) process (HDEHP)( ) can be combined into a single process solvent to separate 1) the lanthanides and actinides from acidic high-level waste and 2) the actinides from the lanthanides in a single solvent extraction process. (Note: This combined process will hereafter be referred to as the TRUSPEAK process.) A series of empirical measurements performed (both at PNNL and Argonne National Laboratory) in FY 2009 supported this hypothesis, but also indicated some nuances to the chemistry. Lanthanide/americium separation factors of 12 and higher were obtained with a prototypic TRUSPEAK solvent when extracting the lanthanides from a citrate-buffered DTPA( ) solution. Although the observed separation factors are sufficiently high to design an actinide/lanthanide separation process, a better understanding of the chemistry is expected to lead to improved solvent formulations and improved process performance. Work in FY 2010 focused on understanding the synergistic extraction behavior observed for Nd(III) and Am(III) when extracted into mixtures of CMPO and HDEHP. The interaction between CMPO and HDEHP in dodecane was investigated by 31P NMR spectroscopy, and an adduct of the type CMPO•HDEHP was found to form. The formation of this adduct will reduce the effective extractant concentrations and must be taken into account when modeling metal ion extraction data in this system. Studies were also initiated to determine the Pitzer parameters for Nd(III) in lactate media. 2. Higher oxidation states (e.g., +5 and +6) of Am can be stabilized in solution by complexation with uranophilic ligands, and this chemistry can be exploited to separate Am from Cm. To test this hypothesis, the previously reported stereognostic uranophilic ligands NPB( ) and ETAC(e) were investigated. To assess the potential of these ligands to stabilize pentavalent and hexavalent actinides, stability constants were measured for complexation of these ligands to Nd(III), Np(V), and Pu(VI) in a solvent mixture consisting of 80% methanol/20% water. For comparison, an analogous non-stereognostic ligand, NTA,(f) was also examined. The ligand ETAC showed greater binding affinity for hexavalent Pu versus trivalent Nd by two orders-of-magnitude. Such selectivity was not observed for either NTA or NPB.

Lumetta, Gregg J.; Sinkov, Sergey I.; Neiner, Doinita; Levitskaia, Tatiana G.; Braley, Jenifer C.; Carter, Jennifer C.; Warner, Marvin G.; Pittman, Jonathan W.; Rapko, Brian M.

2010-08-24T23:59:59.000Z

27

Quest for Environmentally-Benign Ligands for Actinide Separations: Thermodynamic, Spectroscopic, and Structural Characterization of U(VI) Complexes with Oxa-Diamide and Related Ligands  

E-Print Network (OSTI)

for Actinide Separations: Thermodynamic, Spectroscopic, andoxydiacetic acid (ODA). Thermodynamic parameters, includingThe trend in the thermodynamic stability of the complexes

Tian, Guoxin; Advanced Light Source

2009-01-01T23:59:59.000Z

28

Rapid Separation Methods to Characterize Actinides and Metallic Impurities in Plutonium Scrap Materials at SRS  

SciTech Connect

The Nuclear Materials Stabilization and Storage Division at SRS plans to stabilize selected plutonium scrap residue materials for long term storage by dissolution processing and plans to stabilize other plutonium vault materials via high-temperature furnace processing. To support these nuclear material stabilization activities, the SRS Analytical Laboratories Department (ALD) will provide characterization of materials required prior to the dissolution or the high-firing of these materials. Lab renovations to install new analytical instrumentation are underway to support these activities that include glove boxes with simulated-process dissolution and high- pressure microwave dissolution capability. Inductively-coupled plasma atomic emission spectrometry (ICP-AES), inductively- coupled mass spectrometry (ICP-MS) and thermal-ionization mass spectrometry (TIMS) will be used to measure actinide isotopics and metallic impurities. New high-speed actinide separation methods have been developed that will be applied to isotopic characterization of nuclear materials by TIMS and ICP-MS to eliminate isobaric interferences between Pu-238 /U- 238 and Pu-241/Am-241. TEVA Resin, UTEVA Resin, and TRU Resin columns will be used with vacuum-assisted flow rates to minimize TIMS and ICP-MS sample turnaround times. For metallic impurity analysis, rapid column removal methods using UTEVA Resin, AGMP-1 anion resin and AG MP-50 cation resin have also been developed to remove plutonium and uranium matrix interferences prior to ICP-AES and ICP- MS measurements.

Maxwell, S.L. III [Westinghouse Savannah River Company, AIKEN, SC (United States); Jones, V.D.

1998-07-01T23:59:59.000Z

29

Demonstration of the UNEX Process for the Simultaneous Separation of Cesium, Strontium, and the Actinides from Actual INEEL Tank Waste  

Science Conference Proceedings (OSTI)

A universal solvent extraction (UNEX) process for the simultaneous separation of cesium, strontium, and the actinides from actual radioactive acidic tank waste was demonstrated at the Idaho National Engineering and Environmental Laboratory. The waste solution used in the countercurrent flowsheet demonstration was obtained from tank WM-185. The UNEX process uses a tertiary solvent containing 0.08 M chlorinated cobalt dicarbollide, 0.5% polyethylene glycol-400 (PEG-400), and 0.02 M diphenyl-N,N-dibutylcarbamoyl phosphine oxide (Ph2Bu2CMPO) in a diluent consisting of phenyltrifluoromethyl sulfone (FS-13). The countercurrent flowsheet demonstration was performed in a shielded cell facility using 24 stages of 2-cm diameter centrifugal contactors. Removal efficiencies of 99.4%, 99.995%, and 99.96% were obtained for 137Cs, 90Sr, and total alpha, respectively. This is sufficient to reduce the activities of 137Cs, 90Sr, and actinides in the WM-185 waste to below NRC Class A LLW requirement s. Flooding and/or precipitate formation were not observed during testing. Significant amounts of the Zr (87%), Ba (>99%), Pb (98.8%), Fe (8%), Ca (10%), Mo (32%), and K (28%) were also removed from the feed with the universal solvent extraction flowsheet. 99Tc, Al, Hg, and Na were essentially inextractable (<1% extracted).

Law, J.D.; Herbst, R.S.; Todd, T.A. (INEEL); Romanovskiy, V.N.; Esimantovskiy, V.M.; Smirnov, I.V.; Babain, V.A.; Zaitsev, B.N. (V. G. Khlopin Radium Institute); Logunov, M.V. (MAYAK Production Association)

1999-10-01T23:59:59.000Z

30

Selective Separation of Trivalent Actinides from Lanthanides by Aqueous Processing with Introduction of Soft Donor Atoms  

SciTech Connect

With increased application of MOX fuels and longer burnup times for conventional fuels, higher concentrations of the transplutonium actinides Am and Cm (and even heavier species like Bk and Cf) will be produced. The half-lives of the Am isotopes are significantly longer than those of the most important long-lived, high specific activity lanthanides or the most common Cm, Bk and Cf isotopes, thus the greatest concern as regards long-term radiotoxicity. With the removal and transmutation of Am isotopes, radiation levels of high level wastes are reduced to near uranium mineral levels within less than 1000 years as opposed to the time-fram if they remain in the wastes.

Kenneth L. Nash; Sue B. Clark; Gregg Lumetta

2009-09-23T23:59:59.000Z

31

TAILORING INORGANIC SORBENTS FOR SRS STRONTIUM AND ACTINIDE SEPARATIONS: MODIFIED MONOSODIUM TITANATE PHASE III FINAL REPORT  

DOE Green Energy (OSTI)

This document provides a final report of Phase III testing activities for the development of modified monosodium titanate (mMST), which exhibits improved strontium and actinide removal characteristics compared to the baseline MST material. The activities included characterization of the crystalline phases present at varying temperatures, solids settling characteristics, quantification of the peroxide content; evaluation of the post-synthesis gas release under different conditions; the extent of desorption of {sup 85}Sr, Np, and Pu under washing conditions; and the effects of age and radiation on the performance of the mMST. Key findings and conclusions include the following. The peroxide content of several mMST samples was determined using iodometric titration. The peroxide content was found to decrease with age or upon extended exposure to elevated temperature. A loss of peroxide was also measured after exposure of the material to an alkaline salt solution similar in composition to the simulated waste solution. To determine if the loss of peroxide with age affects the performance of the material, Sr and actinide removal tests were conducted with samples of varying age. The oldest sample (4 years and 8 months) did show lower Sr and Pu removal performance. When compared to the youngest sample tested (1 month), the oldest sample retained only 15% of the DF for Pu. Previous testing with this sample indicated no decrease in Pu removal performance up to an age of 30 months. No loss in Np removal performance was observed for any of the aged samples, and no uptake of uranium occurred at the typical sorbent loading of 0.2 g/L. Additional testing with a uranium only simulant and higher mMST loading (3.0 g/L) indicated a 10% increase of uranium uptake for a sample aged 3 years and 8 months when compared to the results of the same sample measured at an age of 1 year and 5 months. Performance testing with both baseline-MST and mMST that had been irradiated in a gamma source to a total dose of 3.95 x 10{sup 6} R, indicated little to no affect on the performance of the material to remove Sr and actinides. Previous testing established that mMST releases oxygen gas during the synthesis, and continues to off-gas during storage post synthesis. The post-synthesis gas release rate was measured under several conditions, including varying the pH of the wash water and at elevated temperature (49 C, typical of bounding summertime storage without air conditioning). Results indicated that a high pH (basic) wash reduced the initial gas release rate, but after 2 days the release rates from all different pH washed samples were not statistically different. The gas release rate at 49 C, a temperature at which the material may be exposed to during shipping and storage, was consistently about 2.5 times higher than the rate at room temperature. All gas release results indicated that vented containers would be necessary for shipping and storage of large quantities of material. Suspension of sorbate-loaded solids into diluted solutions representing intermediate and final stages of washing for 24-hours revealed no evidence of desorption of Sr, Pu or Np from the mMST solids. Based on the results of the Phase III testing as well as that from earlier studies (Phases I and II), SRNL researchers recommend adopting the use of the mMST material for the removal of strontium and actinides from the SRS HLW supernatant liquids in the Actinide Removal Process and Salt Waste Processing Facility. Given the decrease in Sr and Pu removal performance for the mMST having an age of 4 years and 8 months, we recommend that mMST be used within 30 months of production. Furthermore we recommend that DOE provide funding to conduct pilot-scale testing of the mixing and settling characteristics of the mMST and impact, if any, on the generation of hydrogen during processing in the Defense Waste Processing Facility (DWPF).

Taylor-Pashow, K.; Hobbs, D.

2010-09-01T23:59:59.000Z

32

Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products  

SciTech Connect

This project is investigating techniques involving ionic liquids (IL) and supercritical (SC) fluids for dissolution and separation of lanthanides, actinides, and fission products. The research project consists of the following tasks: Study direct dissolution of lanthanide oxides, uranium dioxide and other actinide oxides in [bmin][Tf{sub 2}N] with TBP(HNO{sub 3}){sub 1.8}(H{sub 2}O){sub 0.6} and similar types of Lewis acid-Lewis base complexing agents; Measure distributions of dissolved metal species between the IL and the sc-CO{sub 2} phases under various temperature and pressure conditions; Investigate the chemistry of the dissolved metal species in both IL and sc-CO{sub 2} phases using spectroscopic and chemical methods; Evaluate potential applications of the new extraction techniques for nuclear waste management and for other projects. Supercritical carbon dioxide (sc-CO{sub 2}) and ionic liquids are considered green solvents for chemical reactions and separations. Above the critical point, CO{sub 2} has both gas- and liquid-like properties, making it capable of penetrating small pores of solids and dissolving organic compounds in the solid matrix. One application of sc-CO{sub 2} extraction technology is nuclear waste management. Ionic liquids are low-melting salts composed of an organic cation and an anion of various forms, with unique properties making them attractive replacements for the volatile organic solvents traditionally used in liquid-liquid extraction processes. One type of room temperature ionic liquid (RTIL) based on the 1-alkyl-3-methylimidazolium cation [bmin] with bis(trifluoromethylsulfonyl)imide anion [Tf{sub 2}N] is of particular interest for extraction of metal ions due to its water stability, relative low viscosity, high conductivity, and good electrochemical and thermal stability. Recent studies indicate that a coupled IL sc-CO{sub 2} extraction system can effectively transfer trivalent lanthanide and uranyl ions from nitric acid solutions. Advantages of this technique include operation at ambient temperature and pressure, selective extraction due to tunable sc-CO{sub 2} solvation strength, no IL loss during back-extraction, and no organic solvent introduced into the IL phase.

Wai, Chien M. [Univ. of Idaho, Moscow, ID (United States); Bruce Mincher

2012-12-01T23:59:59.000Z

33

Development of immobilized ligands for actinide separations. Final report, June 1991--May 1994  

SciTech Connect

Primary goals during this grant period were to (1) synthesize new bifunctional chelating ligands, (2) characterize the structural features of the Ln and An coordination complexes formed by these ligands, (3) use structural data to iteratively design new classes of multifunctional ligands, and (4) explore additional routes for attachment of key ligands to solid supports that could be useful for chromatographic separations. Some highlights of recently published work as well as a summary of submitted, unpublished and/or still in progress research are outlined.

Paine, R.T.

1994-06-01T23:59:59.000Z

34

Actinide Chemistry  

NLE Websites -- All DOE Office Websites (Extended Search)

Actinide Chemistry Actinide Chemistry Actinide Chemistry Research into alternative forms of energy, especially energy security, is one of the major national security imperatives of this century. Get Expertise David Gallimore Actinide Analytical Chemistry Email Rebecca Chamberlin Actinide Analytical Chemistry Email Josh Smith Chemistry Communications Email Along with the lanthanides, they are often called "the f-elements" because they have valence electrons in the f shell. Actinide chemistry serves a critical role in addressing global threats Project Description At Los Alamos, scientists are using actinide analytical chemistry to identify and quantify the chemical and isotopic composition of materials. Since the Manhattan Project, such work has supported the Laboratory's

35

Proceedings of the 17th Biennial Waste Processing Conference WASTE SEPARATION-  

E-Print Network (OSTI)

Proceedings of the 17th Biennial Waste Processing Conference ASME 1996 WASTE SEPARATION- DOES IT INFLUENCE MUNICIPAL WASTE COMBUSTOR EMISSIONS? A. John Chandler A.J. Chandler & Associates Ltd. Willowdale that MSW incinerator emissions show significant variations because of the heterogeneous nature of the waste

Columbia University

36

The Universal Solvent Exchange (UNEX) Process II: Flowsheet Development & Demonstration of the UNEX Process for the Separation of Cesium, Strontium, and Actinides from Actual Acidic Radioactive Waste  

Science Conference Proceedings (OSTI)

A novel solvent extraction process, the Universal Extraction (UNEX) process, has been developed for the simultaneous separation of cesium, strontium, and the actinides from acidic waste solutions. The UNEX process solvent consists of chlorinated cobalt dicarbollide for the extraction of 137Cs, polyethylene glycol for the extraction of 90Sr, and diphenyl-N,N-dibutylcarbamoyl phosphine oxide for the extraction of the actinides and lanthanides. A nonnitroaromatic polar diluent consisting of phenyltrifluoromethyl sulfone has been developed for this process. A UNEX flowsheet consisting of a single solvent extraction cycle has been developed as a part of a collaborative effort between the Khlopin Radium Institute (KRI) and the Idaho National Engineering and Environmental Laboratory (INEEL). This flowsheet has been demonstrated with actual acidic radioactive tank waste at the INEEL using 24 stages of 2-cm diameter centrifugal contactors installed in a shielded cell facility. The activities of 137Cs, 90Sr, and the actinides were reduced to levels at which a grout waste form would meet NRC Class A LLW requirements. The extraction of 99Tc and several nonradioactive metals by the UNEX solvent has also been evaluated.

Law, Jack Douglas; Herbst, Ronald Scott; Todd, Terry Allen; Romanovskiy, V. N.; Smirnov, I. V.; Esimantovskiy, V. M.; Zaitsev. B. N.; Babain, V. A.

2001-01-01T23:59:59.000Z

37

PRODUCTION OF ACTINIDE METAL  

DOE Patents (OSTI)

A process of reducing actinide oxide to the metal with magnesium-zinc alloy in a flux of 5 mole% of magnesium fluoride and 95 mole% of magnesium chloride plus lithium, sodium, potassium, calcium, strontium, or barium chloride is presented. The flux contains at least 14 mole% of magnesium cation at 600-- 900 deg C in air. The formed magnesium-zinc-actinide alloy is separated from the magnesium-oxide-containing flux. (AEC)

Knighton, J.B.

1963-11-01T23:59:59.000Z

38

CMP flowsheet development for the separation of actinides from ICPP sodium-bearing waste using centrifugal contactors  

Science Conference Proceedings (OSTI)

Previous results of lab-scale batch contacts with sodium-bearing waste (SBW) simulant suggested a potential flowsheet for partitioning actinides using solvent extraction with dihexyl-N,N-diethylcarbamoylmethyl phosphonate (DHDECMP or simply CMP) as the extractant. The suggested baseline flowsheet includes: an extraction section to remove actinides from liquid SBW into the CMP solvent (0.75 M CMP, 1.0 M TBP in Isopar-L{reg_sign}); a thermally unstable complexant (TUCS) strip section to back-extract actinides; a sodium carbonate wash section for solvent cleanup; and a dilute HNO{sub 3} rinse section to re-acidify the solvent. The purpose of these studies was to test and develop a baseline CMP flowsheet for Idaho Chemical Processing Plant (ICPP) SBW under continuous, countercurrent conditions using centrifugal contactors. This flowsheet was tested in two experiments using the Centrifugal Contactor Mockup which consists of sixteen stages of 5.5 cm diameter centrifugal contactors (procured from Oak Ridge National Laboratory). All testing was performed using non-radioactive SBW simulant. Potential flowsheets were evaluated with regard to the behavior of the non-radioactive components potentially extracted by the CMP solvent. Specifically, the behavior of the matrix components, including Fe, Hg, and Zr, was studied. In addition, Nd was added to the SBW simulant as a surrogate for {sup 241}Am. In general, the behavior of the individual components closely paralleled that anticipated from batch testing. Based on the assumption that the behavior of Am will be very similar to the behavior of the Nd surrogate, eight extraction stages are more than sufficient to reduce the actinide content in the SBW to levels well below the NRC Class A LLW criteria of 10 nCi/g. Very little Fe or Zr were extracted from the SBW simulant, resulting in only 1% of the Fe and 4% of the Zr exiting in the high-activity waste (HAW) fraction.

Law, J.D.; Herbst, R.S.; Rodriguez, A.M.

1995-08-01T23:59:59.000Z

39

Demonstration of the UNEX Process for the Simultaneous Separation of Cesium, Strontium, and the Actinides from Actual INEEL Sodium-Bearing Waste  

SciTech Connect

A universal solvent extraction (UNEX) process for the simultaneous separation of cesium, strontium, and the actinides from actual radioactive acidic tank waste was demonstrated at the Idaho National Engineering and Environmental Laboratory. The waste solution used in the countercurrent flowsheet demonstration was obtained from tank WM-185. The UNEX process uses a tertiary solvent containing 0.08 M chlorinated cobalt dicarbollide, 0.5% polyethylene glycol-400 (PEG-400), and 0.02 M diphenyl-N,N-dibutylcarbamoyl phosphine oxide (Ph2Bu2CMPO) in a diluent consisting of phenyltrifluoromethyl sulfone (FS-13). The countercurrent flowsheet demonstration was performed in a shielded cell facility using 24 stages of 2-cm diameter centrifugal contactors. Removal efficiencies of 99.4%, 99.995%, and 99.96% were obtained for 137Cs, 90Sr, and total alpha, respectively. This is sufficient to reduce the activities of 137Cs, 90Sr, and actinides in the WM-185 waste to below NRC Class A LLW requirements. Flooding and/or precipitate formation were not observed during testing. Significant amounts of the Zr (87%), Ba (>99%), Pb (98.8%), Fe (8%), Ca (10%), Mo (32%), and K (28%) were also removed from the feed with the universal solvent extraction flowsheet. 99Tc, Al, Hg, and Na were essentially inextractable (<1% extracted).

Law, Jack Douglas; Herbst, Ronald Scott; Todd, Terry Allen; Romanovskiy, V.; Smirnov, I.; Babain, V.; Zaitsev, B.; Esimantovskiy, V.

1999-11-01T23:59:59.000Z

40

Electronic structure and correlation effects in actinides  

Science Conference Proceedings (OSTI)

This report consists of the vugraphs given at a conference on electronic structure. Topics discussed are electronic structure, f-bonding, crystal structure, and crystal structure stability of the actinides and how they are inter-related.

Albers, R.C.

1998-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Separation of actinide(III) from lanthanide(III) by thermo-sensitive gel co-polymerized with TPPEN derivatives  

Science Conference Proceedings (OSTI)

Extraction separation of Am(III) and Eu(III) was examined by the thermal-swing extraction technique using a thermo-sensitive gel, poly-N-isopropyl-acrylamide (NIPA) co-polymerized with a TPEN derivative, N,N,N',N'- tetrakis(4-propenyl-oxy-2-pyridyl-methyl)ethylenediamine (TPPEN). The separation of Am(III) from Eu(III) was observed in the swollen state of gel (5 deg. C) and the separation factor of Am(III) was evaluated as about 18 at pH 5.2. More than 90% of Am(III) extracted into the gel was released by the volume phase transition of gel from the swollen state (5 deg. C) to the shrunken one (40 deg. C). The repetition test for the thermal swing extraction of a soft metal ion, Cd(II), which was used as a substitute of Am(III), was carried out and the extraction and release of Cd(II) were repeated three times stably under the thermal-swing operation between 5 deg. C and 40 deg. C. The radiation effect of gel on the extraction of Am and Eu was tested by the irradiation of {gamma}-ray (10 kGy) and the long-term adsorption of {alpha}-emitter ({sup 244}Cm). The TPPEN-NIPA gel sustained no damage by these radiation tests. These results suggest that the thermal-swing extraction technique is applicable to the MA partitioning process indispensable for the establishment of P and T technology. (authors)

Takeshita, Kenji; Fugate, Glenn [Chemical Resources Laboratory, Tokyo Institute of Technology 4259 Nagatsuta, Midori-ku, Yokohama 226-8503 (Japan); Matsumura, Tatsuro [Nuclear Science and Engineering Directorate, Japan Atomic Energy Agency Tokai-mura, Naka-gun, Ibaragi, 319-1195 (Japan); Nakano, Yoshio [Interdisciplinary Graduate School of Science and Engineering, Tokyo Institute of Technology 4259 Nagatsuta, Midori-ku, Yokohama, 226-8502 (Japan); Mori, Atsunori; Fukuoka, Sachio [Department of Chemical Science and Engineering, Graduate School of Engineering, Kobe University 1-1 Rokkodai-cho, Nada-ku, Kobe, 657-8501 (Japan)

2007-07-01T23:59:59.000Z

42

Improved Strontium and Actinide Separations  

Effect of aging on mMST performance 15 wt% mMST suspension in water Dried mMST powder mMST dissolved Scanning electron micrograph of mMST in sulfuric ...

43

Actinide metal processing  

DOE Patents (OSTI)

A process for converting an actinide metal such as thorium, uranium, or plutonium to an actinide oxide material by admixing the actinide metal in an aqueous medium with a hypochlorite as an oxidizing agent for sufficient time to form the actinide oxide material and recovering the actinide oxide material is described together with a low temperature process for preparing an actinide oxide nitrate such as uranyl nitrate. Additionally, a composition of matter comprising the reaction product of uranium metal and sodium hypochlorite is provided, the reaction product being an essentially insoluble uranium oxide material suitable for disposal or long term storage.

Sauer, N.N.; Watkin, J.G.

1992-03-24T23:59:59.000Z

44

Actinide metal processing  

DOE Patents (OSTI)

This invention is comprised of a process of converting an actinide metal such as thorium, uranium, or plutonium to an actinide oxide material by admixing the actinide metal in an aqueous medium with a hypochlorite as an oxidizing agent for sufficient time to form the actinide oxide material and recovering the actinide oxide material is provided together with a low temperature process of preparing an actinide oxide nitrate such as uranyl nitrate. Additionally, a composition of matter comprising the reaction product of uranium metal and sodium hypochlorite is provided, the reaction product being an essentially insoluble uranium oxide material suitable for disposal or long term storage.

Sauer, N.N.; Watkin, J.G.

1991-04-05T23:59:59.000Z

45

Decontamination of matrices containing actinide oxides  

DOE Patents (OSTI)

There is provided a method for removing actinides and actinide oxides, particularly fired actinides, from soil and other contaminated matrices, comprising: (a) contacting a contaminated material with a solution of at least one inhibited fluoride and an acid to form a mixture; (b) heating the mixture of contaminated material and solution to a temperature in the range from about 30 C to about 90 C while stirring; (c) separating the solution from any undissolved matrix material in the mixture; (d) washing the undissolved matrix material to remove any residual materials; and (e) drying and returning the treated matrix material to the environment.

Villarreal, Robert

1997-12-01T23:59:59.000Z

46

PREPARATION OF ACTINIDE-ALUMINUM ALLOYS  

DOE Patents (OSTI)

BS>A process is given for preparing alloys of aluminum with plutonium, uranium, and/or thorium by chlorinating actinide oxide dissolved in molten alkali metal chloride with hydrochloric acid, chlorine, and/or phosgene, adding aluminum metal, and passing air and/or water vapor through the mass. Actinide metal is formed and alloyed with the aluminum. After cooling to solidification, the alloy is separated from the salt. (AEC)

Moore, R.H.

1962-09-01T23:59:59.000Z

47

Bidentate organophosphorus solvent extraction process for actinide recovery and partition  

DOE Patents (OSTI)

A liquid-liquid extraction process for the recovery and partitioning of actinide values from acidic nuclear waste aqueous solutions, the actinide values including trivalent, tetravalent and hexavalent oxidation states is provided and includes the steps of contacting the aqueous solution with a bidentate organophosphorous extractant to extract essentially all of the actinide values into the organic phase. Thereafter the respective actinide fractions are selectively partitioned into separate aqueous solutions by contact with dilute nitric or nitric-hydrofluoric acid solutions. The hexavalent uranium is finally removed from the organic phase by contact with a dilute sodium carbonate solution.

Schulz, Wallace W. (Richland, WA)

1976-01-01T23:59:59.000Z

48

Improved method for extracting lanthanides and actinides from acid solutions  

DOE Patents (OSTI)

A process for the recovery of actinide and lanthanide values from aqueous acidic solutions uses a new series of neutral bi-functional extractants, the alkyl(phenyl)-N,N-dialkylcarbamoylmethylphosphine oxides. The process is suitable for the separation of actinide and lanthanide values from fission product values found together in high-level nuclear reprocessing waste solutions.

Horwitz, E.P.; Kalina, D.G.; Kaplan, L.; Mason, G.W.

1983-07-26T23:59:59.000Z

49

Method for extracting lanthanides and actinides from acid solutions  

SciTech Connect

A process for the recovery of actinide and lanthanide values from aqueous acidic solutions with an organic extractant is patented. The process is suitable for the separation of actinide and lanthanide values from fission product values found together in high-level nuclear reprocessing waste solutions.

Horwitz, E.P.; Kalina, D.G.; Kaplan, L.; Mason, G.W.

1985-10-22T23:59:59.000Z

50

Actinide Spectroscopy Workshop  

E-Print Network (OSTI)

the actinide series: Plutonium and Americium." The programin the 5f States of Plutonium. ” Gerrit van der Laan ofStructure of Uranium and Plutonium Compounds. ” Changing

Tobin, J.G.; Shuh, D.K.

2004-01-01T23:59:59.000Z

51

NWChem and Actinide Chemistry  

NLE Websites -- All DOE Office Websites (Extended Search)

ACTINIDE CHEMISTRY MEETS COMPUTATION ACTINIDE CHEMISTRY MEETS COMPUTATION Capturing how contaminants migrate across groundwater-surface water inter- faces is a challenge that researchers at the Department of Energy's EMSL-the Environmental Molecular Sciences Laboratory-are rising to. This challenge, a top priority for waste cleanup efforts at the Hanford Site in Richland, Washington, and other parts of the DOE weapons complex, is being addressed using NWChem, a computational chemistry package developed at EMSL that is designed to run on high-performance parallel supercomputers, such as EMSL's Chinook. NWChem is enabling breakthrough discoveries in actinide behavior and chemistry, in part because it allows researchers to accurately model the dynamical formation, speciation, and redox chemistry of actinide complexes in realistic complex mo-

52

ACTINIDES-1981. ABSTRACTS  

E-Print Network (OSTI)

ACIDIC BOON TEMPERATURE MOLTEN SALT* R. De Waele, L. Heermanthe other actinides in molten salts » . This work describesAcinic Room Temperature Molten Salt R. De Waele, L. Heerman

Authors, Various

2010-01-01T23:59:59.000Z

53

Actinide recovery process  

DOE Patents (OSTI)

Process for the removal of plutonium polymer and ionic actinides from aqueous solutions by absorption onto a solid extractant loaded on a solid inert support such as polystyrene-divinylbenzene. The absorbed actinides can then be recovered by incineration, by stripping with organic solvents, or by acid digestion. Preferred solid extractants are trioctylphosphine oxide and octylphenyl-N,N-diisobutylcarbamoylmethylphosphine oxide and the like. 2 tabs.

Muscatello, A.C.; Navratil, J.D.; Saba, M.T.

1985-06-13T23:59:59.000Z

54

HHIM Conference  

NLE Websites -- All DOE Office Websites (Extended Search)

Small angle neutron scattering pattern from thin films of ErT1-x3Hex Small angle neutron scattering pattern from thin films of ErT1-x3Hex Hydrogen and Helium Isotopes in Materials Conference TEM image of 3He platelet formation along crystallographic planes in ErT1-x3Hex thin film April 20-21, 2010 * Oak Ridge National Laboratory * Oak Ridge, TN, USA Workshop Home Agenda and Important Deadlines Call for Abstracts Registration and Payment Logistics, Hotel, Transportation Presentations Committee/Contacts HHIM 2008 filler Hydrogen and Helium Isotopes in Materials Conference The purpose of this conference is to promote interaction among researchers interested in the behavior of hydrogen and helium isotopes in materials of interest to the tritide, fusion, and actinide science communities as well as those researchers engaged in the development of new reactor materials. The emphasis of the contributed discussion will be the correlation of hydrogen and helium behavior and materials structure-property relationships.

55

Nonaqueous actinide hydride dissolution and production of actinide $beta$- diketonates  

DOE Patents (OSTI)

Actinide beta-diketonate complex molecular compounds are produced by reacting a beta-diketone compound with a hydride of the actinide material in a mixture of carbon tetrachloride and methanol. (auth)

Crisler, L.R.

1975-11-11T23:59:59.000Z

56

Actinide and xenon reactivity effects in ATW high flux systems  

SciTech Connect

In this paper, initial system reactivity response to flux changes caused by the actinides and xenon are investigated separately for a high flux ATW system. The maximum change in reactivity after a flux change due to the effect of the changing quantities of actinides is generally at least two orders of magnitude smaller than either the positive or negative reactivity effect associated with xenon after a shutdown or start-up. In any transient flux event, the reactivity response of the system to xenon will generally occlude the response due to the actinides.

Woosley, M.; Olson, K.; Henderson, D. L.; Sailor, W. C. [Department of Mechanical, Aerospace, and Nuclear Engineering University of Virginia, Charlottesville, Virginia 22903 (United States); Department of Nuclear Engineering and Engineering Physics University of Wisconsin, Madison, Wisconsin 53706-1687 (United States); Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States)

1995-09-15T23:59:59.000Z

57

Engineering-Scale Distillation of Cadmium for Actinide Recovery  

Science Conference Proceedings (OSTI)

During the recovery of actinide products from spent nuclear fuel, cadmium is separated from the actinide products by a distillation process. Distillation occurs in an induction-heated furnace called a cathode processor capable of processing kilogram quantities of cadmium. Operating parameters have been established for sufficient recovery of the cadmium based on mass balance and product purity. A cadmium distillation rate similar to previous investigators has also been determined. The development of cadmium distillation for spent fuel treatment enhances the capabilities for actinide recovery processes.

J.C. Price; D. Vaden; R.W. Benedict

2007-10-01T23:59:59.000Z

58

URANIUM SEPARATION PROCESS  

DOE Patents (OSTI)

A method of separating uranium oxides from PuO/sub 2/, ThO/sub 2/, and other actinide oxides is described. The oxide mixture is suspended in a fused salt melt and a chlorinating agent such as chlorine gas or phosgene is sparged through the suspension. Uranium oxides are selectively chlorinated and dissolve in the melt, which may then be filtered to remove the unchlorinated oxides of the other actinides. (AEC)

Lyon, W.L.

1962-04-17T23:59:59.000Z

59

Device for Detecting Actinides, Method for Detecting Actinides  

DOE Patents (OSTI)

A heavy metal detector is provided comprising a first molecule and a second molecule, whereby the first and second molecules interact in a predetermined manner; a first region on the first molecule adapted to interact with an actinide; and a second region on the second molecule adapted to interact with the actinide, whereby the interactions of the actinide with the regions effect the predetermined manner of interaction between the molecules.

Stevens, Fred J.; Wilkins-Stevens, Priscilla

1998-10-29T23:59:59.000Z

60

Flowsheet report for baseline actinide blanket processing for accelerator transmutation of waste  

Science Conference Proceedings (OSTI)

We provide a flowsheet analysis of the chemical processing of actinide and fission product materials form the actinide blanket of an accelerator-based transmutation concept. An initial liquid ion exchange step is employed to recover unburned plutonium and neptunium, so that it can be returned quickly to the transmitter. The remaining materials, consisting of fission products and trivalent actinides (americium, curium), is processed after a cooling period. A reverse Talspeak process is employed to separate these trivalent actinides from lanthanides and other fission products.

Walker, R.B.

1992-04-08T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Actinide halide complexes  

DOE Patents (OSTI)

A compound of the formula MX{sub n}L{sub m} wherein M = Th, Pu, Np,or Am thorium, X = a halide atom, n = 3 or 4, L is a coordinating ligand selected from the group consisting of aprotic Lewis bases having an oxygen-, nitrogen-, sulfur-, or phosphorus-donor, and m is 3 or 4 for monodentate ligands or is 2 for bidentate ligands, where n + m = 7 or 8 for monodentate ligands or 5 or 6 for bidentate ligands, a compound of the formula MX{sub n} wherein M, X, and n are as previously defined, and a process of preparing such actinide metal compounds including admixing the actinide metal in an aprotic Lewis base as a coordinating solvent in the presence of a halogen-containing oxidant, are provided.

Avens, L.R.; Zwick, B.D.; Sattelberger, A.P.; Clark, D.L.; Watkin, J.G.

1991-02-07T23:59:59.000Z

62

Heavy Actinides | ornl.gov  

NLE Websites -- All DOE Office Websites (Extended Search)

actinides with the construction and commissioning of the High Flux Isotope Reactor (HFIR) and Radiochemical Engineering Development Center (REDC) in 1965 and 1966,...

63

Actinide halide complexes  

DOE Patents (OSTI)

A compound is described of the formula MX[sub n]L[sub m] wherein M is a metal atom selected from the group consisting of thorium, plutonium, neptunium or americium, X is a halide atom, n is an integer selected from the group of three or four, L is a coordinating ligand selected from the group consisting of aprotic Lewis bases having an oxygen-, nitrogen-, sulfur-, or phosphorus-donor, and m is an integer selected from the group of three or four for monodentate ligands or is the integer two for bidentate ligands, where the sum of n+m equals seven or eight for monodentate ligands or five or six for bidentate ligands. A compound of the formula MX[sub n] wherein M, X, and n are as previously defined, and a process of preparing such actinide metal compounds are described including admixing the actinide metal in an aprotic Lewis base as a coordinating solvent in the presence of a halogen-containing oxidant.

Avens, L.R.; Zwick, B.D.; Sattelberger, A.P.; Clark, D.L.; Watkin, J.G.

1992-11-24T23:59:59.000Z

64

Actinide halide complexes  

DOE Patents (OSTI)

A compound of the formula MX.sub.n L.sub.m wherein M is a metal atom selected from the group consisting of thorium, plutonium, neptunium or americium, X is a halide atom, n is an integer selected from the group of three or four, L is a coordinating ligand selected from the group consisting of aprotic Lewis bases having an oxygen-, nitrogen-, sulfur-, or phosphorus-donor, and m is an integer selected from the group of three or four for monodentate ligands or is the integer two for bidentate ligands, where the sum of n+m equals seven or eight for monodentate ligands or five or six for bidentate ligands, a compound of the formula MX.sub.n wherein M, X, and n are as previously defined, and a process of preparing such actinide metal compounds including admixing the actinide metal in an aprotic Lewis base as a coordinating solvent in the presence of a halogen-containing oxidant, are provided.

Avens, Larry R. (Los Alamos, NM); Zwick, Bill D. (Santa Fe, NM); Sattelberger, Alfred P. (Los Alamos, NM); Clark, David L. (Los Alamos, NM); Watkin, John G. (Los Alamos, NM)

1992-01-01T23:59:59.000Z

65

Actinide removal from nitric acid waste streams  

SciTech Connect

Actinide separations research at the Rocky Flats Plant (RFP) has found ways to significantly improve plutonium secondary recovery and americium removal from nitric acid waste streams generated by plutonium purification operations. Capacity and breakthrough studies show anion exchange with Dowex 1x4 (50 to 100 mesh) to be superior for secondary recovery of plutonium. Extraction chromatography with TOPO(tri-n-octyl-phosphine oxide) on XAD-4 removes the final traces of plutonium, including hydrolytic polymer. Partial neutralization and solid supported liquid membrane transfer removes americium for sorption on discardable inorganic ion exchangers, potentially allowing for non-TRU waste disposal.

Muscatello, A.C.; Navratil, J.D.

1986-01-01T23:59:59.000Z

66

Method for extracting lanthanides and actinides from acid solutions  

SciTech Connect

A process for the recovery of actinide and lanthanide values from aqueous acidic solutions with an organic extractant having the formula: ##STR1## where .phi. is phenyl, R.sup.1 is a straight or branched alkyl or alkoxyalkyl containing from 6 to 12 carbon atoms and R.sup.2 is an alkyl containing from 3 to 6 carbon atoms. The process is suitable for the separation of actinide and lanthanide values from fission product values found together in high level nuclear reprocessing waste solutions.

Horwitz, E. Philip (Naperville, IL); Kalina, Dale G. (Naperville, IL); Kaplan, Louis (Lombard, IL); Mason, George W. (Clarendon Hills, IL)

1985-01-01T23:59:59.000Z

67

Actinide Burning in CANDU Reactors  

Science Conference Proceedings (OSTI)

Actinide burning in CANDU reactors has been studied as a method of reducing the actinide content of spent nuclear fuel from light water reactors, and thereby decreasing the associated long term decay heat load. In this work simulations were performed of actinides mixed with natural uranium to form a mixed oxide (MOX) fuel, and also mixed with silicon carbide to form an inert matrix (IMF) fuel. Both of these fuels were taken to a higher burnup than has previously been studied. The total transuranic element destruction calculated was 40% for the MOX fuel and 71% for the IMF. (authors)

Hyland, B.; Dyck, G.R. [Atomic Energy of Canada Limited, Chalk River, Ontario, K0J 1J0 (Canada)

2007-07-01T23:59:59.000Z

68

Miami international conference on alternative energy sources  

SciTech Connect

A separate record was prepared for each of the condensed papers presented at the conference for data base. (RCK)

Veziroglu, T.N. (ed.)

1977-01-01T23:59:59.000Z

69

Key features of the Talspeak and similar trivalent actinide-lanthanide partitioning processes  

Science Conference Proceedings (OSTI)

As closing of the nuclear-fuel cycle via the suite of UREX processes under development in the U.S. progresses, the Trivalent Actinide-Lanthanide Separation by Phosphorus Extractants and Aqueous Komplexants (TALSPEAK) process has been selected as the baseline process for partition of trivalent actinides away from fission-product lanthanides. In this report, selected features of the chemistry of the TALSPEAK process and the limited parallel information on other TALSPEAK-like processes are discussed. (author)

Nash, Kenneth L. [Washington State University, Chemistry Department, P.O. Box 644630, Pullman, WA 99164-4630 (United States)

2008-07-01T23:59:59.000Z

70

Burning actinides in very hard spectrum reactors  

SciTech Connect

The major unresolved problem in the nuclear industry is the ultimate disposition of the waste products of light water reactors. The study demonstrates the feasibility of designing a very hard spectrum actinide burner reactor (ABR). A 1100 MW/sub t/ ABR design fueled entirely with actinides reprocessed from light water reactor (LWR) wastes is proposed as both an ultimate disposal mechanism for actinides and a means of concurrently producing usable power. Actinides from discharged ABR fuel are recycled to the ABR while fission products are routed to a permanent repository. As an integral part of a large energy park, each such ABR would dispose of the waste actinides from 2 LWRs.

Robinson, A.H.; Shirley, G.W.; Prichard, A.W.; Trapp, T.J.

1978-03-20T23:59:59.000Z

71

Determination of actinides in urine and fecal samples  

DOE Patents (OSTI)

A method of determining the radioactivity of specific actinides that are carried in urine or fecal sample material is disclosed. The samples are ashed in a muffle furnace, dissolved in an acid, and then treated in a series of steps of reduction, oxidation, dissolution, and precipitation, including a unique step of passing a solution through a chloride form anion exchange resin for separation of uranium and plutonium from americium.

McKibbin, T.T.

1992-12-31T23:59:59.000Z

72

Determination of actinides in urine and fecal samples  

DOE Patents (OSTI)

A method of determining the radioactivity of specific actinides that are carried in urine or fecal sample material is disclosed. The samples are ashed in a muffle furnace, dissolved in an acid, and then treated in a series of steps of reduction, oxidation, dissolution, and precipitation, including a unique step of passing a solution through a chloride form anion exchange resin for separation of uranium and plutonium from americium.

McKibbin, T.T.

1993-03-02T23:59:59.000Z

73

Proceedings of the Plutonium Futures ? The Science 2006 Conference  

SciTech Connect

Plutonium Futures--The Science 2006 provided opportunities to examine present knowledge of the chemical and physical properties of plutonium and other actinides in complex media and materials; to discuss the current and emerging science (chemistry, physics, materials science, nuclear science, and environmental effects) of plutonium and actinides relevant to enhancing global nuclear security; and to exchange ideas. This international conference also provided a forum for illustrating and enhancing capabilities and interests, and assessing issues in these areas. U.S. and international scientists, engineers, faculty, and students from universities, national laboratories, and DOE's nuclear complex were encouraged to participate and make technical contributions. The Conference ran from Sunday, July 9th through Thursday, July 13th. A popular aspect of the conference was the opening tutorial session on Sunday afternoon intended for students and scientists new to the area of plutonium research. The tutorial was well attended by novices and veterans alike, and featured such diverse topics as; plutonium metallurgy, plutonium in the environment, and international arms control and nonproliferation. Two plenary lectures began each morning and each afternoon session and highlighted the breakout sessions on coordination/organometallic chemistry, solid-state physics, environmental chemistry, materials science, separations and reprocessing, advanced fuels and waste forms, phase transformations, solution and gas-phase chemistry, compounds and complexes, electronic structure and physical properties, and more. Chemistry Highlights--Among the many chemistry highlights presented in this proceedings are the overview of concepts and philosophies on inert nuclear fuel matrices and concerns about the ever-increasing amounts of minor actinides and plutonium generated in the fuel cycle. The various ideas involve multiple reduction schemes for these materials, suggesting fuels for 'burning' or 'cradle-to-grave' accountability for various reactor types. Related work is presented on identification of the unique reaction mechanisms and identification of the intermediate products, including Pu(III), at the end of the PUREX process. In the important area of nuclear forensics, actual scenarios of nuclear materials confiscation and the successes of applying forensics protocols to determine attribution and possible intention are provided. In the area of reactor incidents, there is no other place on Earth like the Chernobyl Site Object Shelter and radioactive aerosol particle characterization studies reflect an important effort described herein. An additional report from another unique environmental site presents results on radionuclide monitoring, fate, and transport in the ecosystem of the Yenisei River in the Krasoyarsk region. In the area of nuclear waste disposal, a study of the ion irradiation damage to pyrochlore compounds with varying amounts of host elements and actinide dopants is presented. Papers on both the aqueous and nonaqueous chemistry of plutonium and other actinides are presented including anhydrous coordination chemistry and redox behavior in the presence of humic materials and the their sorption on common minerals in the environment. Also published herein are reports on the field of anhydrous coordination chemistry of the transuranic elements where there is scarce information. Solid-State and Materials Highlights--Plutonium solid-state and materials research is represented in these proceedings by a wealth of leading edge discovery class research. The breadth of this research is reflected in the topics covered: solid-state; materials science; superconductivity; phase changes, phonons, and entropy; electronic structure and physical properties; surface science and corrosion; and radiation effects, defects, impurities, and property changes. Indeed the scientific challenge and excitement of plutonium can best be highlighted by quoting the tutorial prospectus of Drs. Sarrao and Schwartz. 'Plutonium has long been re

Fluss, M; Hobart, D; Allan, P; Jarvinen, G

2007-07-12T23:59:59.000Z

74

Conference Summary  

Science Conference Proceedings (OSTI)

Summary of the conference, summarizing both theoretical and experimental presentations and discussions.

Brodsky, Stanley J.; /SLAC; Rijssenbeek, Michael; /SUNY, Stony Brook

2005-11-09T23:59:59.000Z

75

Science Conference Proceedings : About  

Office of Scientific and Technical Information (OSTI)

Science Conference Proceedings - Home Science Conference Proceedings - Home Science Conference Proceedings - About Science Conference Proceedings - Advanced Search Science...

76

UTILITY OF MECHANISTIC MODELS FOR DIRECTING ADVANCED SEPARATIONS RESEARCH & DEVELOPMENT ACTIVITIES: Electrochemically Modulated Separation Example  

SciTech Connect

The objective for this work was to demonstrate the utility of mechanistic computer models designed to simulate actinide behavior for use in efficiently and effectively directing advanced laboratory R&D activities associated with developing advanced separations methods.

Schwantes, Jon M.

2009-06-01T23:59:59.000Z

77

Multiphoton processes: conference proceedings  

SciTech Connect

The chapters of this volume represent the invited papers delivered at the conference. They are arranged according to thermatic proximity beginning with atoms and continuing with molecules and surfaces. Section headings include multiphoton processes in atoms, field fluctuations and collisions in multiphoton process, and multiphoton processes in molecules and surfaces. Abstracts of individual items from the conference were prepared separately for the data base. (GHT)

Lambropoulos, P.; Smith, S.J. (eds.)

1984-01-01T23:59:59.000Z

78

Actinide production in /sup 136/Xe bombardments of /sup 249/Cf  

Science Conference Proceedings (OSTI)

The production cross sections for the actinide products from /sup 136/Xe bombardments of /sup 249/Cf at energies 1.02, 1.09, and 1.16 times the Coulomb barrier were determined. Fractions of the individual actinide elements were chemically separated from recoil catcher foils. The production cross sections of the actinide products were determined by measuring the radiations emitted from the nuclides within the chemical fractions. The chemical separation techniques used in this work are described in detail, and a description of the data analysis procedure is included. The actinide production cross section distributions from these /sup 136/Xe + /sup 249/Cf bombardments are compared with the production cross section distributions from other heavy ion bombardments of actinide targets, with emphasis on the comparison with the /sup 136/Xe + /sup 248/Cm reaction. A technique for modeling the final actinide cross section distributions has been developed and is presented. In this model, the initial (before deexcitation) cross section distribution with respect to the separation energy of a dinuclear complex and with respect to the Z of the target-like fragment is given by an empirical procedure. It is then assumed that the N/Z equilibration in the dinuclear complex occurs by the transfer of neutrons between the two participants in the dinuclear complex. The neutrons and the excitation energy are statistically distributed between the two fragments using a simple Fermi gas level density formalism. The resulting target-like fragment initial cross section distribution with respect to Z, N, and excitation energy is then allowed to deexcite by emission of neutrons in competition with fission. The result is a final cross section distribution with respect to Z and N for the actinide products. 68 refs., 33 figs., 6 tabs.

Gregorich, K.E.

1985-08-01T23:59:59.000Z

79

Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials  

SciTech Connect

Spent nuclear fuel from commercial reactors is comprised of 95-99 percent UO{sub 2} and 1-5 percent fission products and transuranic elements. Certain actinides and fission products are of particular interest in terms of fuel stability, which affects reprocessing and waste materials. The transuranics found in spent nuclear fuels are Np, Pu, Am, and Cm, some of which have long half- lives (e.g., 2.1 million years for {sup 237}Np). These actinides can be separated and recycled into new fuel matrices, thereby reducing the nuclear waste inventory. Oxides of these actinides are isostructural with UO{sub 2}, and are expected to form solid solutions. This project will use computational techniques to conduct a comprehensive study on thermodynamic properties of actinide-oxide solid solutions. The goals of this project are to: Determine the temperature-dependent mixing properties of actinide-oxide fuels; Validate computational methods by comparing results with experimental results; Expand research scope to complex (ternary and quaternary) mixed actinide oxide fuels. After deriving phase diagrams and the stability of solid solutions as a function of temperature and pressure, the project team will determine whether potential phase separations or ordered phases can actually occur by studying diffusion of cations and the kinetics of potential phase separations or ordered phases. In addition, the team will investigate the diffusion of fission product gases that can also have a significant influence on fuel stability. Once the system has been established for binary solid solutions of Th, U, Np, and Pu oxides, the methodology can be quickly applied to new compositions that apply to ternaries and quaternaries, higher actinides (Am, Cm), burnable poisons (B, Gd, Hf), and fission products (Cs, Sr, Tc) to improve reactivity.

Becker, Udo [Univ. of Michigan (United States)

2013-04-16T23:59:59.000Z

80

Conference - CECM  

E-Print Network (OSTI)

Finite Geometries (Second Irsee Conference), Kloster Irsee, Germany, September 10-16, 2006. Workshop: Algorithms in algebraic geometry Minnesota,  ...

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
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81

Ceramic Composition for Immobilization of Actinides  

DOE Patents (OSTI)

Disclosed is a ceramic composition for the immobilization of actinides, particularly uranium and plutonium. The ceramic is a titanate material comprising pyrochlore, brannerite and rutile.

Ebbinghaus, Bartley B.; Van Konynenburg, Richard A.; Vance, Eric R.; Stewart, Martin W.; Jostsons, Adam; Allender, Jeffrey S.; Rankin, David Thomas

1999-06-22T23:59:59.000Z

82

CHARACTERIZATION OF ACTINIDES IN SIMULATED ALKALINE TANK WASTE SLUDGES AND LEACHATES  

SciTech Connect

In this project, both the fundamental chemistry of actinides in alkaline solutions (relevant to those present in Hanford-style waste storage tanks), and their dissolution from sludge simulants (and interactions with supernatants) have been investigated under representative sludge leaching procedures. The leaching protocols were designed to go beyond conventional alkaline sludge leaching limits, including the application of acidic leachants, oxidants and complexing agents. The simulant leaching studies confirm in most cases the basic premise that actinides will remain in the sludge during leaching with 2-3 M NaOH caustic leach solutions. However, they also confirm significant chances for increased mobility of actinides under oxidative leaching conditions. Thermodynamic data generated improves the general level of experiemental information available to predict actinide speciation in leach solutions. Additional information indicates that improved Al removal can be achieved with even dilute acid leaching and that acidic Al(NO3)3 solutions can be decontaminated of co-mobilized actinides using conventional separations methods. Both complexing agents and acidic leaching solutions have significant potential to improve the effectiveness of conventional alkaline leaching protocols. The prime objective of this program was to provide adequate insight into actinide behavior under these conditions to enable prudent decision making as tank waste treatment protocols develop.

Nash, Kenneth L.

2008-11-20T23:59:59.000Z

83

EA-1404: Actinide Chemistry and Repository Science Laboratory...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4: Actinide Chemistry and Repository Science Laboratory, Carlsbad, New Mexico EA-1404: Actinide Chemistry and Repository Science Laboratory, Carlsbad, New Mexico SUMMARY This EA...

84

EIA - 2008 Conference Presentation Videos  

U.S. Energy Information Administration (EIA)

Home > Presentations & Conferences > Conferences > EIA 2008 Energy Conference > EIA 2008 Energy Conference Videos. EIA Documentary - produced for 2008 EIA Conference

85

Status of development of actinide blanket processing flowsheets for accelerator transmutation of nuclear waste  

SciTech Connect

An accelerator-driven subcritical nuclear system is briefly described that transmutes actinides and selected long-lived fission products. An application of this accelerator transmutation of nuclear waste (ATW) concept to spent fuel from a commercial nuclear power plant is presented as an example. The emphasis here is on a possible aqueous processing flowsheet to separate the actinides and selected long-lived fission products from the remaining fission products within the transmutation system. In the proposed system the actinides circulate through the thermal neutron flux as a slurry of oxide particles in heavy water in two loops with different average residence times: one loop for neptunium and plutonium and one for americium and curium. Material from the Np/Pu loop is processed with a short cooling time (5-10 days) because of the need to keep the total actinide inventory, low for this particular ATW application. The high radiation and thermal load from the irradiated material places severe constraints on the separation processes that can be used. The oxide particles are dissolved in nitric acid and a quarternary, ammonium anion exchanger is used to extract neptunium, plutonium, technetium, and palladium. After further cooling (about 90 days), the Am, Cm and higher actinides are extracted using a TALSPEAK-type process. The proposed operations were chosen because they have been successfully tested for processing high-level radioactive fuels or wastes in gram to kilogram quantities.

Dewey, H.J.; Jarvinen, G.D.; Marsh, S.F.; Schroeder, N.C.; Smith, B.F.; Villarreal, R.; Walker, R.B.; Yarbro, S.L.; Yates, M.A.

1993-09-01T23:59:59.000Z

86

Conference Reviews  

Science Conference Proceedings (OSTI)

"Houston's Terra Firma Hosts the Silver Anniversary of the Offshore Technology Conference" (TMS News), July 1993, pp. 65, 68. "The Impact of the New ...

87

Method for reprocessing and separating spent nuclear fuels  

DOE Patents (OSTI)

Spent nuclear fuels, including actinide fuels, volatile and non-volatile fission products, are reprocessed and separated in a molten metal solvent housed in a separation vessel made of a carbon-containing material. A first catalyst, which promotes the solubility and permeability of carbon in the metal solvent, is included. By increasing the solubility and permeability of the carbon in the solvent, the rate at which actinide oxides are reduced (carbothermic reduction) is greatly increased. A second catalyst, included to increase the affinity for nitrogen in the metal solvent, is added to increase the rate at which actinide nitrides form after carbothermic reduction is complete.

Krikorian, Oscar H. (Danville, CA); Grens, John Z. (Livermore, CA); Parrish, Sr., William H. (Walnut Creek, CA)

1983-01-01T23:59:59.000Z

88

Method for reprocessing and separating spent nuclear fuels. [Patent application  

DOE Patents (OSTI)

Spent nuclear fuels, including actinide fuels, volatile and nonvolatile fission products, are reprocessed and separated in a molten metal solvent housed in a separation vessel made of a carbon-containing material. A first catalyst, which promotes the solubility and permeability of carbon in the metal solvent, is included. By increasing the solubility and permeability of the carbon in the solvent, the rate at which actinide oxides are reduced (carbothermic reduction) is greatly increased. A second catalyst, included to increase the affinity for nitrogen in the metal solvent, is added to increase the rate at which actinide nitrides form after carbothermic reduction is complete.

Krikorian, O.H.; Grens, J.Z.; Parrish, W.H. Sr.

1982-01-19T23:59:59.000Z

89

Plutonium and minor actinides utilization in Thorium molten salt reactor  

Science Conference Proceedings (OSTI)

FUJI-12 reactor is one of MSR systems that proposed by Japan. The original FUJI-12 design considers Th/{sup 233}U or Th/Pu as main fuel. In accordance with the currently suggestion to stay away from the separation of Pu and minor actinides (MA), in this study we evaluated the utilization of Pu and MA in FUJI-12. The reactor grade Pu was employed in the present study as a small effort of supporting THORIMS-NES scenario. The result shows that the reactor can achieve its criticality with the Pu and MA composition in the fuel of 5.96% or more.

Waris, Abdul; Aji, Indarta K.; Novitrian,; Kurniadi, Rizal; Su'ud, Zaki [Nuclear Physics and Biophysics Research Division, Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jalan Ganesa 10 Bandung 40132 (Indonesia)

2012-06-06T23:59:59.000Z

90

Method for extracting lanthanides and actinides from acid solutions by modification of Purex solvent  

DOE Patents (OSTI)

A process has been developed for the extraction of multivalent lanthanide and actinide values from acidic waste solutions, and for the separation of these values from fission product and other values, which utilizes a new series of neutral bi-functional extractants, the alkyl(phenyl)-N, N-dialkylcarbamoylmethylphosphine oxides, in combination with a phase modifier to form an extraction solution. The addition of the extractant to the Purex process extractant, tri-n-butylphosphate in normal paraffin hydrocarbon diluent, will permit the extraction of multivalent lanthanide and actinide values from 0.1 to 12.0 molar acid solutions.

Horwitz, E.P.; Kalina, D.G.

1984-05-21T23:59:59.000Z

91

EJ Conference  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EJ Conference, Inc. EJ Conference, Inc. Presents DOUBLETREE HOTEL CRYSTAL CITY 300 ARMY NAVY DRIVE ARLINGTON, VA 22202 MAY 27-29, 2009 Meet the Agencies and Exhibit Registration Form One of the recommendations from the 2008 State of Environmental Justice in America Conference was the introduction of an activity through which participants would have an opportunity to engage in short-but-informative conversations with representatives of various Federal agencies It was noted that the conference is one of few for many local community participants to obtain an audience with high- level Federal officials. Since one of the stated purposes of the conference is to bring together diverse groups of individuals interested in environmental justice through a process of substantive and honest

92

Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation  

E-Print Network (OSTI)

Potential Uses for Depleted Uranium Oxide. 2009, DOE. p.15. WNA. Uranium and Depleted Uranium. 2009 [cited 2010R. , Direct Use of Depleted Uranium As Fuel in a Traveling-

Heidet, Florent

2010-01-01T23:59:59.000Z

93

Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation  

E-Print Network (OSTI)

without need for uranium enrichment capability or actinidesfor expanding the uranium enrichment capacity and withoutleft over from the uranium enrichment process: (1) Per unit

Heidet, Florent

2010-01-01T23:59:59.000Z

94

Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation  

E-Print Network (OSTI)

if(tvar~/^102/)rxName="SNG" else if(tvar~/^16/)rxName="SN2N"=NR&&c1==2&&$1~/^SNA$/{sna[iso]=$2} FNR==NR&&c1==2&&$1~/^SNG$/{sng[iso]=$2} FNR==NR&&c1==2&&$1~/^SNAB$/{snab[iso]=$2}

Heidet, Florent

2010-01-01T23:59:59.000Z

95

Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation  

E-Print Network (OSTI)

Wood, Completely automated nuclear reactors for long- termhandbook: Nuclear physics and reactor theory. 1993. (121 p).The analysis of any nuclear reactor system is closely

Heidet, Florent

2010-01-01T23:59:59.000Z

96

Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation  

E-Print Network (OSTI)

According to the DOE handbook [57], a shutdown margin largerp. 812. Not, A. , DOE fundamentals handbook: Nuclear physics

Heidet, Florent

2010-01-01T23:59:59.000Z

97

Method for decontamination of nickel-fluoride-coated nickel containing actinide-metal fluorides  

DOE Patents (OSTI)

The invention is a process for decontaminating particulate nickel contaminated with actinide-metal fluorides. In one aspect, the invention comprises contacting nickel-fluoride-coated nickel with gaseous ammonia at a temperature effecting nickel-catalyzed dissociation thereof and effecting hydrogen-reduction of the nickel fluoride. The resulting nickel is heated to form a melt and a slag and to effect transfer of actinide metals from the melt into the slag. The melt and slag are then separated. In another aspect, nickel containing nickel oxide and actinide metals is contacted with ammonia at a temperature effecting nickel-catalyzed dissociation to effect conversion of the nickel oxide to the metal. The resulting nickel is then melted and separated as described. In another aspect nickel-fluoride-coated nickel containing actinide-metal fluorides is contacted with both steam and ammonia. The resulting nickel then is melted and separated as described. The invention is characterized by higher nickel recovery, efficient use of ammonia, a substantial decrease in slag formation and fuming, and a valuable increase in the service life of the furnace liners used for melting.

Windt, Norman F. (Paducah, KY); Williams, Joe L. (Paducah, KY)

1983-01-01T23:59:59.000Z

98

Actinide removal from spent salts  

DOE Patents (OSTI)

A method for removing actinide contaminants (uranium and thorium) from the spent salt of a molten salt oxidation (MSO) reactor is described. Spent salt is removed from the reactor and analyzed to determine the contaminants present and the carbonate concentration. The salt is dissolved in water, and one or more reagents are added to precipitate the thorium as thorium oxide and/or the uranium as either uranium oxide or as a diuranate salt. The precipitated materials are filtered, dried and packaged for disposal as radioactive waste. About 90% of the thorium and/or uranium present is removed by filtration. After filtration, salt solutions having a carbonate concentration >20% can be dried and returned to the reactor for re-use. Salt solutions containing a carbonate concentration <20% require further clean-up using an ion exchange column, which yields salt solutions that contain less than 0.1 ppm of thorium or uranium.

Hsu, Peter C. (Pleasanton, CA); von Holtz, Erica H. (Livermore, CA); Hipple, David L. (Livermore, CA); Summers, Leslie J. (Livermore, CA); Adamson, Martyn G. (Danville, CA)

2002-01-01T23:59:59.000Z

99

Overview of actinide chemistry in the WIPP  

Science Conference Proceedings (OSTI)

The year 2009 celebrates 10 years of safe operations at the Waste Isolation Pilot Plant (WIPP), the only nuclear waste repository designated to dispose defense-related transuranic (TRU) waste in the United States. Many elements contributed to the success of this one-of-the-kind facility. One of the most important of these is the chemistry of the actinides under WIPP repository conditions. A reliable understanding of the potential release of actinides from the site to the accessible environment is important to the WIPP performance assessment (PA). The environmental chemistry of the major actinides disposed at the WIPP continues to be investigated as part of the ongoing recertification efforts of the WIPP project. This presentation provides an overview of the actinide chemistry for the WIPP repository conditions. The WIPP is a salt-based repository; therefore, the inflow of brine into the repository is minimized, due to the natural tendency of excavated salt to re-seal. Reducing anoxic conditions are expected in WIPP because of microbial activity and metal corrosion processes that consume the oxygen initially present. Should brine be introduced through an intrusion scenario, these same processes will re-establish reducing conditions. In the case of an intrusion scenario involving brine, the solubilization of actinides in brine is considered as a potential source of release to the accessible environment. The following key factors establish the concentrations of dissolved actinides under subsurface conditions: (1) Redox chemistry - The solubility of reduced actinides (III and IV oxidation states) is known to be significantly lower than the oxidized forms (V and/or VI oxidation states). In this context, the reducing conditions in the WIPP and the strong coupling of the chemistry for reduced metals and microbiological processes with actinides are important. (2) Complexation - For the anoxic, reducing and mildly basic brine systems in the WIPP, the most important inorganic complexants are expected to be carbonate/bicarbonate and hydroxide. There are also organic complexants in TRU waste with the potential to strongly influence actinide solubility. (3) Intrinsic and pseudo-actinide colloid formation - Many actinide species in their expected oxidation states tend to form colloids or strongly associate with non actinide colloids present (e.g., microbial, humic and organic). In this context, the relative importance of actinides, based on the TRU waste inventory, with respect to the potential release of actinides from the WIPP, is greater for plutonium and americium, and to less extent for uranium and thorium. The most important oxidation states for WIPP-relevant conditions are III and IV. We will present an update of the literature on WIPP-specific data, and a summary of the ongoing research related to actinide chemistry in the WIPP performed by the Los Alamos National Laboratory (LANL) Actinide Chemistry and Repository Science (ACRSP) team located in Carlsbad, NM [Reed 2007, Lucchini 2007, and Reed 2006].

Borkowski, Marian [Los Alamos National Laboratory; Lucchini, Jean - Francois [Los Alamos National Laboratory; Richmann, Michael K [Los Alamos National Laboratory; Reed, Donald T [Los Alamos National Laboratory; Khaing, Hnin [Los Alamos National Laboratory; Swanson, Juliet [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

100

SPECIFIC SEQUESTERING AGENTS FOR THE ACTINIDES  

E-Print Network (OSTI)

for the actinides. Two tetra-catechol chelating agents wereprotons. The acidity of the catechol groups can be increased43 and 46. Figure 4. catechol aqueous solution, on a hanging

Raymond, Kenneth N.

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
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to obtain the most current and comprehensive results.


101

BWR Assembly Optimization for Minor Actinide Recycling  

Science Conference Proceedings (OSTI)

The Primary objective of the proposed project is to apply and extend the latest advancements in LWR fuel management optimization to the design of advanced boiling water reactor (BWR) fuel assemblies specifically for the recycling of minor actinides (MAs).

G. Ivan Maldonado; John M. Christenson; J.P. Renier; T.F. Marcille; J. Casal

2010-03-22T23:59:59.000Z

102

Actinide minimization using pressurized water reactors  

E-Print Network (OSTI)

Transuranic actinides dominate the long-term radiotoxity in spent LWR fuel. In an open fuel cycle, they impose a long-term burden on geologic repositories. Transmuting these materials in reactor systems is one way to ease ...

Visosky, Mark Michael

2006-01-01T23:59:59.000Z

103

Lattice effects in the light actinides  

Science Conference Proceedings (OSTI)

The light actinides show a variety of lattice effects that do not normally appear in other regions of the periodic table. The article will cover the crystal structures of the light actinides, their atomic volumes, their thermal expansion behavior, and their elastic behavior as reflected in recent thermal vibration measurements made by neutron diffraction. A discussion of the melting points will be given in terms of the thermal vibration measurements. Pressure effects will be only briefly indicated.

Lawson, A.C.; Cort, B.; Roberts, J.A.; Bennett, B.I.; Brun, T.O.; Dreele, R.B. von [Los Alamos National Lab., NM (United States); Richardson, J.W. Jr. [Argonne National Lab., IL (United States)

1998-12-31T23:59:59.000Z

104

Final Report on Actinide Glass Scintillators for Fast Neutron Detection  

Science Conference Proceedings (OSTI)

This is the final report of an experimental investigation of actinide glass scintillators for fast-neutron detection. It covers work performed during FY2012. This supplements a previous report, PNNL-20854 “Initial Characterization of Thorium-loaded Glasses for Fast Neutron Detection” (October 2011). The work in FY2012 was done with funding remaining from FY2011. As noted in PNNL-20854, the glasses tested prior to July 2011 were erroneously identified as scintillators. The decision was then made to start from “scratch” with a literature survey and some test melts with a non-radioactive glass composition that could later be fabricated with select actinides, most likely thorium. The normal stand-in for thorium in radioactive waste glasses is cerium in the same oxidation state. Since cerium in the 3+ state is used as the light emitter in many scintillating glasses, the next most common substitute was used: hafnium. Three hafnium glasses were melted. Two melts were colored amber and a third was clear. It barely scintillated when exposed to alpha particles. The uses and applications for a scintillating fast neutron detector are important enough that the search for such a material should not be totally abandoned. This current effort focused on actinides that have very high neutron capture energy releases but low neutron capture cross sections. This results in very long counting times and poor signal to noise when working with sealed sources. These materials are best for high flux applications and access to neutron generators or reactors would enable better test scenarios. The total energy of the neutron capture reaction is not the only factor to focus on in isotope selection. Many neutron capture reactions result in energetic gamma rays that require large volumes or high densities to detect. If the scintillator is to separate neutrons from gamma rays, the capture reactions should produce heavy particles and few gamma rays. This would improve the detection of a signal for fast neutron capture.

Bliss, Mary; Stave, Jean A.

2012-10-01T23:59:59.000Z

105

Nonaqueous method for dissolving lanthanide and actinide metals  

DOE Patents (OSTI)

Lanthanide and actinide beta-diketonate complex molecular compounds are produced by reacting a beta-diketone compound with a lanthanide or actinide element in the elemental metallic state in a mixture of carbon tetrachloride and methanol.

Crisler, L.R.

1975-11-11T23:59:59.000Z

106

EJ Conference  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Howard University School of Law (Washington, DC) on May 27, 2009 Howard University School of Law (Washington, DC) on May 27, 2009 Crystal City Doubletree Hotel (300 Army Navy Drive, Arlington, VA 22202) on May 28 and 29, 2009 Meet the Agencies Request for Appointment One of the recommendations from the 2008 State of Environmental Justice in America Conference was the introduction of an activity through which participants would have an opportunity to engage in short-but-informative conversations with representatives of various Federal agencies. It was noted that the conference is one of few occasions for many local community participants to obtain an audience with high-level Federal officials. Since one of the stated purposes of the conference is to bring together diverse groups of individuals interested in

107

Superconductivity Conference Held  

NLE Websites -- All DOE Office Websites (Extended Search)

Superconductivity Conference Held Z.-X. Shen SSRL sponsored a major international conference on superconductivity early this year. The conference, entitled "Spectroscopies in Novel...

108

Combined Extraction of Cesium, Strontium, and Actinides from Alkaline Media: An Extension of the Caustic-Side Solvent Extraction (CSSX) Process Technology  

Science Conference Proceedings (OSTI)

The wastes present at DOE long-term storage sites are usually highly alkaline, and because of this, much of the actinides in these wastes are in the sludge phase. Enough actinide materials still remain in the supernatant liquid that they require separation followed by long-term storage in a geological repository. The removal of these metals from the liquid waste stream would permit their disposal as low-level waste and dramatically reduce the volume of high-level wastes.

Kenneth Raymond

2004-11-03T23:59:59.000Z

109

Ultratrace analysis of transuranic actinides by laser-induced fluorescence  

DOE Patents (OSTI)

Ultratrace quantities of transuranic actinides are detected indirectly by their effect on the fluorescent emissions of a preselected fluorescent species. Transuranic actinides in a sample are coprecipitated with a host lattice material containing at least one preselected fluorescent species. The actinide either quenches or enhances the laser-induced fluorescence of the preselected fluorescent species. The degree of enhancement or quenching is quantitatively related to the concentration of actinide in the sample.

Miller, Steven M. (Chelmsford, MA)

1988-01-01T23:59:59.000Z

110

Operation of a bushing melter system designed for actinide vitrification  

SciTech Connect

The Westinghouse Savannah River Company is developing a melter system to vitrify actinide materials. The melter system will used to vitrify the americium and curium solution which is currently stored in one of the Savannah River Site`s (SRS) processing canyons. This solution is one of the materials designated by the Defense Nuclear Facilities Safety Board (DNFSB) to be dispositioned as part of the DNFSB recommendation 94-1. The Am/Cm solution contains an extremely large fraction (>2 kilograms of Cm and 10 kilograms of Am) of t he United States`s total inventory of both elements. They have an estimated value on the order of one billion dollars - if they are processed through the DOE Isotope Sales program at the Oak Ridge National Laboratory. It is therefore deemed highly desirable to transfer the material to Oak Ridge in a form which can allow for recovery of the material. A commercial glass composition has been demonstrated to be compatible with up to 40 weight percent of the Am/Cm solution contents. This glass is also selectively attacked by nitric acid. This allows the actinide to be recovered by common separation processes.

Ramsey, W.G.

1996-03-01T23:59:59.000Z

111

Supercritical Carbon Dioxide-Soluble Ligands for Extracting Actinide Metal Ions from Porous Solids  

SciTech Connect

Numerous types of actinide-bearing waste materials are found throughout the DOE complex. Most of these wastes consist of large volumes of non-hazardous materials contaminated with relatively small quantities of actinide elements. Separation of these wastes into their inert and radioactive components would dramatically reduce the costs of stabilization and disposal. For example, the DOE is responsible for decontaminating concrete within 7000 surplus contaminated buildings. The best technology now available for removing surface contamination from concrete involves removing the surface layer by grit blasting, which produces a large volume of blasting residue containing a small amount of radioactive material. Disposal of this residue is expensive because of its large volume and fine particulate nature. Considerable cost savings would result from separation of the radioactive constituents and stabilization of the concrete dust. Similarly, gas diffusion plants for uranium enrichment contain valuable high-purity nickel in the form of diffusion barriers. Decontamination is complicated by the extremely fine pores in these barriers, which are not readily accessible by most cleaning techniques. A cost-effective method for the removal of radioactive contaminants would release this valuable material for salvage. The objective of this project is to develop novel, substituted diphosphonic acid ligands that can be used for supercritical carbon dioxide extraction of actinide ions from solid wastes. Specifically, selected diphosphonic acids, which are known to form extremely stable complexes with actinides in aqueous and organic solution, are to be rendered carbon dioxide-soluble by the introduction of appropriate alkyl- or silicon-containing substituents. The metal complexation chemistry of these new ligands in SC-CO2 will then be investigated and techniques for their use in actinide extraction from porous solids developed.

Dietz, Mark L.

2001-06-01T23:59:59.000Z

112

A worldwide perspective on actinide burning  

SciTech Connect

Worldwide interest has been evident over the past few years in reexamining the merits of recovering the actinides from spent light-water reactor (LWR) fuel and transmuting them in fast reactors to reduce hazards in geologic repositories. This paper will summarize some of the recent activities in this field. Several countries are embarked on programs of reprocessing and vitrification of present wastes, from which removal of the actinides is largely precluded. The United States is assessing the ideas related to the fast reactor program and the potential application to defense wastes. 18 refs., 2 figs.

Burch, W.D.

1991-01-01T23:59:59.000Z

113

METHOD OF SEPARATING Pu FROM METATHESIZED BiPO$sub 4$ CARRIER  

DOE Patents (OSTI)

A process is given for separating uranium, neptunium, and/or plutonium from a bismuth hydroxide carrier by selective dissolution of these actinides with nitric acid of a concentration of from 0.05 to 0.5N.

Knox, W.J.; Thompson, S.G.

1960-05-31T23:59:59.000Z

114

Characterization of Actinides in Simulated Alkaline Tank Waste Sludges and Leachates  

SciTech Connect

Removal of waste-limiting components of sludge (Al, Cr, S, P) in underground tanks at Hanford by treatment with concentrated alkali has proven less efficacious for Al and Cr removal than had been hoped. More aggressive treatments of sludges, for example, contact with oxidants targeting Cr(III), have been tested in a limited number of samples and found to improve leaching efficiency for Cr. Oxidative alkaline leaching can be expected to have at best a secondary influence on the mobilization of Al. Our earlier explorations of Al leaching from sludge simulants indicated acidic and complexometric leaching can improve Al dissolution. Unfortunately, treatments of sludge samples with oxidative alkaline, acidic or complexing leachates produce conditions under which normally insoluble actinide ions (e.g., Am3+, Pu4+, Np4+) can be mobilized to the solution phase. Few experimental or meaningful theoretical studies of actinide chemistry in strongly alkaline, strongly oxidizing solutions have been completed. Unfortunately, extrapolation of the more abundant acid phase thermodynamic data to these radically different conditions provides limited reliable guidance for predicting actinide speciation in highly salted alkaline solutions. In this project, we are investigating the fundamental chemistry of actinides and important sludge components in sludge simulants and supernatants under representative oxidative leaching conditions. We are examining the potential impact of acidic or complexometric leaching with concurrent secondary separations on Al removal from sludges. Finally, a portion of our research is directed at the control of polyvalent anions (SO4=, CrO4=, PO43-) in waste streams destined for vitrification. Our primary objective is to provide adequate insight into actinide behavior under these conditions to enable prudent decision making as tank waste treatment protocols develop. We expect to identify those components of sludges that are likely to be problematic in the application of oxidative, acidic, and complexometric leaching protocols.

Nash, Kenneth L.

2005-06-01T23:59:59.000Z

115

The role of actinide burning and the Integral Fast Reactor in the future of nuclear power  

Science Conference Proceedings (OSTI)

A preliminary assessment is made of the potential role of actinide burning and the Integral Fast Reactor (IFR) in the future of nuclear power. The development of a usable actinide burning strategy could be an important factor in the acceptance and implementation of a next generation of nuclear power. First, the need for nuclear generating capacity is established through the analysis of energy and electricity demand forecasting models which cover the spectrum of bias from anti-nuclear to pro-nuclear. The analyses take into account the issues of global warming and the potential for technological advances in energy efficiency. We conclude, as do many others, that there will almost certainly be a need for substantial nuclear power capacity in the 2000--2030 time frame. We point out also that any reprocessing scheme will open up proliferation-related questions which can only be assessed in very specific contexts. The focus of this report is on the fuel cycle impacts of actinide burning. Scenarios are developed for the deployment of future nuclear generating capacity which exploit the advantages of actinide partitioning and actinide burning. Three alternative reactor designs are utilized in these future scenarios: The Light Water Reactor (LWR); the Modular Gas-Cooled Reactor (MGR); and the Integral Fast Reactor (FR). Each of these alternative reactor designs is described in some detail, with specific emphasis on their spent fuel streams and the back-end of the nuclear fuel cycle. Four separation and partitioning processes are utilized in building the future nuclear power scenarios: Thermal reactor spent fuel preprocessing to reduce the ceramic oxide spent fuel to metallic form, the conventional PUREX process, the TRUEX process, and pyrometallurgical reprocessing.

Hollaway, W.R.; Lidsky, L.M.; Miller, M.M.

1990-12-01T23:59:59.000Z

116

Preliminary investigation of actinide and xenon reactivity effects in accelerator transmutation of waste high-flux systems  

SciTech Connect

The possibility of an unstable positive reactivity growth in an accelerator transmutation of waste (ATW)-type high-flux system is investigated. While it has always been clear that xenon is an important actor in the reactivity response of a system to flux changes, it has been suggested that in very high thermal flux transuranic burning systems, a positive, unstable reactivity growth could be caused by the actinides alone. Initial system reactivity response to flux changes caused by the actinides and xenon are investigated separately. The maximum change in reactivity after a flux change caused by the effect of the changing quantities of actinides is generally at least two orders of magnitude smaller than either the positive or negative reactivity effect associated with xenon after a shutdown or startup. In any transient flux event, the reactivity response of the system to xenon will generally occlude the response caused by the actinides. The capabilities and applications of both the current actinide model and the xenon model are discussed. Finally, the need for a complete dynamic model for the high-flux fluid-fueled ATW system is addressed.

Olson, K.R.; Henderson, D.L. [Univ. of Wisconsin, Madison, WI (United States). Dept. of Nuclear Engineering and Engineering Physics; Woosley, M.L. Jr. [Univ. of virginia, Charlottesville, VA (United States). Dept. of Mechanical, Aerospace, and Nuclear Engineering; Sailor, W.C. [Los Alamos National Lab., NM (United States)

1995-04-01T23:59:59.000Z

117

Synthesis of actinide nitrides, phosphides, sulfides and oxides  

DOE Patents (OSTI)

This invention is comprised of a process of preparing an actinide compound of the formula An{sub x}Z{sub y} wherein An is an actinide metal atom selected from the group consisting of thorium, uranium, plutonium, neptunium, and americium, x is selected from the group consisting of one, two or three, Z is a main group element atom selected from the group consisting of nitrogen, phosphorus, oxygen and sulfur and y is selected from the group consisting of one, two, three or four, by admixing an actinide organometallic precursor wherein said actinide is selected from the group consisting of thorium, uranium, plutonium, neptunium, and americium, a suitable solvent and a protic Lewis base selected from the group consisting of ammonia, phosphine, hydrogen sulfide and water, at temperatures and for time sufficient to form an intermediate actinide complex, heating said intermediate actinide complex at temperatures and for time sufficient to form the actinide compound, and a process of depositing a thin film of such an actinide compound, e.g., uranium mononitride, by subliming an actinide organometallic precursor, e.g., a uranium amide precursor, in the presence of an effective amount of a protic Lewis base, e.g., ammonia, within a reactor at temperatures and for time sufficient to form a thin film of the actinide compound, are disclosed.

Van Der Sluys, W.G.; Burns, C.J.; Smith, D.C.

1991-04-02T23:59:59.000Z

118

Synthesis of actinide nitrides, phosphides, sulfides and oxides  

DOE Green Energy (OSTI)

A process of preparing an actinide compound of the formula An.sub.x Z.sub.y wherein An is an actinide metal atom selected from the group consisting of thorium, uranium, plutonium, neptunium, and americium, x is selected from the group consisting of one, two or three, Z is a main group element atom selected from the group consisting of nitrogen, phosphorus, oxygen and sulfur and y is selected from the group consisting of one, two, three or four, by admixing an actinide organometallic precursor wherein said actinide is selected from the group consisting of thorium, uranium, plutonium, neptunium, and americium, a suitable solvent and a protic Lewis base selected from the group consisting of ammonia, phosphine, hydrogen sulfide and water, at temperatures and for time sufficient to form an intermediate actinide complex, heating said intermediate actinide complex at temperatures and for time sufficient to form the actinide compound, and a process of depositing a thin film of such an actinide compound, e.g., uranium mononitride, by subliming an actinide organometallic precursor, e.g., a uranium amide precursor, in the presence of an effectgive amount of a protic Lewis base, e.g., ammonia, within a reactor at temperatures and for time sufficient to form a thin film of the actinide compound, are disclosed.

Van Der Sluys, William G. (Missoula, MT); Burns, Carol J. (Los Alamos, NM); Smith, David C. (Los Alamos, NM)

1992-01-01T23:59:59.000Z

119

Electrorecovery of actinides at room temperature  

Science Conference Proceedings (OSTI)

There are a large number of purification and processing operations involving actinide species that rely on high-temperature molten salts as the solvent medium. One such application is the electrorefining of impure actinide metals to provide high purity material for subsequent applications. There are some drawbacks to the electrodeposition of actinides in molten salts including relatively low yields, lack of accurate potential control, maintaining efficiency in a highly corrosive environment, and failed runs. With these issues in mind we have been investigating the electrodeposition of actinide metals, mainly uranium, from room temperature ionic liquids (RTILs) and relatively high-boiling organic solvents. The RTILs we have focused on are comprised of 1,3-dialkylimidazolium or quaternary ammonium cations and mainly the {sup -}N(SO{sub 2}CF{sub 3}){sub 2} anion [bis(trif1uoromethylsulfonyl)imide {equivalent_to} {sup -}NTf{sub 2}]. These materials represent a class of solvents that possess great potential for use in applications employing electrochemical procedures. In order to ascertain the feasibility of using RTILs for bulk electrodeposition of actinide metals our research team has been exploring the electron transfer behavior of simple coordination complexes of uranium dissolved in the RTIL solutions. More recently we have begun some fundamental electrochemical studies on the behavior of uranium and plutonium complexes in the organic solvents N-methylpyrrolidone (NMP) and dimethylsulfoxide (DMSO). Our most recent results concerning electrodeposition will be presented in this account. The electrochemical behavior of U(IV) and U(III) species in RTILs and the relatively low vapor pressure solvents NMP and DMSO is described. These studies have been ongoing in our laboratory to uncover conditions that will lead to the successful bulk electrodeposition of actinide metals at a working electrode surface at room temperature or slightly elevated temperatures. The RTILs we have focused on thus far are based on 1,3-dialkylimidazolium or quaternary ammonium cations and {sup -}N(SO{sub 2}CF{sub 3}){sub 2} anions. Our results from XPS studies of e1ectrooxidized uranium metal surfaces indicate that uranium metal reacts with the anion from the RTIL, most likely through an initial f1uoride abstraction, forming decomposition products that inhibit the bulk electrodeposition of uranium metal. Similar results were found when the organic solvents were used with TBA[B(C{sub 6}F{sub 5}){sub 4}] as the supporting electrolyte, although the voltammetric data of uranium ions in these solutions is more encouraging in relation to electrodeposition of uranium metal. Preliminary results on the voltammetric behavior and bulk electrodeposition of plutonium species are also presented.

Stoll, Michael E [Los Alamos National Laboratory; Oldham, Warren J [Los Alamos National Laboratory; Costa, David A [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

120

Conferences & Seminars  

E-Print Network (OSTI)

www.asse.org/military Message from the Chair As a follow-up to the March 2012 issue, the Military Branch staffed the ASSE display during the Navy-sponsored Safety PDC in Hampton, VA, and I attended the Pacific Rim Safety Conference in Honolulu, HI. We did not have an opportunity to visit with the Coast Guard Safety Director, but that should happen in the near future. From the perspective of the Military Branch, the Navy PDC was a great success. We talked to many potential members and connected with parts of the uniformed services that we had not previously reached. The Pac Rim conference was not as fruitful because duty commitments kept local active duty members away. As I forecast in the last issue, OSHA publish the final rule of the revised Hazard Communication Standard (1910.1200). The standard was revised to make it consistent with the United Nations ’ effort to implement a globally harmonized system of safety data sheets, labels and other nomenclature for hazardous

Bill Parsons; Chris Gates; Robert Barnette; Shawn Lewis; Pam Wilkinson

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
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121

Separation of strontium from fecal matter  

DOE Patents (OSTI)

The present invention relates to a method of separating strontium, and, more particularly, to a method of separating strontium from a sample of biomass potentially contaminated with various radionuclides. Radioactive strontium is a radionuclide which represents a hazard to man because of its long half-life and, if ingested, its tendency to be retained in the human body. In the event that radionuclides such as strontium or various actinides are ingested, it is desirable to monitor the discharge or release of these radionuclides from the human body through analysis of fecal matter. In laboratories and other facilities where potential for radionuclide contamination exists, fecal analysis for strontium is routinely conducted for individuals who are terminating from their position or are suspected of having been contaminated with radionuclides. Methods for separating and analyzing radioactive actinides from a biomass sample are well known and have been extensively developed for the US Department of Energy. These methods, described in the Department`s internal procedure, USDOE, RESL/ID, A-16, 1981, as well as in US Patent 5,190,881, involve the use of an iron phosphate precipitation step to separate actinides from a solution, or supernate. However, there are no established procedures for the separation of strontium from a biomass sample wherein an iron phosphate precipitation step is involved.

Kester, D.K.

1994-12-31T23:59:59.000Z

122

Surrogate Reactions in the Actinide Region  

SciTech Connect

Over the past three years we have studied various surrogate reactions (d,p), ({sup 3}He,t), ({alpha},{alpha}{sup '}) on several uranium isotopes {sup 234}U, {sup 235}U, {sup 236}U, and {sup 238}U. An overview of the STARS/LIBERACE surrogate research program as it pertains to the actinides is discussed. A summary of results to date will be presented along with a discussion of experimental difficulties encountered in surrogate experiments and future research directions.

Burke, J. T.; Bernstein, L. A.; Scielzo, N. D.; Bleuel, D. L.; Lesher, S. R.; Escher, J.; Ahle, L.; Dietrich, F. S.; Hoffman, R. D.; Norman, E. B.; Sheets, S. A.; Phair, L.; Fallon, P.; Clark, R. M.; Gibelin, J.; Jewett, C.; Lee, I. Y.; Macchiavelli, A. O.; McMahan, M. A.; Moretto, L. G. [Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Lawrence Berkeley National Laboratory, Berkeley, California, 94720 (United States); University of California, Berkeley, Berkeley, California, 94720 (United States); University of Richmond, Richmond, Virginia, 23173 (United States); Yale University, New Haven, Connecticut, 06520 (United States); Rutgers University, New Brunswick, New Jersey, 08901 (United States)] (and others)

2008-04-17T23:59:59.000Z

123

Joint Actinide Shock Physics Experimental Research Facility Restart...  

NLE Websites -- All DOE Office Websites (Extended Search)

Office of Safety and Emergency Management Evaluations Activity Report for the Joint Actinide Shock Physics Experimental Research Facility Restart Operational Readiness...

124

Complexation of Actinides in Solution: Thermodynamic Measurements and Structural Characterization  

E-Print Network (OSTI)

of Actinides in Solution: Thermodynamic Measurements andAn integrated approach of thermodynamic measurements andAn integrated approach of thermodynamic measurements and

Rao, L.

2007-01-01T23:59:59.000Z

125

REPORT: Inert-Matrix Fuel: Actinide ''Burning'' and Direct ... - TMS  

Science Conference Proceedings (OSTI)

Jun 27, 2007 ... Excess actinides result from the dismantlement of nuclear weapons (Pu) and the reprocessing of commercial spent nuclear fuel (mainly 241 Am ...

126

Advanced Nuclear Fuel Concepts for Minor Actinide Burning  

Science Conference Proceedings (OSTI)

Abstract Scope, New fuel cycle strategies entail advanced nuclear fuel concepts. This especially applies for the burning of minor actinides in a fast reactor cycle ...

127

Joint Actinide Shock Physics Experimental Research Facility Restart...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

and Emergency Management Evaluations Activity Report for the Joint Actinide Shock Physics Experimental Research Facility Restart Operational Readiness Review Pre- Visit Dates...

128

Investigation of Separation Performances of Various Isotope Exchange Catalysts for the Deuterium-Hydrogen System  

Science Conference Proceedings (OSTI)

Isotope Separation / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

I. Cristescu; Ioana-R. Cristescu; U. Tamm; R.-D. Penzhorn; C. J. Caldwell-Nichols

129

Proceedings of the fourth annual international conference of the Nuclear Target Development Society, September 30--October 1--2, 1975  

SciTech Connect

Twenty-one papers were presented at the conference. A separate abstract was prepared for each paper. (JRD)

Thomas, G.E.; Karasek, F.J. (eds.)

1975-01-01T23:59:59.000Z

130

Eighth national passive solar conference. Final report  

DOE Green Energy (OSTI)

The Eighth National Passive Solar Conference was held near Santa Fe, New Mexico at the Glorieta Conference Center on September 5 to 11, 1983. Nearly 900 people from all across the nation and the world attended the conference. Close to 200 technical papers were presented, 50 solar product exhibits were available; 34 poster sessions were presented; 16 solar workshops were conducted; 10 renowned solar individuals participated in rendezvous sessions; 7 major addresses were delivered; 5 solar home tours were conducted; 2 emerging architecture sessions were held which included 21 separate presentations; and commercial product presentations were given for the first time ever at a national passive solar conference. Peter van Dresser of Santa Fe received the prestigious Passive Solar Pioneer Award, posthumously, from the American Solar Energy Society and Benjamin T. Buck Rogers of Embudo received the prestigious Peter van Dresser Award from the New Mexico Solar Energy Association. This report reviews conference organization, attendance, finances, conference evaluation form results, and includes press coverage samples, selected conference photos courtesy of Marshall Tyler, and a summary with recommendations for future conferences. The Appendices included conference press releases and a report by the New Mexico Solar Industry Development Corporation on exhibits management.

Owen, A.; Zee, R.

1983-12-01T23:59:59.000Z

131

SEPARATION OF TRANSURANIC ELEMENTS FROM RARE EARTH COMPOUNDS  

DOE Patents (OSTI)

A process of separating neptunium and plutonium values from rare earths and alkaline earth fission products present on a solid mixed actinide carrier (Th or U(IV) oxalate or fluoride) --fission product carrier (LaF/sub 3/, CeF/sub 3/, SrF/sub 2/, CaF/sub 2/, YF/sub 3/, La oxalate, cerous oxalate, Sr oxalate, Ca oxalate or Y oxalate) by extraction of the actinides at elevated temperature with a solution of ammonium fluoride and/or ammonium oxalate is described. Separation of the fission-product-containing carriers from the actinide solution formed and precipitation of the neptunium and plutonium from the solution with mineral acid are also accomplished. (AEC)

Kohman, T.P.

1961-11-21T23:59:59.000Z

132

SEPARATION OF METAL SALTS BY ADSORPTION  

DOE Patents (OSTI)

It has been found that certain metal salts, particularly the halides of iron, cobalt, nickel, and the actinide metals, arc readily absorbed on aluminum oxide, while certain other salts, particularly rare earth metal halides, are not so absorbed. Use is made of this discovery to separate uranium from the rare earths. The metal salts are first dissolved in a molten mixture of alkali metal nitrates, e.g., the eutectic mixture of lithium nitrate and potassium nitrate, and then the molten salt solution is contacted with alumina, either by slurrying or by passing the salt solution through an absorption tower. The process is particularly valuable for the separation of actinides from lanthanum-group rare earths.

Gruen, D.M.

1959-01-20T23:59:59.000Z

133

APPA Customer Connections Conference  

Energy.gov (U.S. Department of Energy (DOE))

The Customer Connections Conference is APPA's annual meeting for utility professionals in the areas of:

134

Apparatus and method for reprocessing and separating spent nuclear fuels. [Patent application  

DOE Patents (OSTI)

Spent nuclear fuels, including actinide fuels, volatile and non-volatile fission products, are reprocessed and separated in a molten metal solvent housed in the reaction region of a separation vessel which includes a reflux region positioned above the molten tin solvent. The reflux region minimizes loss of evaporated solvent during the separation of the actinide fuels from the volatile fission products. Additionally, inclusion of the reflux region permits the separation of the more volatile fission products (noncondensable) from the less volatile ones (condensable).

Krikorian, O.H.; Grens, J.Z.; Parrish, W.H. Sr.

1982-01-19T23:59:59.000Z

135

Process for Making a Ceramic Composition for Immobilization of Actinides  

DOE Patents (OSTI)

Disclosed is a process for making a ceramic composition for the immobilization of actinides, particularly uranium and plutonium. The ceramic is a titanate material comprising pyrochlore, brannerite and rutile. The process comprises oxidizing the actinides, milling the oxides to a powder, blending them with ceramic precursors, cold pressing the blend and sintering the pressed material.

Ebbinghaus, Bartley B.; Van Konynenburg, Richard A.; Vance, Eric R.; Stewart, Martin W.; Walls, Philip A.; Brummond, William Allen; Armantrout, Guy A.; Curtis, Paul G.; Hobson, Beverly F.; Farmer, Joseph; Herman, Connie Cicero; Herman, David Thomas

1999-06-22T23:59:59.000Z

136

Process for making a ceramic composition for immobilization of actinides  

DOE Patents (OSTI)

Disclosed is a process for making a ceramic composition for the immobilization of actinides, particularly uranium and plutonium. The ceramic is a titanate material comprising pyrochlore, brannerite and rutile. The process comprises oxidizing the actinides, milling the oxides to a powder, blending them with ceramic precursors, cold pressing the blend and sintering the pressed material.

Ebbinghaus, Bartley B. (Livermore, CA); Van Konynenburg, Richard A. (Livermore, CA); Vance, Eric R. (Kirrawee, AU); Stewart, Martin W. (Barden Ridge, AU); Walls, Philip A. (Cronulla, AU); Brummond, William Allen (Livermore, CA); Armantrout, Guy A. (Livermore, CA); Herman, Connie Cicero (Pleasanton, CA); Hobson, Beverly F. (Livermore, CA); Herman, David Thomas (Pleasanton, CA); Curtis, Paul G. (Tracy, CA); Farmer, Joseph (Tracy, CA)

2001-01-01T23:59:59.000Z

137

POTENTIAL BENCHMARKS FOR ACTINIDE PRODUCTION IN HANFORD REACTORS  

Science Conference Proceedings (OSTI)

A significant experimental program was conducted in the early Hanford reactors to understand the reactor production of actinides. These experiments were conducted with sufficient rigor, in some cases, to provide useful information that can be utilized today in development of benchmark experiments that may be used for the validation of present computer codes for the production of these actinides in low enriched uranium fuel.

PUIGH RJ; TOFFER H

2011-10-19T23:59:59.000Z

138

Actinide partitioning from actual Idaho chemical processing plant acidic tank waste using centrifugal contactors  

Science Conference Proceedings (OSTI)

The TRUEX process is being evaluated at the Idaho Chemical Processing Plant (ICPP) for the separation of the actinides from acidic radioactive wastes stored at the ICPP. These efforts have culminated in a recent demonstration of the TRUEX process with actual tank waste. This demonstration was performed using 24 stages of 2-cm diameter centrifugal contactors installed in a shielded hot cell at the ICPP Remote Analytical Laboratory. An overall removal efficiency of 99.97% was obtained for the actinides. As a result, the activity of the actinides was reduced from 457 nCi/g in the feed to 0.12 nCi/g in the aqueous raffinate, which is well below the U.S. NRC Class A LLW requirement of 10 nCi/g for non-TRU waste. Iron was partially extracted by the TRUEX solvent, resulting in 23% of the Fe exiting in the strip product. Mercury was also extracted by the TRUEX solvent (76%) and stripped from the solvent in the 0.25 M Na{sub 2}CO{sub 3} wash section.

Law, J.D.; Brewer, K.N.; Todd, T.A.

1997-10-01T23:59:59.000Z

139

Apparatus and method for reprocessing and separating spent nuclear fuels. [Patent application  

DOE Patents (OSTI)

A method and apparatus for separating and reprocessing spent nuclear fuels includes a separation vessel housing a molten metal solvent in a reaction region, a reflux region positioned above and adjacent to the reaction region, and a porous filter member defining the bottom of the separation vessel in a supporting relationship with the metal solvent. Spent fuels are added to the metal solvent. A nonoxidizing nitrogen-containing gas is introduced into the separation vessel, forming solid actinide nitrides in the metal solvent from actinide fuels, while leaving other fission products in solution. A pressure of about 1.1 to 1.2 atm is applied in the reflux region, forcing the molten metal solvent and soluble fission products out of the vessel, while leaving the solid actinide nitrides in the separation vessel.

Krikorian, O.H.; Grens, J.Z.; Parrish, W.H. Sr.; Coops, M.S.

1982-01-19T23:59:59.000Z

140

Microscopy for STEM Educators - SPIE Conference 2012  

Science Conference Proceedings (OSTI)

SPIE Conference 2012. SPIE Conference 2012. ... Microscopy for STEM Educators - SPIE Conference 2012. Sound interesting? ...

2012-05-09T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

4. International reservoir characterization technical conference  

Science Conference Proceedings (OSTI)

This volume contains the Proceedings of the Fourth International Reservoir Characterization Technical Conference held March 2-4, 1997 in Houston, Texas. The theme for the conference was Advances in Reservoir Characterization for Effective Reservoir Management. On March 2, 1997, the DOE Class Workshop kicked off with tutorials by Dr. Steve Begg (BP Exploration) and Dr. Ganesh Thakur (Chevron). Tutorial presentations are not included in these Proceedings but may be available from the authors. The conference consisted of the following topics: data acquisition; reservoir modeling; scaling reservoir properties; and managing uncertainty. Selected papers have been processed separately for inclusion in the Energy Science and Technology database.

NONE

1997-04-01T23:59:59.000Z

142

Why have we stopped research on liquid centrifugal separation  

SciTech Connect

Using high-temperature high-speed liquid centrifuges for lanthanides and actinides separation was originally proposed as a physical separation method in the Los Alamos ADTT/ATW concept [C. Bowman, LA-UR-92-1065 (1992)]. The authors investigated centrifugal separation in a concerted effort of experiments, theoretical analysis and numerical simulations. They discovered that owing to the ionic-composition-dependence of the sedimentation coefficients for the fission products and actinides, separation by grouping of molecular densities would not work in general in the molten salt environment. Alternatively the lanthanides and actinides could be transferred to a liquid metal carrier (e.g. bismuth) via reductive extraction and then separated by liquid centrifuges, but the material and technical challenges are severe. Meanwhile the authors have established that the reductive extraction procedure itself can be used for desired separations. Unlike conventional aqueous-based reprocessing technologies, reductive extraction separation uses only reagent (Li) that reconstitutes carrier salts (LiF-BeF{sub 2}) and a processing medium (Bi) that can be continuously recycled and reused, with a nearly-pure fission products waste stream. The processing units are compact and reliable, and can be built at relatively low cost while maintaining high throughput. Therefore the research effort on developing liquid centrifuges for separations in ADTT/ATW was terminated in late 1995. This paper will discuss the various aspects involved in reaching this decision.

Li, N.

1996-05-28T23:59:59.000Z

143

Proliferation Resistance Evaluation of ACR-1000 Fuel with Minor Actinides  

Science Conference Proceedings (OSTI)

The Global Nuclear Energy Partnership (GNEP) program is to significantly advance the science and technology of nuclear energy systems and to enhance the spent fuel proliferation resistance. It consists of both innovative nuclear reactors and innovative research in separation and transmutation. The merits of nuclear energy are high-density energy, with low environmental impacts (i.e. almost zero greenhouse gas emission). Planned efforts involve near-term and intermediate-term improvements in fuel utilization and recycling in current light water reactors (LWRs) as well as the longer-term development of new nuclear energy systems that offer much improved fuel utilization and proliferation resistance, along with continued advances in operational safety. For future advanced nuclear systems, minor actinides (MA) are viewed more as a resource to be recycled, and transmuted to less hazardous and possibly more useful forms, rather than simply disposed of as a waste stream in an expensive repository facility. MAs can play a much larger part in the design of advanced systems and fuel cycles, not only as additional sources of useful energy, but also as direct contributors to the reactivity control of the systems into which they are incorporated. In this work, an Advanced CANDU Reactor (ACR) fuel unit lattice cell model with 43 UO2 fuel rods will be used to investigate the effectiveness of a Minor Actinide Reduction Approach (MARA) for enhancing proliferation resistance and improving the fuel cycle performance. The main MARA objective is to increase the 238Pu / Pu isotope ratio by using the transuranic nuclides (237Np and 241Am) in the high burnup fuel and thereby increase the proliferation resistance even for a very low fuel burnup. As a result, MARA is a very effective approach to enhance the proliferation resistance for the on power refueling ACR system nuclear fuel. The MA transmutation characteristics at different MA loadings were compared and their impact on neutronics criticality assessed. The concept of MARA, significantly increases the 238Pu/Pu ratio for proliferation resistance, as well as serves as a burnable absorber to hold-down the initial excess reactivity. It is believed that MARA can play an important role in atoms for peace and the intermediate term of nuclear energy reconnaissance

Gray S. Chang

2008-09-01T23:59:59.000Z

144

Joint Actinide Shock Physics Experimental Research | National Nuclear  

National Nuclear Security Administration (NNSA)

Actinide Shock Physics Experimental Research | National Nuclear Actinide Shock Physics Experimental Research | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Jasper Joint Actinide Shock Physics Experimental Research Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Research and Development >

145

Winter Simulation Conference  

Science Conference Proceedings (OSTI)

Welcome to the 2009 Winter Simulation Conference (WSC), recognized as the premiere international conference for simulation professionals in discrete and combined discrete-continuous simulation. WSC is always located in exciting and dynamic locations ...

Ann Dunkin; Ricki G. Ingalls

2009-12-01T23:59:59.000Z

146

Fabrication and Pre-irradiation Characterization of a Minor Actinide and Rare Earth Containing Fast Reactor Fuel Experiment for Irradiation in the Advanced Test Reactor  

SciTech Connect

The United States Department of Energy, seeks to develop and demonstrate the technologies needed to transmute the long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter lived fission products, thereby decreasing the volume of material requiring disposal and reducing the long-term radiotoxicity and heat load of high-level waste sent to a geologic repository. This transmutation of the long lived actinides plutonium, neptunium, americium and curium can be accomplished by first separating them from spent Light Water Reactor fuel using a pyro-metalurgical process, then reprocessing them into new fuel with fresh uranium additions, and then transmuted to short lived nuclides in a liquid metal cooled fast reactor. An important component of the technology is developing actinide-bearing fuel forms containing plutonium, neptunium, americium and curium isotopes that meet the stringent requirements of reactor fuels and materials.

Timothy A. Hyde

2012-06-01T23:59:59.000Z

147

Separation of strontium from fecal matter  

DOE Patents (OSTI)

A method of separating strontium from a sample of biomass potentially contaminated with various radionuclides. After the sample is reduced, dissociated, and carried on a first precipitate of actinides, the first precipitate is removed to leave a supernate. Next, oxalic acid is added to the supernate to cause a second precipitate of strontium and calcium. Then, after separating the second precipitate, nitric acid is added to the second precipitate to cause a third precipitate of strontium. The calcium remains in solution and is discarded to leave essentially the precipitate of strontium.

Kester, Dianne K. (Idaho Falls, ID)

1995-01-01T23:59:59.000Z

148

Separation of strontium from fecal matter  

DOE Patents (OSTI)

A method is presented of separating strontium from a sample of biomass potentially contaminated with various radionuclides. After the sample is reduced, dissociated, and carried on a first precipitate of actinides, the first precipitate is removed to leave a supernate. Next, oxalic acid is added to the supernate to cause a second precipitate of strontium and calcium. Then, after separating the second precipitate, nitric acid is added to the second precipitate to cause a third precipitate of strontium. The calcium remains in solution and is discarded to leave essentially the precipitate of strontium.

Kester, D.K.

1995-01-03T23:59:59.000Z

149

Conference Proceedings Publication Proposal  

Science Conference Proceedings (OSTI)

AVAILABILITY. ? Concurrent with conference ? Non-concurrent (publication recommended within 3 months of meeting). Date papers are due to editors: ...

150

Security Automation Conference & Workshop  

Science Conference Proceedings (OSTI)

... Security Automation Conference & Workshop. ... Richard Hale, DISA - Information Security & Security Automation in DoD (coming soon); ...

151

Battery separators  

SciTech Connect

Novel, improved battery separators carrying a plurality of polymeric ribs on at least one separator surface. The battery separators are produced by extruding a plurality of ribs in the form of molten polymeric rib providing material onto the surface of a battery separator to bond the material to the separator surface and cooling the extruded rib material to a solidified state. The molten polymeric rib providing material of this invention includes a mixture or blend of polypropylenes and an ethylene propylene diene terpolymer.

Battersby, W. R.

1984-12-25T23:59:59.000Z

152

Registration - 21st NISS Conference  

Science Conference Proceedings (OSTI)

... Conference The registration fee covers conference materials, coffee breaks, and admission to the banquet and award ceremony. ...

1998-10-20T23:59:59.000Z

153

Minor actinide waste disposal in deep geological boreholes  

E-Print Network (OSTI)

The purpose of this investigation was to evaluate a waste canister design suitable for the disposal of vitrified minor actinide waste in deep geological boreholes using conventional oil/gas/geothermal drilling technology. ...

Sizer, Calvin Gregory

2006-01-01T23:59:59.000Z

154

ACTINIDE-SPECIFIC SEQUESTERING AGENTS AND DECONTAMINATION APPLICATIONS  

E-Print Network (OSTI)

In: The Health Eff, of Plutonium and Radium, Proc. Sym. ,The Metabolism of Compounds Plutonium and Other Actinides.In: The Radiobiology of Plutonium. Stover, B. J. , Jee, H.

Smith, William L.

2013-01-01T23:59:59.000Z

155

Supercritical Carbon Dioxide Ligands for Extracting Actinide Metal Ions from Porous Solids  

SciTech Connect

Numerous types of actinide-bearing waste materials are found throughout the DOE complex. Most of these wastes consist of large volumes of non-hazardous materials contaminated with relatively small quantities of actinide elements. Separation of these wastes into their inert and radioactive components would dramatically reduce the costs of stabilization and disposal. For example, the DOE is responsible for decontaminating concrete within 7000 surplus contaminated buildings. The best technology now available for removing surface contamination from concrete involves removing the surface layer by grit blasting, which produces a large volume of blasting residue containing a small amount of radioactive material. Disposal of this residue is expensive because of its large volume and fine particulate nature. Considerable cost savings would result from separation of the radioactive constituents and stabilization of the concrete dust. Similarly, gas diffusion plants for uranium enrichment contain valuable high-purity nickel in the form of diffusion barriers. Decontamination is complicated by the extremely fine pores in these barriers, which are not readily accessible by most cleaning techniques. A cost-effective method for the removal of radioactive contaminants would release this valuable material for salvage.

Albert W. Herlinger; Dr. Mark L. Dietz

2003-03-06T23:59:59.000Z

156

Supercritical Carbon Dioxide-Soluble Ligands for Extracting Actinide Metal Ions from Porous Solids  

SciTech Connect

Numerous types of actinide-bearing waste materials are found throughout the DOE complex. Most of these wastes consist of large volumes of non-hazardous materials contaminated with relatively small quantities of actinide elements. Separation of these wastes into their inert and radioactive components would dramatically reduce the costs of stabilization and disposal. For example, the DOE is responsible for decontaminating concrete within 7000 surplus contaminated buildings. The best technology now available for removing surface contamination from concrete involves removing the surface layer by grit blasting, which produces a large volume of blasting residue containing a small amount of radioactive material. Disposal of this residue is expensive because of its large volume and fine particulate nature. Considerable cost savings would result from separation of the radioactive constituents and stabilization of the concrete dust. Similarly, gas diffusion plants for uranium enrichment contain valuable high-purity nickel in the form of diffusion barriers. Decontamination is complicated by the extremely fine pores in these barriers, which are not readily accessible by most cleaning techniques. A cost-effect method for the removal of radioactive contaminants would release this valuable material for salvage.

Joan Brennecke; Mark Dietz; Richard Barrans; Alabert Herlinger

2003-07-03T23:59:59.000Z

157

NETL: First National Conference on Carbon Sequestration  

NLE Websites -- All DOE Office Websites (Extended Search)

First National Conference on Carbon Sequestration First National Conference on Carbon Sequestration Table of Contents Disclaimer Papers and Presentations Plenary Session Industry Focus Panel Discussion Session 1A. Geologic Sequestration I - Overview Session 1B. Capture & Separation I - Industrial Efforts Session 1C. Modeling I - Case Studies & Deployment Session 2A. Geologic Sequestration II - EOR/EGR Session 2B. Capture & Separation II - Improved Processes Session 2C. Modeling II - Economics Poster Presentations International Panel Discussion Session 3A. Geologic Sequestration III - Enhanced Coalbed Methane Session 3B. Capture & Separation III - Adsorption Studies Session 3C. Terrestrial Sequestration I - Ecosystem Behavior Session 4A. Geologic Sequestration IV - Saline Aquifers Session 4B. Capture & Separation IV - Power Systems Concepts

158

IEEE Power Engineering Society. Papers from the joint power generation conference  

SciTech Connect

Twenty-nine papers were presented at the conference. A separate abstract was prepared for 22 papers. Seven papers have been previously entered in the data base. (LCL)

1977-01-01T23:59:59.000Z

159

Fourth technical contractors' conference on peat  

SciTech Connect

This conference reported the status of the US Department of Energy Peat Program. The papers presented dealt with peat dewatering, international peat programs, environmental and socio-economic factors, peat gasification, peat harvesting, and the state peat surveys for 14 states. Separate abstracts were prepared for the individual papers. (CKK)

Not Available

1981-01-01T23:59:59.000Z

160

1985 mining industry technical conference (Conference record)  

SciTech Connect

This book presents the papers given at a conference on underground coal mining technology. Topics considered at the conference included trends in the electronic control of mine hoists, a probabilistic model of power demand for sequential conveyor systems, a slurry monitor for the precision determination of the density of slurries flowing in pipelines, and an intrinsically safe communication, signalling and control system used in underground working sections of coal mines.

Not Available

1985-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Battery separators  

Science Conference Proceedings (OSTI)

A novel, improved battery separator and process for making the separator. Essentially, the separator carries a plurality of polymeric ribs bonded to at least one surface and the ribs have alternating elevated segments of uniform maxiumum heights and depressed segments along the length of the ribs.

Le Bayon, R.; Faucon, R.; Legrix, J.

1984-11-13T23:59:59.000Z

162

A Heterogeneous Sodium Fast Reactor Designed to Transmute Minor Actinide Actinide Waste Isotopes into Plutonium Fuel  

Science Conference Proceedings (OSTI)

An axial heterogeneous sodium fast reactor design is developed for converting minor actinide waste isotopes into plutonium fuel. The reactor design incorporates zirconium hydride moderating rods in an axial blanket above the active core. The blanket design traps the active core’s axial leakage for the purpose of transmuting Am-241 into Pu-238. This Pu-238 is then co-recycled with the spent driver fuel to make new driver fuel. Because Pu-238 is significantly more fissile than Am-241 in a fast neutron spectrum, the fissile worth of the initial minor actinide material is upgraded by its preconditioning via transmutation in the axial targets. Because, the Am-241 neutron capture worth is significantly stronger in a moderated epithermal spectrum than the fast spectrum, the axial targets serve as a neutron trap which recovers the axial leakage lost by the active core. The sodium fast reactor proposed by this work is designed as an overall transuranic burner. Therefore, a low transuranic conversion ratio is achieved by a degree of core flattening which increases axial leakage. Unlike a traditional “pancake” design, neutron leakage is recovered by the axial target/blanket system. This heterogeneous core design is constrained to have sodium void and Doppler reactivity worth similar to that of an equivalent homogeneous design. Because minor actinides are irradiated only once in the axial target region; elemental partitioning is not required. This fact enables the use of metal targets with electrochemical reprocessing. Therefore, the irradiation environment of both drivers and targets was constrained to ensure applicability of the established experience database for metal alloy sodium fast reactor fuels.

Samuel E. Bays

2011-02-01T23:59:59.000Z

163

Actinide Production in the Reaction of Heavy Ions withCurium-248  

Science Conference Proceedings (OSTI)

Chemical experiments were performed to examine the usefulness of heavy ion transfer reactions in producing new, neutron-rich actinide nuclides. A general quasi-elastic to deep-inelastic mechanism is proposed, and the utility of this method as opposed to other methods (e.g. complete fusion) is discussed. The relative merits of various techniques of actinide target synthesis are discussed. A description is given of a target system designed to remove the large amounts of heat generated by the passage of a heavy ion beam through matter, thereby maximizing the beam intensity which can be safely used in an experiment. Also described is a general separation scheme for the actinide elements from protactinium (Z = 91) to mendelevium (Z = 101), and fast specific procedures for plutonium, americium and berkelium. The cross sections for the production of several nuclides from the bombardment of {sup 248}Cm with {sup 18}O, {sup 86}Kr and {sup 136}Xe projectiles at several energies near and below the Coulomb barrier were determined. The results are compared with yields from {sup 48}Ca and {sup 238}U bombardments of {sup 248}Cm. Simple extrapolation of the product yields into unknown regions of charge and mass indicates that the use of heavy ion transfer reactions to produce new, neutron-rich above-target species is limited. The substantial production of neutron-rich below-target species, however, indicates that with very heavy ions like {sup 136}Xe and {sup 238}U the new species {sup 248}Am, {sup 249}Am and {sup 247}Pu should be produced with large cross sections from a {sup 248}Cm target. A preliminary, unsuccessful attempt to isolate {sup 247}Pu is outlined. The failure is probably due to the half life of the decay, which is calculated to be less than 3 minutes. The absolute gamma ray intensities from {sup 251}Bk decay, necessary for calculating the {sup 251}Bk cross section, are also determined.

Moody, K.J.

1983-07-01T23:59:59.000Z

164

11th International Conference on Nanotechnology - IEEE ...  

Science Conference Proceedings (OSTI)

11th International Conference on Nanotechnology - IEEE Nano 2011 Conference. ... IEEE Nano 2011 Conference - August 15-20, 2011. Purpose: ...

2011-07-20T23:59:59.000Z

165

NETL: 2002 Conference Proceedings  

NLE Websites -- All DOE Office Websites (Extended Search)

16th Annual Conference on Fossil Energy Materials April 22-24, 2002 Table of Contents Disclaimer Papers and Presentations Session I Functional Materials Session II Coatings...

166

Science Conference Proceedings  

Office of Scientific and Technical Information (OSTI)

energy, aeronautics and astronautics, meteorology, engineering, computer science, electric power, and fossil fuels The OSTI Science Conference Proceedings portal was devised to...

167

2010 Energy Conference Highlights  

U.S. Energy Information Administration (EIA)

Home > About EIA > EIA 2010 Energy Conference Highlights : ... Continuing Shifts in the Industry and Long-Term ... Technology and Energy Transformation — Donald L ...

168

About this Conference  

Science Conference Proceedings (OSTI)

Conference Tools for Liquid Metal Processing and Casting 2013 ... Slag and Refractory Reactions with Liquid Metals - Refining, Evaporation and Gas/Metal ...

169

Superalloys Conference Proceedings Archive  

Science Conference Proceedings (OSTI)

Search more than 1,000 technical articles from the history of the Superalloys Conference Proceedings. ... A New Ni-Base Superalloy for Oil and Gas Applications ...

170

EIA - Energy Conferences & Presentations.  

U.S. Energy Information Administration (EIA) Indexed Site

EIA Conference 2009 Plenary Session Welcome - Howard Gruenspecht Acting Administrator, Energy Information Administration Keynote Address; The Energy Problem - Dr. Steven Chu,...

171

About this Conference  

Science Conference Proceedings (OSTI)

Understanding today's materials problems is also critical for the future in advanced light water reactor and fusion reactors. The purpose of this conference is to ...

172

Find Conference Proceedings  

NLE Websites -- All DOE Office Websites (Extended Search)

Here is one strategy: Click on "Advanced Search" tab Choose "Words in all fields" field Enter keywords from the conference title and location Plutonium and Albuquerque will find...

173

APS 2006 Conferences  

NLE Websites -- All DOE Office Websites (Extended Search)

Conference on Synchrotron Radiation Instrumentation (May 28 - June 3) Daegu, Exco, Korea EPICS Collaboration Meeting (June 12-16) Argonne National Laboratory Argonne, IL Tenth...

174

Selective partitioning of mercury from co-extracted actinides in a simulated acidic ICPP waste stream  

SciTech Connect

The TRUEX process is being evaluated at the Idaho Chemical Processing Plant (ICPP) as a means to partition the actinides from acidic sodium-bearing waste (SBW). The mercury content of this waste averages 1 g/l. Because the chemistry of mercury has not been extensively evaluated in the TRUEX process, mercury was singled out as an element of interest. Radioactive mercury, {sup 203}Hg, was spiked into a simulated solution of SBW containing 1 g/l mercury. Successive extraction batch contacts with the mercury spiked waste simulant and successive scrubbing and stripping batch contacts of the mercury loaded TRUEX solvent (0.2 M CMPO-1.4 M TBP in dodecane) show that mercury will extract into and strip from the solvent. The extraction distribution coefficient for mercury, as HgCl{sub 2} from SBW having a nitric acid concentration of 1.4 M and a chloride concentration of 0.035 M was found to be 3. The stripping distribution coefficient was found to be 0.5 with 5 M HNO{sub 3} and 0.077 with 0.25 M Na{sub 2}CO{sub 3}. An experimental flowsheet was designed from the batch contact tests and tested counter-currently using 5.5 cm centrifugal contactors. Results from the counter-current test show that mercury can be removed from the acidic mixed SBW simulant and recovered separately from the actinides.

Brewer, K.N.; Herbst, R.S.; Tranter, T.J. [and others

1995-12-01T23:59:59.000Z

175

Method for the recovery of actinide elements from nuclear reactor waste  

DOE Green Energy (OSTI)

A process for partitioning and recovering actinide values from acidic waste solutions resulting from reprocessing of irradiated nuclear fuels by adding hydroxylammonium nitrate and hydrazine to the waste solution to adjust the valence of the neptunium and plutonium values in the solution to the +4 oxidation state, thus forming a feed solution and contacting the feed solution with an extractant of dihexoxyethyl phosphoric acid in an organic diluent whereby the actinide values, most of the rare earth values and some fission product values are taken up by the extractant. Separation is achieved by contacting the loaded extractant with two aqueous strip solutions, a nitric acid solution to selectively strip the americium, curium and rare earth values and an oxalate solution of tetramethylammonium hydrogen oxalate and oxalic acid or trimethylammonium hydrogen oxalate to selectively strip the neptunium, plutonium and fission product values. Uranium values remain in the extractant and may be recovered with a phosphoric acid strip. The neptunium and plutonium values are recovered from the oxalate by adding sufficient nitric acid to destroy the complexing ability of the oxalate, forming a second feed, and contacting the second feed with a second extractant of tricaprylmethylammonium nitrate in an inert diluent whereby the neptunium and plutonium values are selectively extracted. The values are recovered from the extractant with formic acid.

Horwitz, E. Philip (Elmhurst, IL); Delphin, Walter H. (Woodridge, IL); Mason, George W. (Clarendon Hills, IL)

1979-01-01T23:59:59.000Z

176

Double liquid membrane system for the removal of actinides and lanthanides from acidic nuclear wastes  

SciTech Connect

Supported liquid membranes (SLM), consisting of an organic solution of n-octyl-(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) and tributyl-phosphate (TBP) in decalin are able to perform selective separation and concentration of actinide and lanthanide ions from aqueous nitrate feed solutions and synthetic nuclear wastes. In the membrane process a possible strip solution is a mixture of formic acid and hydroxylammonium formate (HAF). The effectiveness of this strip solution is reduced and eventually nullified by the simultaneous transfer through the SLM of nitric acid which accumulates in the strip solution. A possible way to overcome this drawback is to make use of a second SLM consisting of a primary amine which is able to extract only HNO/sub 3/ from the strip solution. In this work the results obtained by experimentally studying the membrane system: synthetic nuclear waste/CMPO-TBP membrane/HCOOH-HAF strip solution/primary amine membrane/NaOH solution, are reported. They show that the use of a second liquid membrane is effective in controlling the HNO/sub 3/ concentration in the strip solution, thus allowing the actinide and lanthanide ions removal from the feed solution to proceed to completion. 15 refs., 10 figs., 1 tab.

Chiarizia, R.; Danesi, P.R.

1985-01-01T23:59:59.000Z

177

Enhancing BWR Proliferation Resistance Fuel with Minor Actinides  

Science Conference Proceedings (OSTI)

Key aspects of the Global Nuclear Energy Partnership (GNEP) are to significantly advance the science and technology of nuclear energy systems and the Advanced Fuel Cycle (AFC) program. It consists of both innovative nuclear reactors and innovative research in separation and transmutation. To accomplish these goals, international cooperation is very important and public acceptance is crucial. The merits of nuclear energy are high-density energy, with low environmental impacts (i.e. almost zero greenhouse gas emission). Planned efforts involve near-term and intermediate-term improvements in fuel utilization and recycling in current light water reactors (LWRs) as well as the longer-term development of new nuclear energy systems that offer much improved fuel utilization and proliferation resistance, along with continued advances in operational safety. The challenges are solving the energy needs of the world, protection against nuclear proliferation, the problem of nuclear waste, and the global environmental problem. To reduce spent fuel for storage and enhance the proliferation resistance for the intermediate-term, there are two major approaches (a) increase the discharged spent fuel burnup in the advanced LWR (Gen-III Plus), which not only can reduce the spent fuel for storage, but also increase the 238Pu and 240Pu isotopes ratio to enhance the proliferation resistance, and (b) use of transuranic nuclides (237Np and 241Am) in the high burnup fuel, which can drastically increase the proliferation resistance isotope ratio of 238Pu /Pu. For future advanced nuclear systems, the minor actinides (MA) are viewed more as a resource to be recycled, or transmuted to less hazardous and possibly more useful forms, rather than simply as a waste stream to be disposed of in expensive repository facilities. As a result, MAs play a much larger part in the design of advanced systems and fuel cycles, not only as additional sources of useful energy, but also as direct contributors to the reactivity control of the systems into which they are incorporated. In the study, a typical boiling water reactor (BWR) fuel unit lattice cell model with UO2 fuel pins will be used to investigate the effectiveness of minor actinide reduction approach (MARA) for enhancing proliferation resistance and improving the fuel cycle performance in the intermediate term goal for future nuclear energy systems. To account for the water coolant density variation from the bottom (0.76 g/cm3) to the top (0.35 g/cm3) of the core, the axial coolant channel and fuel pin were divided to 24 nodes. The MA transmutation characteristics at different elevations were compared and their impact on neutronics criticality discussed. We concluded that the concept of MARA, which involves the use of transuranic nuclides (237Np and/or 241Am), significantly increases the 238Pu/Pu ratio for proliferation resistance, as well as serves as a burnable absorber to hold-down the initial excess reactivity. It is believed that MARA can play an important role in atoms for peace and the intermediate term of nuclear energy rennaissance.

Gray S. Chang

2008-07-01T23:59:59.000Z

178

2005 World Oleochemical Conference  

Science Conference Proceedings (OSTI)

This CD-ROM is a compilation of the PowerPoint presentations given at the 2005 World Oleochemical Conference, Meeting Demands of the Future, held 10-13 April 2005, Athens, Greece. 2005 World Oleochemical Conference DVD & CD-ROMs Food Science & Technology

179

2011 AAOCS Conference Program  

Science Conference Proceedings (OSTI)

2011 AAOCS biennial conference programme Wednesday, November 9th Hot topic symposium – Current issues in olive oil quality chaired by Rod Mailer and Laurence Eyres 12:00-1:00 Conference registration 1:00-1:30 Why We Need a New Oli

180

Environmental Assessment for Actinide Chemistry and Repository Science  

NLE Websites -- All DOE Office Websites (Extended Search)

questions on the Environmental Assessment for Actinide Chemistry and Repository Science Laboratory, email Harold.Johnson@wipp.ws or call (505) 234-7349. questions on the Environmental Assessment for Actinide Chemistry and Repository Science Laboratory, email Harold.Johnson@wipp.ws or call (505) 234-7349. Environmental Assessment for Actinide Chemistry and Repository Science Laboratory Final - January, 2006 This document has been provided to you in PDF format. Please install Adobe Acrobat Reader before accessing these documents. Some of the Chapters containing complex graphics have been split into multiple parts to allow for more detail in the graphics and ease in downloading. Cover Sheet, Table of Contents, List of Tables, List of Figures, and Acronyms and Abbreviations Chapter 1 - Introduction and Statement of Purpose and Need Chapter 2 - Proposed Action and Alternatives Chapter 3 - Existing Environment

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While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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181

FY2010 Annual Report for the Actinide Isomer Detection Project  

Science Conference Proceedings (OSTI)

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 Special Nuclear Materials (SNM). Future work will include a follow-up measurement scheduled for December 2010 at LBNL. Lessons learned from the July 2010 measurements will be incorporated into these new measurements. Analysis of both the July and December experiments will be completed in a few months. A research paper to be submitted to a peer-reviewed journal will be drafted if the conclusions from the measurements warrant publication.

Warren, Glen A.; Francy, Christopher J.; Ressler, Jennifer J.; Erikson, Luke E.; Miller, Erin A.; Hatarik, R.

2011-01-01T23:59:59.000Z

182

Actinide (III) solubility in WIPP Brine: data summary and recommendations  

Science Conference Proceedings (OSTI)

The solubility of actinides in the +3 oxidation state is an important input into the Waste Isolation Pilot Plant (WIPP) performance assessment (PA) models that calculate potential actinide release from the WIPP repository. In this context, the solubility of neodymium(III) was determined as a function of pH, carbonate concentration, and WIPP brine composition. Additionally, we conducted a literature review on the solubility of +3 actinides under WIPP-related conditions. Neodymium(III) was used as a redox-invariant analog for the +3 oxidation state of americium and plutonium, which is the oxidation state that accounts for over 90% of the potential release from the WIPP through the dissolved brine release (DBR) mechanism, based on current WIPP performance assessment assumptions. These solubility data extend past studies to brine compositions that are more WIPP-relevant and cover a broader range of experimental conditions than past studies.

Borkowski, Marian; Lucchini, Jean-Francois; Richmann, Michael K.; Reed, Donald T.

2009-09-01T23:59:59.000Z

183

Actinide consumption: Nuclear resource conservation without breeding  

SciTech Connect

A new approach to the nuclear power issue based on a metallic fast reactor fuel and pyrometallurgical processing of spent fuel is showing great potential and is approaching a critical demonstration phase. If successful, this approach will complement and validate the LWR reactor systems and the attendant infrastructure (including repository development) and will alleviate the dominant concerns over the acceptability of nuclear power. The Integral Fast Reactor (IFR) concept is a metal-fueled, sodium-cooled pool-type fast reactor supported by a pyrometallurgical reprocessing system. The concept of a sodium cooled fast reactor is broadly demonstrated by the EBR-II and FFTF in the US; DFR and PFR in the UK; Phenix and SuperPhenix in France; BOR-60, BN-350, BN-600 in the USSR; and JOYO in Japan. The metallic fuel is an evolution from early EBR-II fuels. This fuel, a ternary U-Pu-Zr alloy, has been demonstrated to be highly reliable and fault tolerant even at very high burnup (160-180,000 MWd/MT). The fuel, coupled with the pool type reactor configuration, has been shown to have outstanding safety characteristics: even with all active safety systems disabled, such a reactor can survive a loss of coolant flow, a loss of heat sink, or other major accidents. Design studies based on a small modular approach show not only its impressive safety characteristics, but are projected to be economically competitive. The program to explore the feasibility of actinide recovery from spent LWR fuel is in its initial phase, but it is expected that technical feasibility could be demonstrated by about 1995; DOE has not yet committed funds to achieve this objective. 27 refs.

Hannum, W.H.; Battles, J.E.; Johnson, T.R.; McPheeters, C.C.

1991-01-01T23:59:59.000Z

184

Fission theory and actinide fission data  

SciTech Connect

The understanding of the fission process has made great progress recently, as a result of the calculation of fission barriers, using the Strutinsky prescription. Double-humped shapes were obtained for nuclei in the actinide region. Such shapes could explain, in a coherent manner, many different phenomena: fission isomers, structure in near-threshold fission cross sections, intermediate structure in subthreshold fission cross sections and anisotropy in the emission of the fission fragments. A brief review of fission barrier calculations and relevant experimental data is presented. Calculations of fission cross sections, using double-humped barrier shapes and fission channel properties, as obtained from the data discussed previously, are given for some U and Pu isotopes. The fission channel theory of A. Bohr has greatly influenced the study of low-energy fission. However, recent investigation of the yields of prompt neutrons and ..gamma.. rays emitted in the resonances of /sup 235/U and /sup 239/Pu, together with the spin determination for many resonances of these two nuclei cannot be explained purely in terms of the Bohr theory. Variation in the prompt neutron and ..gamma..-ray yields from resonance to resonance does not seem to be due to such fission channels, as was thought previously, but to the effect of the (n, ..gamma.., f) reaction. The number of prompt fission neutrons and the kinetic energy of the fission fragments are affected by the energy balance and damping or viscosity effects in the last stage of the fission process, from saddle point to scission. These effects are discussed for some nuclei, especially for /sup 240/Pu. 17 figures, 56 ref. (auth)

Michaudon, A.

1975-10-01T23:59:59.000Z

185

Science Conference Proceedings : About  

Office of Scientific and Technical Information (OSTI)

About Science Conference Proceedings About Science Conference Proceedings The OSTI Science Conference Proceedings portal was devised to expedite access to conference papers and proceedings in various fields of science and technology. Emphasis is on U.S. conferences hosted and/or published by scientific and professional organizations whose areas of focus relate substantially to the Department of Energy's mission. Some information accessible through this site may have limitations on its use (including copyright) or contain terms and conditions. For information about these limitations, terms and conditions, refer to the specific organization. Documents from some sites may be available for purchase through an on-line shopping cart. The DOE's Office of Scientific and Technical Information (OSTI) provides

186

SRMS-5 Conference Contributions  

NLE Websites -- All DOE Office Websites (Extended Search)

SRMS 5 logo SRMS 5 logo Fifth International Conference on Synchrotron Radiation in Materials Science SRMS-5 Conference Contributions Table of Contents and Program Introduction Welcome to the 5th International Conference on Synchrotron Radiation in Materials Science (SRMS-5). This conference, the latest in a series of international conferences that are held every two years, takes place at the Drake Hotel in Chicago from July 30 - August 2, 2006. It brings together leading edge researchers from around the world and is a celebration of the strong and increasingly important relationship between materials science and synchrotron radiation research. SRMS-5 takes place at a time when a large proportion of the scientific research at synchrotron user facilities is in materials science and

187

NETL Publications: Conference Proceedings  

NLE Websites -- All DOE Office Websites (Extended Search)

Conference Proceedings Conference Proceedings Publications Conference Proceedings 2013 Aug 20-22 Carbon Storage R&D Project Review Meeting Aug 6-7 2013 NETL Workshop on Multiphase Flow Science July 23 14th Annual SECA Workshop July 8-11 NETL CO2 Capture Technology Meeting June 11-13 University Coal Research/Historically Black Colleges and Universities and other Minority Institutions Contractors Review Meeting 2012 Oct 2-4 2012 University Turbine Systems Research Workshop Aug 21-23 Carbon Storage R&D Project Review Meeting July 24-27 13th Annual SECA Workshop July 9-12 2012 NETL CO2 Capture Technology Meeting May 30-31 2012 University Coal Research/ Historically Black Colleges and Universities and Other Minority Institutions Contractors Review Conference April 17-19 The 26th Annual Conference on Fossil Energy Materials

188

Selection of actinide chemical analogues for WIPP tests  

Science Conference Proceedings (OSTI)

The Department of Energy must demonstrate the effectiveness of the Waste Isolation Pilot Plant (WIPP) as a permanent repository for the disposal of transuranic (TRU) waste. Performance assessments of the WIPP require that estimates of the transportability and outcome of the radionuclides (actinides) be determined from disposal rooms that may become either partially or completely filled with brine. Federal regulations limit the amount of radioactivity that may be unintentionally released to the accessible environment by any mechanism during the post closure phase up to 10,000 years. Thermodynamic models have been developed to predict the concentrations of actinides in the WIPP disposal rooms under various situations and chemical conditions. These models are based on empirical and theoretical projections of the chemistry that might be present in and around the disposal room zone for both near and long-term periods. The actinides that are known to be present in the TRU wastes (and are included in the model) are Th, U, Np, Pu, and Am. Knowledge of the chemistry that might occur in the disposal rooms when the waste comes in contact with brine is important in understanding the range of oxidation states that might be present under different conditions. There is a need to establish the mechanisms and resultant rate of transport, migration, or effective retardation of actinides beyond the disposal rooms to the boundary of the accessible environment. The influence of the bulk salt rock, clay sediments and other geologic matrices on the transport behavior of actinides must be determined to establish the overall performance and capability of the WIPP in isolating waste from the environment. Tests to determine the capabilities of the WIPP geologic formations in retarding actinide species in several projected oxidation states would provide a means to demonstrate the effectiveness of the WIPP in retaining TRU wastes.

Villarreal, R.; Spall, D.

1995-07-05T23:59:59.000Z

189

Separations Technology for Clean Water and Energy  

Science Conference Proceedings (OSTI)

Providing clean water and energy for about nine billion people on the earth by midcentury is a daunting challenge. Major investments in efficiency of energy and water use and deployment of all economical energy sources will be needed. Separations technology has an important role to play in producing both clean energy and water. Some examples are carbon dioxide capture and sequestration from fossil energy power plants and advanced nuclear fuel cycle scemes. Membrane separations systems are under development to improve the economics of carbon capture that would be required at a huge scale. For nuclear fuel cycles, only the PUREX liquid-liquid extraction process has been deployed on a large scale to recover uranium and plutonium from used fuel. Most current R and D on separations technology for used nuclear fuel focuses on ehhancements to a PUREX-type plant to recover the minor actinides (neptunium, americiu, and curium) and more efficiently disposition the fission products. Are there more efficient routes to recycle the actinides on the horizon? Some new approaches and barriers to development will be briefly reviewed.

Jarvinen, Gordon D [Los Alamos National Laboratory

2012-06-22T23:59:59.000Z

190

Physics studies of higher actinide consumption in an LMR  

Science Conference Proceedings (OSTI)

The core physics aspects of the transuranic burning potential of the Integral Fast Reactor (IFR) are assessed. The actinide behavior in fissile self-sufficient IFR closed cycles of 1200 MWt size is characterized, and the transuranic isotopics and risk potential of the working inventory are compared to those from a once-through LWR. The core neutronic performance effects of rare-earth impurities present in the recycled fuel are addressed. Fuel cycle strategies for burning transuranics from an external source are discussed, and specialized actinide burner designs are described. 4 refs., 4 figs., 3 tabs.

Hill, R.N.; Wade, D.C.; Fujita, E.K.; Khalil, H.S.

1990-01-01T23:59:59.000Z

191

Proceedings: 1989 Fossil Power Plant construction conference  

SciTech Connect

EPRI's First International Conference on Fossil Plant Construction was held in Cincinnati, Ohio on August 29--31, 1989. The Conference was attended by approximately 140 people representing 35 utilities, many US architect engineering companies, equipment suppliers and independent power producers. The conference covered world wide developments in fossil plant construction. Included in these proceedings are papers from the following sessions: The Challenge of Demands for New Capacity and Construction; Recent Plant Construction Experience; Construction Experience for New Technologies; Cogeneration Project Experience; Regulatory Requirements for Fossil Plant Construction; Planning, Development and Design; Modular Construction Techniques; Applications of Advanced Computer Technologies; International and Domestic Construction Advances; Management Challenges of Fossil Projects; and Retrofit and Repowering Construction Experience. Individual projects are processed separately for the data bases.

Armor, A.F.; Divakaruni, S.M. (eds.)

1991-07-01T23:59:59.000Z

192

Char separator  

DOE Patents (OSTI)

Particulates removed from the flue gases produced in a fluidized-bed furnace are separated into high-and low-density portions. The low-density portion is predominantly char, and it is returned to the furnace or burned in a separate carbon burnup cell. The high-density portion, which is predominantly limestone products and ash, is discarded or reprocessed. According to another version, the material drained from the bed is separated, the resulting high-and low-density portions being treated in a manner similar to that in which the flue-gas particulates are treated.

Matthews, Francis T. (Poquonock, CT)

1979-01-01T23:59:59.000Z

193

CENTRIFUGAL SEPARATORS  

DOE Patents (OSTI)

A centrifugal separator is described for separating gaseous mixtures where the temperature gradients both longitudinally and radially of the centrifuge may be controlled effectively to produce a maximum separation of the process gases flowing through. Tbe invention provides for the balancing of increases and decreases in temperature in various zones of the centrifuge chamber as the result of compression and expansions respectively, of process gases and may be employed effectively both to neutralize harmful temperature gradients and to utilize beneficial temperaturc gradients within the centrifuge.

Skarstrom, C.

1959-03-10T23:59:59.000Z

194

About the 2004 Electronic Materials Conference: Exhibition ...  

Science Conference Proceedings (OSTI)

2004 Electronic Materials Conference: Exhibition & Exhibitor Information ... REGISTRATION & HOUSING INFORMATION · PERSONAL CONFERENCE ...

195

Dynamical approach to heavy-ion induced fusion using actinide target  

Science Conference Proceedings (OSTI)

To treat heavy-ion reactions using actinide target nucleus, we propose a model which takes into account the coupling to the collective states of interacting nuclei in the penetration of the Coulomb barrier and the dynamical evolution of nuclear shape from the contact configuration. A fluctuation-dissipation model (Langevin equation) was applied in the dynamical calculation, where effect of nuclear orientation at the initial impact on the prolately deformed target nucleus was considered. Using this model, we analyzed the experimental data for the mass distribution of fission fragments (MDFF) in the reaction of {sup 36}S+{sup 238}U at several incident energies. Fusion-fission, quasifission and deep-quasi-fission are separated as different trajectories on the potential energy surface. We estimated the fusion cross section of the reaction.

Aritomo, Y.; Hagino, K.; Chiba, S.; Nishio, K. [Flerov Laboratory of Nuclear Reactions, JINR, Dubna, 141980 (Russian Federation); Department of Physics, Tohoku University, Sendai 980-8578 (Japan); Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, Tokyo 152-8550 (Japan); Japan Atomic Energy Agency, Tokai, Ibaraki, 319-1195 (Japan)

2012-10-20T23:59:59.000Z

196

A systematic study of actinide production from the interactions of heavy ions with sup 248 Cm  

Science Conference Proceedings (OSTI)

Production cross sections for heavy actinides produced from the interactions of {sup 12}C, {sup 31}P, {sup 40}Ar, and {sup 44}Ca ions with {sup 248}Cm were measured at energies ranging from 0.98 to 1.35 X Coulomb barrier. The recoiling reaction products were collected in copper or gold catcher foils located near the {sup 248}Cm target. Separate fractions of Bk, Cf, Es, Fm, and Md were obtained from a radiochemical separation procedure. For the {sup 12}C system, a He/KCl jet was used to transport the recoiling No activities of interest to a rotating wheel system. The isotopic distributions of the actinide products were found to be essentially symmetric about the maximum with full-widths-at-half-maximum of approximately 2.5 mass units. Isotopic distributions of the {sup 12}C, {sup 31}P, {sup 40}Ar, and {sup 44}Ca systems were found to be very similar to the {sup 40,48}Ca systems studied previously. The maxima of the isotopic distributions generally occurred for those reaction channels which involved the exchange of the fewest number of nucleons between the target and projectile for which the calculated excitation energy was a positive quantity. Additionally, the maxima of the excitation functions occurred at those projectile energies which were consistent with the calculated reaction barriers based upon a binary reaction mechanism. The experimental data from the four systems investigated were compared to several models of heavy ion interactions including a damped reaction mechanism, compound nucleus formation and subsequent particle evaporation, and classical partial wave calculations for binary systems.

Leyba, J.D.

1990-09-07T23:59:59.000Z

197

2011 IAEA General Conference  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2011 IAEA General Conference 2011 IAEA General Conference Remarks as Prepared for Delivery Secretary Steven Chu Monday, September 19, 2011 Thank you, Ambassador Feruta. Congratulations on your election as President of this Conference. I also want to thank Director General Amano for his outstanding leadership. I am honored to represent the United States today, and I want to share a message from President Barack Obama: "On behalf of the United States, please accept my best wishes for a successful International Atomic Energy Agency General Conference. This year's meeting takes place against the backdrop of the severe earthquake and tsunami that struck Japan in March and the devastating accident at the Fukushima Daiichi Nuclear Power Station that followed. Along with

198

Alaska Rural Energy Conference  

Energy.gov (U.S. Department of Energy (DOE))

Organized and sponsored by the Alaska Energy Authority and the Alaska Center for Energy and Power, the Alaska Rural Energy Conference is a three-day event featuring a wide array of technical...

199

RES California Conference  

Energy.gov (U.S. Department of Energy (DOE))

The NCAIED’s RES California conference and tradeshow will feature respected tribal leaders, state and local elected officials, top CEOs, the NCAIED’s “Twenty Grand Business Plan Competition”,...

200

Indian Housing Training Conference  

Energy.gov (U.S. Department of Energy (DOE))

This four-day conference will provide housing professionals with the tools to maintain good homes, build affordable homes, improve public safety, and provide essential building blocks to a healthy...

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

APS 2002 Conferences  

NLE Websites -- All DOE Office Websites (Extended Search)

section tracks conferences and workshops of interest to the APS researcher community. Photonics West. (Jan. 19-25) San Jose, CA APS March Meeting 2002. (Mar. 18-22) Indianapolis,...

202

APS Conference Center  

NLE Websites -- All DOE Office Websites (Extended Search)

of the Argonne Guest House, a full-service, professionally-managed hotel and restaurant. For Conference Center information or reservations, call (630) 252-4913 or send an...

203

Metabolic Engineering VII Conference  

DOE Green Energy (OSTI)

This 2008 meeting will celebrate our conference tradition of high quality and relevance to both industrial and academic participants, with topics ranging from the frontiers of fundamental science to the practical aspects of metabolic engineering.

Kevin Korpics

2012-12-04T23:59:59.000Z

204

APS 2004 Conferences  

NLE Websites -- All DOE Office Websites (Extended Search)

NY The Third Asian Particle Accelerator Conference (APAC2004). (Mar. 22-26) Gyeongju, Korea 11th Beam Instrumentation Workshop (BIW04). (May 3-6) Knoxville, TN 2004 Users Meeting...

205

Condenser Technology Conference Proceedings  

Science Conference Proceedings (OSTI)

This report documents the proceedings of the Electric Power Research Institute's (EPRI's) 2011 Condenser Technology Conference. A large body of information exists on damage in condenser tubes and related condenser components such as tubesheets and waterboxes. Although technical understanding of damage mechanisms is generally good, past efforts often have not emphasized the practical, action-oriented steps needed to effectively deal with the various forms of damage. This conference was organized to help u...

2011-10-10T23:59:59.000Z

206

Actinide partitioning-transmutation program final report. I. Overall assessment  

SciTech Connect

This report is concerned with an overall assessment of the feasibility of and incentives for partitioning (recovering) long-lived nuclides from fuel reprocessing and fuel refabrication plant radioactive wastes and transmuting them to shorter-lived or stable nuclides by neutron irradiation. The principal class of nuclides considered is the actinides, although a brief analysis is given of the partitioning and transmutation (P-T) of /sup 99/Tc and /sup 129/I. The results obtained in this program permit us to make a comparison of the impacts of waste management with and without actinide recovery and transmutation. Three major conclusions concerning technical feasibility can be drawn from the assessment: (1) actinide P-T is feasible, subject to the acceptability of fuels containing recycle actinides; (2) technetium P-T is feasible if satisfactory partitioning processes can be developed and satisfactory fuels identified (no studies have been made in this area); and (3) iodine P-T is marginally feasible at best because of the low transmutation rates, the high volatility, and the corrosiveness of iodine and iodine compounds. It was concluded on the basis of a very conservative repository risk analysis that there are no safety or cost incentives for actinide P-T. In fact, if nonradiological risks are included, the short-term risks of P-T exceed the long-term benefits integrated over a period of 1 million years. Incentives for technetium and iodine P-T exist only if extremely conservative long-term risk analyses are used. Further RD and D in support of P-T is not warranted.

Croff, A.G.; Blomeke, J.O.; Finney, B.C.

1980-06-01T23:59:59.000Z

207

3rd annual biomass energy systems conference  

DOE Green Energy (OSTI)

The main objectives of the 3rd Annual Biomass Energy Systems Conference were (1) to review the latest research findings in the clean fuels from biomass field, (2) to summarize the present engineering and economic status of Biomass Energy Systems, (3) to encourage interaction and information exchange among people working or interested in the field, and (4) to identify and discuss existing problems relating to ongoing research and explore opportunities for future research. Abstracts for each paper presented were edited separately. (DC)

Not Available

1979-10-01T23:59:59.000Z

208

SOLVENT EXTRACTION PROCESS FOR SEPARATING URANIUM AND PLUTONIUM FROM AQUEOUS ACIDIC SOLUTIONS OF NEUTRON IRRADIATED URANIUM  

DOE Patents (OSTI)

A solvent extraction process was developed for separating actinide elements including plutonium and uranium from fission products. By this method the ion content of the acidic aqueous solution is adjusted so that it contains more equivalents of total metal ions than equivalents of nitrate ions. Under these conditions the extractability of fission products is greatly decreased. (AEC)

Bruce, F.R.

1962-07-24T23:59:59.000Z

209

ISOTOPE SEPARATORS  

DOE Patents (OSTI)

An improvement is presented in the structure of an isotope separation apparatus and, in particular, is concerned with a magnetically operated shutter associated with a window which is provided for the purpose of enabling the operator to view the processes going on within the interior of the apparatus. The shutier is mounted to close under the force of gravity in the absence of any other force. By closing an electrical circuit to a coil mouated on the shutter the magnetic field of the isotope separating apparatus coacts with the magnetic field of the coil to force the shutter to the open position.

Bacon, C.G.

1958-08-26T23:59:59.000Z

210

Proceedings of the Fourteenth DOE solar photochemistry research conference  

DOE Green Energy (OSTI)

The central themes of this year's Solar Photochemistry Research Conference encompassed initial charge separation in photosynthesis, photoinduced charge separation in other organized assemblies, electron transfer, organic and inorganic photochemistry, and photoelectrochemistry. This volume contains a copy of the program the abstracts of 29 formal presentations and 47 posters, a record of the discussion following each presentation, and an address list for the 96 attendees. Individual projects are processed separately for the databases. .

Not Available

1989-01-01T23:59:59.000Z

211

Toward understanding the thermodynamics of TALSPEAK process. Medium effects on actinide complexation  

SciTech Connect

The ingenious combination of lactate and diethylenetriamine-N,N,N’,N”,N”-pentaacetic acid (DTPA) as an aqueous actinide-complexing medium forms the basis of the successful separation of americium and curium from lanthanides known as the TALSPEAK process. While numerous reports in the prior literature have focused on the optimization of this solvent extraction system, considerably less attention has been devoted to the understanding of the basic thermodynamic features of the complex fluids responsible for the separation. The available thermochemical information of both lactate and DTPA protonation and metal complexation reactions are representative of the behavior of these ions under idealized conditions. Our previous studies of medium effects on lactate protonation suggest that significant departures from the speciation predicted based on reported thermodynamic values should be expected in the TALSPEAK aqueous environment. Thermodynamic parameters describing the separation chemistry of this process thus require further examination at conditions significantly removed from conventional ideal systems commonly employed in fundamental solution chemistry. Such thermodynamic characterization is the key to predictive modelling of TALSPEAK. Improved understanding will, in principle, allow process technologists to more efficiently respond to off-normal conditions during large scale process operation. In this report, the results of calorimetric and potentiometric investigations of the effects of aqueous electrolytes on the thermodynamic parameters for lactate protonation and lactate complexation of americium and neodymium will be presented. Studies on the lactate protonation equilibrium will clearly illustrate distinct thermodynamic variations between strong electrolyte aqueous systems and buffered lactate environment.

Peter R Zalupski; Leigh R Martin; Ken Nash; Yoshinobu Nakamura; Masahiko Yamamoto

2009-07-01T23:59:59.000Z

212

Conference Center Lecture Hall  

NLE Websites -- All DOE Office Websites (Extended Search)

401 Library Take the elevators downstairs to the Gallery. 401 Library Take the elevators downstairs to the Gallery. Conference Center Lecture Hall The Lecture Hall is a fully-equipped site for meetings of up to 540 people. This total includes: 237 seats on the Lecture Hall main level; 161 seats in the Lecture Hall balcony; and 142 seats in the two flexible rooms under the balcony (with interior walls removed). These rooms can also be used for meetings, both individually (32 classroom-style seats) or together (72 classroom-style seats). An additional 80 people can be seated in the nearby seminar room (A1100). Photo of the Conference Center's Lecture Hall Conference Center Gallery Seminar Room (A1101) The Seminar Room is located just off the Atrium. Conference Center Lecture Hall Atrium The Conference Center Atrium provides an open, elegant space ideal for registration, informational displays, and social hours. Computers are located just off the Atruim for e-mail access.

213

Proceedings of the joint contractors meeting: FE/EE Advanced Turbine Systems conference FE fuel cells and coal-fired heat engines conference  

SciTech Connect

The joint contractors meeting: FE/EE Advanced Turbine Systems conference FEE fuel cells and coal-fired heat engines conference; was sponsored by the US Department of Energy Office of Fossil Energy and held at the Morgantown Energy Technology Center, P.O. Box 880, Morgantown, West Virginia 26507-0880, August 3--5, 1993. Individual papers have been entered separately.

Geiling, D.W. [ed.

1993-08-01T23:59:59.000Z

214

Information Resources: Past Conferences  

NLE Websites -- All DOE Office Websites (Extended Search)

Past Conferences Past Conferences The U.S. Department of Energy (DOE) hosts workshops, conferences, roundtables, and other meetings related to solid-state lighting (SSL) to provide a forum for information exchange and updates on this rapidly evolving technology. November 2013 DOE SSL Market Introduction Workshop Over 200 attendees gathered at the eighth annual DOE SSL Market Introduction Workshop in Portland, OR, to share the latest updates and strategies for successful market introduction of high-quality, energy-efficient SSL solutions. The workshop was preceded by a half day of free educational sessions for newcomers and lighting professionals alike, and an evening bus tour to see the latest CALiPER LED PAR38 and troffer investigations. Highlights Presentations and Materials

215

NASEO Energy Outlook Conference  

Gasoline and Diesel Fuel Update (EIA)

NASEO Energy Outlook Conference NASEO Energy Outlook Conference 2/26/01 Click here to start Table of Contents NASEO Energy Outlook Conference Retail Product Prices Are Driven By Crude Oil WTI Crude Oil Price: Base Case and 95% Confidence Interval OPEC Crude Oil Production 1998-2001 Annual World Oil Demand Growth by Region, 1991-2001 Total OECD Oil Stocks* Fundamentals Explain High Crude Oil Prices Product Price Spreads Over Crude Oil Vary With Seasons and Supply/Demand Balance U.S. Distillate Inventories Distillate Stocks Are Important Part of East Coast Winter Supply Both Distillate Supply and Demand Reached Extraordinary Levels This Winter Heating Oil Imports Strong in 2001 Retail Heating Oil and Diesel Fuel Prices Consumer Winter Heating Oil Costs Propane prices Influenced by Crude Oil and Natural Gas

216

SciDAC Conferences  

Office of Science (SC) Website

Conferences Conferences Advanced Scientific Computing Research (ASCR) ASCR Home About Research Applied Mathematics Computer Science Next Generation Networking Scientific Discovery through Advanced Computing (SciDAC) Co-Design SciDAC Institutes Computational Science Graduate Fellowship (CSGF) ASCR SBIR-STTR Facilities Science Highlights Benefits of ASCR Funding Opportunities Advanced Scientific Computing Advisory Committee (ASCAC) News & Resources Contact Information Advanced Scientific Computing Research U.S. Department of Energy SC-21/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-7486 F: (301) 903-4846 E: sc.ascr@science.doe.gov More Information » Scientific Discovery through Advanced Computing (SciDAC) SciDAC Conferences Print Text Size: A A A

217

2010 Energy Conference Highlights  

U.S. Energy Information Administration (EIA) Indexed Site

EIA 2010 Energy Conference Highlights EIA 2010 Energy Conference Highlights 2010 Energy Conference: Short-Term Stresses, Long-Term Change Steven Chu, Secretary of Energy Steve Bolze, President/CEO, Power and Water, GE Energy Richard Newell, EIA Administrator, and Lawrence Summers, Director of the National Economic Council Phil Sharp, President, Resources for the Future Secretary Chu answering questions from the media Photo credits: EIA and Kaveh Sardari Plenary keynote addresses: Dr. Richard Newell Read transcript of opening remarks and introduction of Secretary Steven Chu. Dr. Steven Chu Listen to keynote address. Read presentation. Read transcript. Steve Bolze Read presentation. Read transcript. Dr. Phil Sharp Read transcript. Dr. Lawrence Summers Listen to luncheon address. Read transcript.

218

2013 EIA Energy Conference  

U.S. Energy Information Administration (EIA) Indexed Site

conference energy 2013 eia June 17-18, 2013 JW Marriott Washington, DC Welcome to the 2013 EIA Energy Conference. This year's conference highlights one of the more dynamic times in energy that I can remember: skyrocketing growth in U.S. oil and natural gas production, principally from shales, which leads to challenges and opportunities here and around the world for suppliers, consumers, policymakers, and, of course, EIA. Your participation in discussions over the next two days is crucial as we begin a dialogue about the forces that are remaking the energy world at an accelerating pace. We have again this year invited colleagues from both within and outside EIA to present their views on a host of topical energy issues. We look forward to hearing from a distinguished group of speakers

219

Method for separating actinides. [Patent application; stripping of Np from organic extractant  

DOE Patents (OSTI)

An organic solution used for processing spent nuclear reactor fuels is contacted with an aqueous nitric acid solution to strip Np(VI), U(VI), and Pu(IV) from the organic solution into the acid solution. The acid solution is exposed to ultraviolet light, which reduces Np(VI) to Np(V) without reducing U(VI) and Pu(IV). Since the solubility of Np(V) in the organic solution is much lower than that of Np(VI), U(VI), and Pu(IV), a major part of the Np is stripped from the organic solution while leaving most of the U and Pu therein.

Friedman, H.A.; Toth, L.M.

1980-11-10T23:59:59.000Z

220

NETL: Gasification Systems Conferences and Workshops  

NLE Websites -- All DOE Office Websites (Extended Search)

ConferencesWorkshops Gasification Systems Reference Shelf - Conferences and Workshops Click here for a listing of upcoming Gasification Conferences and Workshops. The following...

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

6th World Conference on Detergents  

Science Conference Proceedings (OSTI)

Archive of 6th World Conference on Detergents. 6th World Conference on Detergents Montreux , Switzerland 6th World Conference on Detergents ...

222

Solid-State Lighting: Past Conferences  

NLE Websites -- All DOE Office Websites (Extended Search)

Past Conferences on Twitter Bookmark Solid-State Lighting: Past Conferences on Google Bookmark Solid-State Lighting: Past Conferences on Delicious Rank Solid-State...

223

Complexation of lanthanides and actinides by acetohydroxamic acid  

Science Conference Proceedings (OSTI)

Acetohydroxamic acid (AHA) has been proposed as a suitable reagent for the complexant-based, as opposed to reductive, stripping of plutonium and neptunium ions from the tributylphosphate solvent phase in advanced PUREX or UREX processes designed for future nuclear-fuel reprocessing. Stripping is achieved by the formation of strong hydrophilic complexes with the tetravalent actinides in nitric acid solutions. To underpin such applications, knowledge of the complexation constants of AHA with all relevant actinide (5f) and lanthanide (4f) ions is therefore important. This paper reports the determination of stability constants of AHA with the heavier lanthanide ions (Dy-Yb) and also U(IV) and Th(IV) ions. Comparisons with our previously published AHA stability-constant data for 4f and 5f ions are made. (authors)

Taylor, R.J. [British Technology Centre, Nexia Solutions, Sellafield, Seascale, CA20 1PG (United Kingdom); Sinkov, S.I. [Pacific Northwest National Laboratory, Richland, WA 99352 (United States); Choppin, G.R. [Department of Chemistry and Biochemistry, Florida State University, Tallahassee, FL (United States)

2008-07-01T23:59:59.000Z

224

Chemical properties of the heavier actinides and transactinides  

Science Conference Proceedings (OSTI)

The chemical properties of each of the elements 99 (Es) through 105 are reviewed and their properties correlated with the electronic structure expected for 5f and 6d elements. A major feature of the heavier actinides, which differentiates them from the comparable lanthanides, is the increasing stability of the divalent oxidation state with increasing atomic number. The divalent oxidation state first becomes observable in the anhydrous halides of californium and increases in stability through the series to nobelium, where this valency becomes predominant in aqueous solution. In comparison with the analogous 4f electrons, the 5f electrons in the latter part of the series are more tightly bound. Thus, there is a lowering of the 5f energy levels with respect to the Fermi level as the atomic number increases. The metallic state of the heavier actinides has not been investigated except from the viewpoint of the relative volatility among members of the series. In aqueous solutions, ions of these elements behave as a normal trivalent actinides and lanthanides (except for nobelium). Their ionic radii decrease with increasing nuclear charge which is moderated because of increased screening of the outer 6p electrons by the 5f electrons. The actinide series of elements is completed with the element lawrencium (Lr) in which the electronic configuration is 5f/sup 14/7s/sup 2/7p. From Mendeleev's periodicity and Dirac-Fock calculations, the next group of elements is expected to be a d-transition series corresponding to the elements Hf through Hg. The chemical properties of elements 104 and 105 only have been studied and they indeed appear to show the properties expected of eka-Hf and eka-Ta. However, their nuclear lifetimes are so short and so few atoms can be produced that a rich variety of chemical information is probably unobtainable.

Hulet, E.K.

1981-01-01T23:59:59.000Z

225

Impact of actinide recycle on nuclear fuel cycle health risks  

SciTech Connect

The purpose of this background paper is to summarize what is presently known about potential impacts on the impacts on the health risk of the nuclear fuel cycle form deployment of the Advanced Liquid Metal Reactor (ALMR){sup 1} and Integral Fast Reactor (IF){sup 2} technology as an actinide burning system. In a companion paper the impact on waste repository risk is addressed in some detail. Therefore, this paper focuses on the remainder of the fuel cycle.

Michaels, G.E.

1992-06-01T23:59:59.000Z

226

Benefits of actinide-only burnup credit for shutdown PWRs  

Science Conference Proceedings (OSTI)

Owners of PWRs that are shutdown prior to resolution of interim storage or permanent disposal issues have to make difficult decisions on what to do with their spent fuel. Maine Yankee is currently evaluating multiple options for spent fuel storage. Their spent fuel pool has 1,434 assemblies. In order to evaluate the value to a utility of actinide-only burnup credit, analysis of the number of canisters required with and without burnup credit was made. In order to perform the analysis, loading curves were developed for the Holtec Hi-Star 100/MPC-32. The MPC-32 is hoped to be representative of future burnup credit designs from many vendors. The loading curves were generated using the actinide-only burnup credit currently under NRC review. The canister was analyzed for full loading (32 assemblies) and with partial loadings of 30 and 28 assemblies. If no burnup credit is used the maximum capacity was assumed to be 24 assemblies. this reduced capacity is due to the space required for flux traps which are needed to sufficiently reduce the canister reactivity for the fresh fuel assumption. Without burnup credit the 1,343 assemblies would require 60 canisters. If all the fuel could be loaded into the 32 assembly canisters only 45 canisters would be required. Although the actinide-only burnup credit approach is very conservative, the total number of canisters required is only 47 which is only two short of the minimum possible number of canisters. The utility is expected to buy the canister and the storage overpack. A reasonable cost estimate for the canister plus overpack is $500,000. Actinide-only burnup credit would save 13 canisters and overpacks which is a savings of about $6.5 million. This savings is somewhat reduced since burnup credit requires a verification measurement of burnup. The measurement costs for these assemblies can be estimated as about $1 million. The net savings would be $5.5 million.

Lancaster, D.; Fuentes, E.; Kang, C. [TRW Environmental Safety Systems, INc., Las Vegas, NV (United States); Rivard, D. [Maine Yankee Atomic Power Co., Westboro, MA (United States)

1998-02-01T23:59:59.000Z

227

Chemical and Ceramic Methods Toward Safe Storage of Actinides  

Science Conference Proceedings (OSTI)

A very import, extremely-long-term, use for monazite as a radwaste encapsulant has been proposed. THe use of ceramic La-monazite for sequestering actinides (isolating them from the environment), especially plutonium and some other radioactive elements )e.g., fission-product rare earths), had been especially championed by Lynn Boatner of ORNL. Monazite may be used alone or, copying its compatibility with many other minerals in nature, may be used in diverse composite combinations.

P.E.D. Morgan; R.M. Housley; J.B. Davis; M.L. DeHaan

2005-08-19T23:59:59.000Z

228

Detection of Actinides via Nuclear Isomer De-Excitation  

Science Conference Proceedings (OSTI)

This dissertation discusses a data collection experiment within the Actinide Isomer Identification project (AID). The AID project is the investigation of an active interrogation technique that utilizes nuclear isomer production, with the goal of assisting in the interdiction of illicit nuclear materials. In an attempt to find and characterize isomers belonging to 235U and its fission fragments, a 232Th target was bombarded with a monoenergetic 6Li ion beam, operating at 45 MeV.

Francy, Christopher J.

2009-07-22T23:59:59.000Z

229

Thireenth international conference on cyclotrons and their applications. Conference summary  

SciTech Connect

This report contains short descriptions of papers presented at the Thirteenth International Conference on Cyclotrons and Their Applications.

Clark, D.J.

1992-07-01T23:59:59.000Z

230

Toward laser ablation Accelerator Mass Spectrometry of actinides  

Science Conference Proceedings (OSTI)

A project to measure neutron capture cross sections of a number of actinides in a reactor environment by Accelerator Mass Spectrometry (AMS) at the ATLAS facility of Argonne National Laboratory is underway. This project will require the precise and accurate measurement of produced actinide isotopes in many (>30) samples irradiated in the Advanced Test Reactor at Idaho National Laboratory with neutron fluxes having different energy distributions. The AMS technique at ATLAS is based on production of highlycharged positive ions in an electron cyclotron resonance (ECR) ion source followed by acceleration in the ATLAS linac and mass-to-charge (m/q) measurement at the focus of the Fragment Mass Analyzer. Laser ablation was selected as the method of feeding the actinide material into the ion source because we expect it will have higher efficiency and lower chamber contamination than either the oven or sputtering techniques, because of a much narrower angular distribution of emitted material. In addition, a new multi-sample holder/changer to allow quick change between samples and a computer-controlled routine allowing fast tuning of the accelerator for different beams, are being developed. An initial test run studying backgrounds, detector response, and accelerator scaling repeatability was conducted in December 2010. The project design, schedule, and results of the initial test run to study backgrounds are discussed.

R. C. Pardo; F. G. Kondev; S. Kondrashev; C. Nair; T. Palchan; R. Scott; D. Seweryniak; R. Vondrasek; M. Paul; P. Collon; C. Deibel; M. Salvatores; G. Palmiotti; J. Berg; J. Fonnesbeck; G. Imel

2013-01-01T23:59:59.000Z

231

Disposition of actinides released from high-level waste glass  

SciTech Connect

A series of static leach tests was conducted using glasses developed for vitrifying tank wastes at the Savannah River Site to monitor the disposition of actinide elements upon corrosion of the glasses. In these tests, glasses produced from SRL 131 and SRL 202 frits were corroded at 90{degrees}C in a tuff groundwater. Tests were conducted using crushed glass at different glass surface area-to-solution volume (S/V) ratios to assess the effect of the S/V on the solution chemistry, the corrosion of the glass, and the disposition of actinide elements. Observations regarding the effects of the S/V on the solution chemistry and the corrosion of the glass matrix have been reported previously. This paper highlights the solution analyses performed to assess how the S/V used in a static leach test affects the disposition of actinide elements between fractions that are suspended or dissolved in the solution, and retained by the altered glass or other materials.

Ebert, W.L.; Bates, J.K.; Buck, E.C.; Gong, M.; Wolf, S.F.

1994-05-01T23:59:59.000Z

232

Behavior of actinides in the Integral Fast Reactor fuel cycle  

SciTech Connect

The Integral Fast Reactor (IFR) under development by Argonne National Laboratory uses metallic fuels instead of ceramics. This allows electrorefining of spent fuels and presents opportunities for recycling minor actinide elements. Four minor actinides ({sup 237}Np, {sup 240}Pu, {sup 241}Am, and {sup 243}Am) determine the waste storage requirements of spent fuel from all types of fission reactors. These nuclides behave the same as uranium and other plutonium isotopes in electrorefining, so they can be recycled back to the reactor without elaborate chemical processing. An experiment has been designed to demonstrate the effectiveness of the high-energy neutron spectra of the IFR in consuming these four nuclides and plutonium. Eighteen sets of seven actinide and five light metal targets have been selected for ten day exposure in the Experimental Breeder Reactor-2 which serves as a prototype of the IFR. Post-irradiation analyses of the exposed targets by gamma, alpha, and mass spectroscopy are used to determine nuclear reaction-rates and neutron spectra. These experimental data increase the authors` confidence in their ability to predict reaction rates in candidate IFR designs using a variety of neutron transport and diffusion programs.

Courtney, J.C. [Louisiana State Univ., Baton Rouge, LA (United States). Nuclear Science Center; Lineberry, M.J. [Argonne National Lab., Idaho Falls, ID (United States). Technology Development Div.

1994-06-01T23:59:59.000Z

233

Transuranic actinide reactions with simple gas-phase molecules.  

DOE Green Energy (OSTI)

The intent of this research is to conduct an experimental study of f-element chemistry fo r the purpose of identifying reaction trends and mechanisms of the early actinide metals with simple gas phase molecules . Previous research has elucidated some of the fundamenta l chemistry of the 4f elements,1-5 however, more complex chemistry is expected for the 5f serie s due to the inclusion of the 5f electrons in the valence shell . The matrix isolation approach, which is well-suited to the experimental study of transient species, will be used for sample collection, and IR/NIR/VIS spectroscopy will be employed to interrogate deposited matrices . The strength of this method lies in the use of isotopes of reactants, which permits the identification of guest molecules in a noble gas matrix by observation of vibrational frequenc y shifts and patterns upon isotopic substitution . Using this technique at the University of Virginia, the first noble gas-actinide bond has recently been identified, a weak U-Ar bond on the CUO molecule.6 Uranium has similarly been observed to bond to krypton and xenon, whereas thoriu m and the lanthanides have not exhibited this activity . It is expected that plutonium will be even more reactive in this respect . We will extend the body of actinide experimental evidence t o include the transuranic elements neptunium, plutonium, and americium reacted with isotopes o f oxygen, nitrogen, hydrogen, carbon monoxide, and carbon dioxide .

Willson, S. P. (Stephen P.); Veirs, D. K. (Douglas Kirk); Baiardo, J. P. (Joseph P.)

2003-01-01T23:59:59.000Z

234

Gas separating  

DOE Patents (OSTI)

Feed gas is directed tangentially along the non-skin surface of gas separation membrane modules comprising a cylindrical bundle of parallel contiguous hollow fibers supported to allow feed gas to flow from an inlet at one end of a cylindrical housing through the bores of the bundled fibers to an outlet at the other end while a component of the feed gas permeates through the fibers, each having the skin side on the outside, through a permeate outlet in the cylindrical casing. 3 figs.

Gollan, A.

1988-03-29T23:59:59.000Z

235

Analysis of Advanced Actinide-Fueled Energy Systems for Deep Space Propulsion Applications.  

E-Print Network (OSTI)

??The present study is focused on evaluating higher actinides beyond uranium that are capable of supporting power and propulsion requirements in robotic deep space and… (more)

Guy, Troy Lamar

2011-01-01T23:59:59.000Z

236

EA-1404: Actinide Chemistry and Repository Science Laboratory, Carlsbad, New Mexico  

Energy.gov (U.S. Department of Energy (DOE))

This EA evaluates the environmental impacts for the proposal to construct and operate an Actinide Chemistry and Repository Science Laboratory to support chemical research activities related to the...

237

EIA - Energy Conferences & Presentations.  

U.S. Energy Information Administration (EIA) Indexed Site

Presentations & Conferences > Conferences > EIA 2008 Energy Conference Presentations & Conferences > Conferences > EIA 2008 Energy Conference Energy Information Administration 2008 Energy Conference: 30 Years of Energy Information and Analysis Conference Videos now available Click presenter name to download PDF of presentation. Monday, April 7 7:30am- 9:00am Registration 9:00am- 10:30am Opening Session Welcome - Guy Caruso, EIA Administrator Keynote Speakers - Secretary Samuel Bodman (full text of speech), Secretary James Schlesinger Distinguished Guest Speaker - Daniel Yergin (Cambridge Energy Research Associates, Inc.) 10:30am- 11:00am Break 11:00am- 12:30pm Concurrent Sessions EIA Program Review and Assessment: Responding to Change Moderator: Howard Gruenspecht (EIA) Panel: Denny Ellerman (Massachusetts Institute of Technology), Lori Krauss (Office of Management and Budget), Kathy Cooper (Southern Methodist University)

238

Online Particle Physics Information - Conferences  

NLE Websites -- All DOE Office Websites (Extended Search)

Conferences Database of more than 12,300 past, present and future conferences, schools, and meetings of interest to high-energy physics and related fields. Covers 1973 to...

239

EMSL: News: Conferences and Events  

NLE Websites -- All DOE Office Websites (Extended Search)

YouTube icon flickr Conferences & Events Past Conferences 2013 August 6-7, 2013 EMSL 2013 User Meeting Richland, WA August 4-8, 2013 M&M 2013 Microscopy and Microanalysis...

240

2008 NORTHEAST RENEWABLE ENERGY CONFERENCE  

E-Print Network (OSTI)

2008 NORTHEAST RENEWABLE ENERGY CONFERENCE Penn Stater Conference Center State College, Pennsylvania AUGUST 26 - 28, 2008 Renewable Energy ­ It's on everyone's mind. The 2008 Northeast Renewable renewable energy and energy efficiency research, demonstrations, and university

Andrews, Anne M.

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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241

Hydrogen Conference: Workshop Proceedings  

Science Conference Proceedings (OSTI)

Hydrogen is currently a major chemical/fuel with long-term energy system benefits that may impact the industry's physical and economic well-being. EPRI's recent hydrogen conference concluded that to be competitive, the production cost must take into account environmental and end-use efficiency benefits.

1989-10-20T23:59:59.000Z

242

Cooling Tower Technology Conference  

Science Conference Proceedings (OSTI)

Cooling towers and associated systems cause significant loss of availability and heat rate degradation in both nuclear and fossil-fired power plants. Twenty-one papers presented at a 2003 conference in Charleston, South Carolina discussed industrial experience and provided case histories of cooling tower problems and solutions.

2003-08-12T23:59:59.000Z

243

Carbamoylmethylphosphoryl derivatives as actinide extractants: their significance in the processing and recovery of plutonium and other actinides  

SciTech Connect

Three classes of carbamoylmethylphosphoryl extractants were studied for their ability to extract selected tri-, tetra-, and hexavalent actinides from nitric acid. The three extractants are dihexyl-N,N-diethylcarbamoylmethylphosphonate (DHDECMP), hexyl hexyl-N,N-diethylcarbamoylmethylphosphinate (HHDECMP), and octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide OphiD(IB)CMPO. The above three extractants were compared on the basis of nitric acid and extractant dependencies for Am(III), solubility of complexes on loading with Nd(III) and U(VI), and selectivity of actinide(III) over fission products. The influence of temperature on D/sub Am/ from LiNO/sub 3/ (10/sup -2/ M HNO/sub 3/) and from 3 M HNO/sub 3/ using dilute solutions of DHDECMP, HHDECMP OphiD(IB)CMPO in o-xylene showed that the increase in D/sub Am/ in the series phosphone-phophinate-phosphine oxide was due primarily to an increase in the enthalpy of extraction. This information was used to develop conceptual flowsheets for the extraction of all of the actinides (U, Np, Pu, Am, and Cm) from high-level waste from PUREX processing using 0.4 M OphiD(IB)CMPO in DEB and for the extraction of all of the actinides from dissolved spent LWR fuel using 0.8 M DHDECMP in DEB. In both flowsheets, no oxidation state of Pu is necessary since the III, IV, and VI state extract into the organic phase. 15 references, 6 figures, 7 tables.

Horwitz, E.P.; Diamond, H.; Kalina, D.G.

1983-01-01T23:59:59.000Z

244

LIBS Spectral Data for a Mixed Actinide Fuel Pellet Containing Uranium, Plutonium, Neptunium and Americium  

Science Conference Proceedings (OSTI)

Laser-induced breakdown spectroscopy (LIBS) was used to analyze a mixed actinide fuel pellet containing 75% UO{sub 2}/20% PuO{sub 2}/3% AmO{sub 2}/2% NpO{sub 2}. The preliminary data shown here is the first report of LIBS analysis of a mixed actinide fuel pellet, to the authors knowledge. The LIBS spectral data was acquired in a plutonium facility at Los Alamos National Laboratory where the sample was contained within a glove box. The initial installation of the glove box was not intended for complete ultraviolet (UV), visible (VIS) and near infrared (NIR) transmission, therefore the LIBS spectrum is truncated in the UV and NIR regions due to the optical transmission of the window port and filters that were installed. The optical collection of the emission from the LIBS plasma will be optimized in the future. However, the preliminary LIBS data acquired is worth reporting due to the uniqueness of the sample and spectral data. The analysis of several actinides in the presence of each other is an important feature of this analysis since traditional methods must chemically separate uranium, plutonium, neptunium, and americium prior to analysis. Due to the historic nature of the sample fuel pellet analyzed, the provided sample composition of 75% UO{sub 2}/20% PuO{sub 2}/3% AmO{sub 2}/2% NpO{sub 2} cannot be confirm without further analytical processing. Uranium, plutonium, and americium emission lines were abundant and easily assigned while neptunium was more difficult to identify. There may be several reasons for this observation, other than knowing the exact sample composition of the fuel pellet. First, the atomic emission wavelength resources for neptunium are limited and such techniques as hollow cathode discharge lamp have different dynamics than the plasma used in LIBS which results in different emission spectra. Secondly, due to the complex sample of four actinide elements, which all have very dense electronic energy levels, there may be reactions and interactions occurring within the plasma, such as collisional energy transfer, that might be a factor in the reduction in neptunium emission lines. Neptunium has to be analyzed alone using LIBS to further understand the dynamics that may be occurring in the plasma of the mixed actinide fuel pellet sample. The LIBS data suggests that the emission spectrum for the mixed actinide fuel pellet is not simply the sum of the emission spectra of the pure samples but is dependent on the species present in the plasma and the interactions and reactions that occur within the plasma. Finally, many of the neptunium lines are in the near infrared region which is drastically reduced in intensity by the current optical setup and possibly the sensitivity of the emission detector in the spectral region. Once the optics are replaced and the optical collection system is modified and optimized, the probability of observing emission lines for neptunium might be increased significantly. The mixed actinide fuel pellet was analyzed under the experimental conditions listed in Table 1. The LIBS spectra of the fuel pellet are shown in Figures 1-49. The spectra are labeled with the observed wavelength and atomic species (both neutral (I) and ionic (II)). Table 2 is a complete list of the observed and literature based emission wavelengths. The literature wavelengths have references including NIST Atomic Spectra Database (NIST), B.A. Palmer et al. 'An Atlas of Uranium Emission Intensities in a Hollow Cathode Discharge' taken at the Kitt Peak National Observatory (KPNO), R.L. Kurucz 1995 Atomic Line Data from the Smithsonian Astrophysical Observatory (SAO), J. Blaise et al. 'The Atomic Spectrum of Plutonium' from Argonne National Laboratory (BFG), and M. Fred and F.S. Tomkins, 'Preliminary Term Analysis of Am I and Am II Spectra' (FT). The dash (-) shown under Ionic State indicates that the ionic state of the transition was not available. In the spectra, the dash (-) is replaced with a question mark (?). Peaks that are not assigned are most likely real features and not noise but cannot be confidently assi

Judge, Elizabeth J. [Los Alamos National Laboratory; Berg, John M. [Los Alamos National Laboratory; Le, Loan A. [Los Alamos National Laboratory; Lopez, Leon N. [Los Alamos National Laboratory; Barefield, James E. [Los Alamos National Laboratory

2012-06-18T23:59:59.000Z

245

Conferences | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Conferences Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs > Office of Advanced Simulation and Computing Institutional Research...

246

Registration - 22nd NISS Conference  

Science Conference Proceedings (OSTI)

... The registration fee covers conference materials, coffee breaks, and admission to the banquet and award ceremony and reception. ...

2002-03-22T23:59:59.000Z

247

25th Annual Users' Conference  

NLE Websites -- All DOE Office Websites (Extended Search)

Registration Conference Schedule Poster Information Banquet Directions SSRLUO Ballot Lodging Information Travel to SLAC Visitor Information For Additional Information Contact:...

248

Particle separation  

DOE Patents (OSTI)

Embodiments of a method for selecting particles, such as based on their morphology, is disclosed. In a particular example, the particles are charged and acquire different amounts of charge, or have different charge distributions, based on their morphology. The particles are then sorted based on their flow properties. In a specific example, the particles are sorted using a differential mobility analyzer, which sorts particles, at least in part, based on their electrical mobility. Given a population of particles with similar electrical mobilities, the disclosed process can be used to sort particles based on the net charge carried by the particle, and thus, given the relationship between charge and morphology, separate the particles based on their morphology.

Moosmuller, Hans (Reno, NV); Chakrabarty, Rajan K. (Reno, NV); Arnott, W. Patrick (Reno, NV)

2011-04-26T23:59:59.000Z

249

Events and Conferences | National Security | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Areas Initiatives Facilities Events and Conferences Supporting Organizations National Security Home | Science & Discovery | National Security | Events and Conferences Events...

250

2001 Electronic Materials Conference: Student Information - TMS  

Science Conference Proceedings (OSTI)

2001 Electronic Materials Conference: Student Information ... and should provide for maximum exchange of information between attendees of both conferences.

251

Understanding the Chemistry of the Actinides in HL Waste Tank Systems: Actinide Speciation in Oxalic Acid Solutions in the Presence of Significant Quantities of Aluminum, Iron, and Manganese  

SciTech Connect

The overall goal of this research plan is to provide a thermodynamic basis for describing actinide speciation over a range of tank-like conditions, including elevated temperature, elevated OH- concentrations, and the presence of various organic ligands. With support from DOE?s EMSP program, we have made significant progress towards measuring thermodynamic parameters for actinide complexation as a function of temperature. We have used the needs of the ESP modelers to guide our work to date, and we have made important progress defining the effect of temperature for actinide complexation by organic, and for hydrolysis of the hexa- and pentvalent oxidation states.

Clark, Sue

2006-07-30T23:59:59.000Z

252

Energy Conferences and Symposia; (USA)  

DOE Green Energy (OSTI)

Energy Conferences and Symposia, a monthly publication, was instituted to keep scientists, engineers, managers, and related energy professionals abreast of meetings sponsored by the Department of Energy (DOE) and by other technical associations. Announcements cover conference, symposia, workshops, congresses, and other formal meetings pertaining to DOE programmatic interests. Complete meeting information, including title, sponsor, and contact, is presented in the main section, which is arranged alphabetically by subject area. Within a subject, citations are sorted by beginning data of the meeting. New listings are indicated by a bullet after the conference number and DOE-sponsored conferences are indicated by a star. Two indexes are provided for cross referencing conference information. The Chronological Index lists conference titles by dates and gives the subject area where complete information they may be found. The Location Index is alphabetically sorted by the city where the conference will be held.

Osborne, J.H.; Simpson, W.F. Jr. (eds.)

1991-01-01T23:59:59.000Z

253

Address EJ Conference  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Congressman Clyburn to Congressman Clyburn to Address EJ Conference Congressman Clyburn has graciously agreed to speak at The State of Environmental Justice in America 2011 Conference. Congressman Clyburn (D - SC) has been a member of the U.S. House of Congress since 1993. He has held the positions of Chairman of the Democratic Black Caucus, House Democratic Caucus Vice Chair, Chair of the Democratic Caucus and from 2006 until January 2011, was the House Majority Whip. Currently, as Assistant Democratic Leader in the 112th Congress and the number three Democrat in the House, James E. Clyburn will be the leadership liaison to the Appropriations Committee and one of the Democratic Caucus' primary liaisons to the White House. Congressman Clyburn has been a life long champion and has worked diligently

254

DOE Technical Conference  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Conference Conference March 29, 2006 Poonum Agrawal Office of Electricity Delivery and Energy Reliability US Department of Energy 2 Considerations in the Statute the economic vitality and development of the corridor, or the end markets served by the corridor, may be constrained by lack of adequate or reasonably priced electricity; (i) the economic growth in the corridor, or the end markets served by the corridor, may be jeopardized by reliance on limited sources of energy; and (ii) a diversification of supply is warranted; the energy independence of the United States would be served by the designation; the designation would be in the interest of national energy policy; and the designation would enhance national defense and homeland security. 3 Criteria

255

Mississippi Climate & Hydrology Conference  

SciTech Connect

The GEWEX Continental International Project (GCIP), which started in 1995 and completed in 2001, held its grand finale conference in New Orleans, LA in May 2002. Participants at this conference along with the scientists funded through the GCIP program are invited to contribute a paper to a special issue of Journal of Geophysical Research (JGR). This special JGR issue (called GCIP3) will serve as the final report on scientific research conducted by GCIP investigators. Papers are solicited on the following topical areas, but are not limited to, (1) water energy budget studies; (2) warm season precipitation; (3) predictability and prediction system; (4) coupled land-atmosphere models; (5) climate and water resources applications. The research areas cover observations, modeling, process studies and water resources applications.

Lawford, R.; Huang, J.

2002-05-01T23:59:59.000Z

256

Neutron Scattering Conference Archive  

NLE Websites -- All DOE Office Websites (Extended Search)

Conference Archive Conference Archive A new portal for neutron scattering has just been established at neutronsources.org. The information contained here in the Neutron Scattering Web has been transferred to the new site. We will leave the current content here for archival purposes but no new content will be added. We encourage everyone interested in neutron scattering to take full advantage of this exciting new resource for our community. Neutronsources.org 2000 | 2001 | 2002 | 2003 | 2004 | 2005 | 2006 | 2007 | 2008 | 2009 | 2010 | 2011 | 2012 2000 June 12-14, 2000 Workshop on "New Opportunities for Better User Group Software (NOBUGS III)" Location Daresbury Laboratory, Cheshire, UK Contact Mark Enderby, Daresbury Laboratory Email M.J.Enderby@dl.ac.uk URL http://nobugs.dl.ac.uk/

257

Gateway Energy Conference  

Science Conference Proceedings (OSTI)

This book presents the papers given at a conference whose purpose was to provide a forum for the exchange of energy information between leaders in business, industry, labor, government, and education. Topics considered at the conference included the economics of energy, agriculture and changing natural gas prices, the economics of superinsulation in the rehabilitation of historic buildings, energy conservation in small industries, computer systems for power demand control, a solar absorption lumber drying system, selective absorbers for Trombe walls, daylighting, lighting control, portable heaters, unitary heat pumps, the electrochemical oxidation of coal, a slurry fuels development program, coal gasification, coal desulfurization, a waste coal recovery process, coal-fired boilers, surface mining of coal, steam gasification of wood, wood fuel use by households, fusion power, and the economic aspects of nuclear waste disposal.

Sauer, H.J.; Hegler, B.E.

1983-01-01T23:59:59.000Z

258

Metabolic Engineering VII Conference  

SciTech Connect

The aims of this Metabolic Engineering conference are to provide a forum for academic and industrial researchers in the field; to bring together the different scientific disciplines that contribute to the design, analysis and optimization of metabolic pathways; and to explore the role of Metabolic Engineering in the areas of health and sustainability. Presentations, both written and oral, panel discussions, and workshops will focus on both applications and techniques used for pathway engineering. Various applications including bioenergy, industrial chemicals and materials, drug targets, health, agriculture, and nutrition will be discussed. Workshops focused on technology development for mathematical and experimental techniques important for metabolic engineering applications will be held for more in depth discussion. This 2008 meeting will celebrate our conference tradition of high quality and relevance to both industrial and academic participants, with topics ranging from the frontiers of fundamental science to the practical aspects of metabolic engineering.

Kevin Korpics

2012-12-04T23:59:59.000Z

259

Proceedings: 17th Asilomar conference on fire and blast effects of nuclear weapons  

Science Conference Proceedings (OSTI)

The objective of the 1983 conference was to provide for the technical exchange of ideas relating to the science and technology of the immediate effects of nuclear weapon explosions. Separate abstracts were prepared for 39 of the papers.

Hickman, R.G.; Meier, C.A. (eds.) [eds.

1983-01-01T23:59:59.000Z

260

2012 SWAT Conference Proceedings  

E-Print Network (OSTI)

The following proceedings are a collection of papers presented at the 2012 International Soil and Water Assessment Tool (SWAT) Conference held in New Delhi, India, July 18-20, 2012. SWAT is a public domain model jointly developed by USDA Agricultural Research Service (USDA-ARS) and Texas A&M AgriLife Research, part of The Texas A&M University System. SWAT is a small watershed to river basin-scale model to simulate the quality and quantity of surface and ground water and predict the environmental impact of land use, land management practices, and climate change. SWAT is widely used in assessing soil erosion prevention and control, non-point source pollution control and regional management in watersheds. The papers presented in the 2012 proceedings cover the following topics: Large scale applications; Climate change applications; Sensitivity calibration and uncertainty; Biofuel and plant growth; Environmental applications; BMPs; Hydrology; Sediment, nutrients, and carbon; Pesticides, bacteria, metals, and pharmaceuticals; Model development; Database and GIS application and development; Urban processes and management; Landscape processes and landscape / river continuum; In-stream sediment and pollutant transport; Ganga river basin management; Swat applications and development in India Presentations and video from the conference, along with more information on SWAT are available on the conference website.

Srinivasan, R.

2013-02-20T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Criticality (keff) Predictions  

SciTech Connect

One of the most significant remaining challenges associated with expanded implementation of burnup credit in the United States is the validation of depletion and criticality calculations used in the safety evaluation - in particular, the availability and use of applicable measured data to support validation, especially for fission products. Applicants and regulatory reviewers have been constrained by both a scarcity of data and a lack of clear technical basis or approach for use of the data. U.S. Nuclear Regulatory Commission (NRC) staff have noted that the rationale for restricting their Interim Staff Guidance on burnup credit (ISG-8) to actinide-only is based largely on the lack of clear, definitive experiments that can be used to estimate the bias and uncertainty for computational analyses associated with using burnup credit. To address the issue of validation, the NRC initiated a project with the Oak Ridge National Laboratory to (1) develop and establish a technically sound validation approach (both depletion and criticality) for commercial spent nuclear fuel (SNF) criticality safety evaluations based on best-available data and methods and (2) apply the approach for representative SNF storage and transport configurations/conditions to demonstrate its usage and applicability, as well as to provide reference bias results. The purpose of this paper is to describe the criticality (k{sub eff}) validation approach, and resulting observations and recommendations. Validation of the isotopic composition (depletion) calculations is addressed in a companion paper at this conference. For criticality validation, the approach is to utilize (1) available laboratory critical experiment (LCE) data from the International Handbook of Evaluated Criticality Safety Benchmark Experiments and the French Haut Taux de Combustion (HTC) program to support validation of the principal actinides and (2) calculated sensitivities, nuclear data uncertainties, and the limited available fission product LCE data to predict and verify individual biases for relevant minor actinides and fission products. This paper (1) provides a detailed description of the approach and its technical bases, (2) describes the application of the approach for representative pressurized water reactor and boiling water reactor safety analysis models to demonstrate its usage and applicability, (3) provides reference bias results based on the prerelease SCALE 6.1 code package and ENDF/B-VII nuclear cross-section data, and (4) provides recommendations for application of the results and methods to other code and data packages.

Scaglione, John M [ORNL; Mueller, Don [ORNL; Wagner, John C [ORNL

2011-01-01T23:59:59.000Z

262

Fourteenth combustion research conference  

SciTech Connect

A total of 92 papers (arranged alphabetically by author) are included. Separate abstracts have been prepared for the data base. (DLC)

Not Available

1992-08-01T23:59:59.000Z

263

8th Global warming international conference and exposition  

Science Conference Proceedings (OSTI)

Abstracts are presented from The 8th Annual Global Warming international conference and expo. Topics centered around greenhouse gas emission and disposal methods, policy and economics, carbon budget, and resource management. Individual reports have been processed separately for the United States Department of Energy databases.

NONE

1997-12-31T23:59:59.000Z

264

Second technical contractors' conference on peat  

SciTech Connect

This conference reported the status of the US Department of Energy Peat Program. The program includes peat resource surveys of eleven states, peat gasification process and equipment studies, dewatering studies, and environmental and socioeconomic factors in the development of peat technology. Separate abstracts were prepared for selected papers. (CKK)

1980-01-01T23:59:59.000Z

265

Proceedings of the Nineteenth DOE Solar Photochemistry Research Conference  

DOE Green Energy (OSTI)

This document is a compilation of reports presented at the Nineteenth DOE Solar Photochemistry Research Conference. Sessions included photophysical properties of transition metal complexes, cage effects on photochemistry, charge transfer, photo-induced charge separation in biomimetic molecules, photosynthesis, and electron transfer.

NONE

1995-07-01T23:59:59.000Z

266

Sixth annual coal preparation, utilization, and environmental control contractors conference  

SciTech Connect

A conference was held on coal preparation, utilization and environmental control. Topics included: combustion of fuel slurries; combustor performance; desulfurization chemically and by biodegradation; coal cleaning; pollution control of sulfur oxides and nitrogen oxides; particulate control; and flue gas desulfurization. Individual projects are processed separately for the databases. (CBS).

Not Available

1990-01-01T23:59:59.000Z

267

Annual Energy Outlook 2000 Conference  

Gasoline and Diesel Fuel Update (EIA)

Summary of Last Year's Conference Summary of Last Year's Conference The Energy Information Administration (EIA) will host its eighth annual National Energy Modeling System/Annual Energy Outlook Conference on March 21, 2000, at the Crystal Gateway Marriott, 1700 Jefferson Davis Highway, Arlington, VA, near the Crystal City Metro station. The conference includes speakers and attendees from Federal and State governments, private industry, and trade associations, discussing energy issues particularly related to EIAÂ’s Annual Energy Outlook 2000, which was released in November 1999, and the National Energy Modeling System. Conference Registration Conference registration is free, but space is limited. You can register on-line or fax this form to: Peggy Wells Energy Information Administration, EI-84

268

Effects of actinide burning on waste disposal at Yucca Mountain  

SciTech Connect

Release rates of 15 radionuclides from waste packages expected to result from partitioning and transmutation of Light-Water Reactor (LWR) and Actinide-Burning Liquid-Metal Reactor (ALMR) spent fuel are calculated and compared to release rates from standard LWR spent fuel packages. The release rates are input to a model for radionuclide transport from the proposed geologic repository at Yucca Mountain to the water table. Discharge rates at the water table are calculated and used in a model for transport to the accessible environment, defined to be five kilometers from the repository edge. Concentrations and dose rates at the accessible environment from spent fuel and wastes from reprocessing, with partitioning and transmutation, are calculated. Partitioning and transmutation of LWR and ALMR spent fuel reduces the inventories of uranium, neptunium, plutonium, americium and curium in the high-level waste by factors of 40 to 500. However, because release rates of all of the actinides except curium are limited by solubility and are independent of package inventory, they are not reduced correspondingly. Only for curium is the repository release rate much lower for reprocessing wastes.

Hirschfelder, J. [California Univ., Berkeley, CA (United States)

1992-07-01T23:59:59.000Z

269

Conservative axial burnup distributions for actinide-only burnup credit  

SciTech Connect

Unlike the fresh fuel approach, which assumes the initial isotopic compositions for criticality analyses, any burnup credit methodology must address the proper treatment of axial burnup distributions. A straightforward way of treating a given axial burnup distribution is to segment the fuel assembly into multiple meshes and to model each burnup mesh with the corresponding isotopic compositions. Although this approach represents a significant increase in modeling efforts compared to the uniform average burnup approach, it can adequately determine the reactivity effect of the axial burnup distribution. A major consideration is what axial burnup distributions are appropriate for use in light of many possible distributions depending on core operating conditions and histories. This paper summarizes criticality analyses performed to determine conservative axial burnup distributions. The conservative axial burnup distributions presented in this paper are included in the Topical Report on Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel Packages, Revision 1 submitted in May 1997 by the US Department of Energy (DOE) to the US Nuclear Regulatory Commission (NRC). When approved by NRC, the conservative axial burnup distributions may be used to model PWR spent nuclear fuel for the purpose of gaining actinide only burnup credit.

Kang, C.; Lancaster, D.

1997-11-01T23:59:59.000Z

270

Rural Energy Conference Project  

SciTech Connect

Alaska remains, even at the beginning of the 21st century, a place with many widely scattered, small, remote communities, well beyond the end of both the road system and the power grid. These communities have the highest energy costs of any place in the United States, despite the best efforts of the utilities that service them. This is due to the widespread dependence on diesel electric generators, which require small capital investments, but recent increases in crude oil prices have resulted in dramatic increases in the cost of power. In the enabling legislation for the Arctic Energy Office in 2001, specific inclusion was made for the study of ways of reducing the cost of electrical power in these remote communities. As part of this mandate, the University of Alaska has, in conjunction with the US Department of Energy, the Denali Commission and the Alaska Energy Authority, organized a series of rural energy conferences, held approximately every 18 months. The goal of these meeting was to bring together rural utility operators, rural community leaders, government agency representatives, equipment suppliers, and researchers from universities and national laboratories to discuss the current state of the art in rural power generation, to discuss current projects, including successes as well as near successes. Many of the conference presenters were from industry and not accustomed to writing technical papers, so the typical method of organizing a conference by requesting abstracts and publishing proceedings was not considered viable. Instead, the organizing committee solicited presentations from appropriate individuals, and requested that (if they were comfortable with computers) prepare Power point presentations that were collected and posted on the web. This has become a repository of many presentations, and may be the best single source of information about current projects in the state of Alaska.

Dennis Witmer; Shannon Watson

2008-12-31T23:59:59.000Z

271

Proceedings: pellet fuels conference  

DOE Green Energy (OSTI)

The conference brought together professionals from the process- engineered-fuels (PEF), utility, paper, plastics, and boiler industries. Although the last two decades have produced technical breakthroughs, efforts to advance PEF must now focus on increasing commercial breakthroughs. Successful commercialization will depend on increasing supplier, consumer, and regulator confidence and support by demonstrating the performance and value of PEF products. Speakers provided updates on how PEF technology is evolving with respect to technical, economic, and regulatory challenges. Actions critical toward full commercialization of PEF were then considered. Discussion groups addressed materials sourcing, fuel processing and transportation, combustion, and ash handling.

Not Available

1995-12-31T23:59:59.000Z

272

EMC 2007: Conference Organizers - TMS  

Science Conference Proceedings (OSTI)

2007 ELECTRONIC MATERIALS CONFERENCE • June 20-22, 2007• University of Notre Dame • Indiana, USA. EMC 2007 Menu. EMC 2007 HOME PAGE ...

273

Ozone Conference II: Abstract Proceedings  

Science Conference Proceedings (OSTI)

Ozone Conference II: Pre- and Post-Harvest Applications Two Years After Gras, was held September 27-28, 1999 in Tulare, California. This conference, sponsored by EPRI's Agricultural Technology Alliance and Southern California Edison's AgTAC facility, was coordinated and organized by the on-site ATA-AgTAC Regional Center. Approximately 175 people attended the day-and-a-half conference at AgTAC. During the Conference twenty-two presentations were given on ozone food processing and agricultural applications...

1999-11-24T23:59:59.000Z

274

NAFOA Finance & Tribal Economies Conference  

Energy.gov (U.S. Department of Energy (DOE))

The Native American Finance Officers Association (NAFOA) will host their fall conference on finance and tribal economies at the Hard Rock Hotel in San Diego, California. 

275

Document Understanding Conferences - Related Publications  

Science Conference Proceedings (OSTI)

... Proceedings of the 5th International Joint Conference on Natural Language Processing (IJCNLP 2011), Chiang Mai, Thailand, pages 1098-1106. ...

276

2012 Regional Conference Sponsorship Packages  

Science Conference Proceedings (OSTI)

... in conference e-mail marketing – your organization's ... $7,500 exclusive (available in Arizona only) ... Moines, IA • September 28, 2012 | Scottsdale, AZ

2012-09-08T23:59:59.000Z

277

Partition of actinides and fission products between metal and molten salt phases: Theory, measurement, and application to IFR pyroprocess development  

Science Conference Proceedings (OSTI)

The chemical basis of Integral Fast Reactor fuel reprocessing (pyroprocessing) is partition of fuel, cladding, and fission product elements between molten LiCl-KCl and either a solid metal phase or a liquid cadmium phase. The partition reactions are described herein, and the thermodynamic basis for predicting distributions of actinides and fission products in the pyroprocess is discussed. The critical role of metal-phase activity coefficients, especially those of rare earth and the transuranic elements, is described. Measured separation factors, which are analogous to equilibrium constants but which involve concentrations rather than activities, are presented. The uses of thermodynamic calculations in process development are described, as are computer codes developed for calculating material flows and phase compositions in pyroprocessing.

Ackerman, J.P.; Johnson, T.R.

1993-10-01T23:59:59.000Z

278

Chattanooga Shale conference  

SciTech Connect

Seven papers are included, relating to the exploitation of the uranium contained in shales. One of these papers discusses the IGT Hytort process, and was previously abstracted. Separate abstracts were prepared for the remaining six papers. (DLC)

1979-11-01T23:59:59.000Z

279

(Tribology conferences and forums)  

DOE Green Energy (OSTI)

The principal meeting attended during this trip was the Japan International Tribology Conference Nagoya 1990. The conference encompassed a wide range of topics, including the tribology of ceramics, the tribology in high-performance automobiles, and many aspects of lubrication technology. Associated forums were also held on the tribology of advanced ceramics, on solid lubrication, and on automotive lubricants. Presentations made during the latter forum discussed anticipated trends in engine development and anticipated improvements in lubricants required for the next generation of engines. In addition to meetings, site visits were made to five industrial organizations to discuss ceramic tribology. Nippon Steel Corporation and Toshiba Corporation are both very active in the ceramic area, Nippon Steel from their interest in research on new materials and Toshiba from both an interest in new materials and in support of their work in electronic devices. Two engine manufacturers were also visited, Toyota Motor Corporation, and Nissan Motor Co., Ltd. These companies were somewhat reserved in their discussion of progress in the utilization of ceramics in automobile engines.

Yust, C.S.

1990-11-30T23:59:59.000Z

280

The 7. global warming international conference and expo: Abstracts  

SciTech Connect

This conference was held April 1--3, 1996 in Vienna, Austria. The purpose of this conference was to provide a multidisciplinary forum for exchange of state-of-the-art information on global warming. Topics of interest include the following: global and regional natural resource management; energy, transportation, minerals and natural resource management; industrial technology and greenhouse gas emission; strategies for the mitigation of greenhouse gas emission; greenhouse gas production/utilization and carbon budgets; strategies for promoting the understanding of global change; international policy strategy and economics; and global warming and public health. Individual papers have been processed separately for inclusion in the appropriate data bases.

NONE

1996-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

26th annual offshore technology conference, 1994 proceedings  

Science Conference Proceedings (OSTI)

This conference is the world's largest and most comprehensive technical conference and exhibition on offshore resource development. The four Proceedings volumes have been separated by major areas of interest, with relative sessions included in each volume. This Volume 3 contains information relative to offshore platforms and marine system designs. It describes both the installation and decommissioning of offshore platforms, retrofitting platforms to meet current safety standards, and technology assessments for both drilling and platform designs. Papers are also provided which describe maintenance and repair technologies for damages to platform.

Not Available

1994-01-01T23:59:59.000Z

282

Design, synthesis, and evaluation of polyhydroxamate chelators for selective complexation of actinides  

SciTech Connect

Specific chelating polymers targeted for actinides have much relevance to problems involving remediation of nuclear waste. Goal is to develop polymer supported, ion specific extraction systems for removing actinides and other hazardous metal ions from wastewaters. This is part of an effort to develop chelators for removing actinide ions such as Pu from soils and waste streams. Selected ligands are being attached to polymeric backbones to create novel chelating polymers. These polymers and other water soluble and insoluble polymers have been synthesized and are being evaluated for ability to selectively remove target metal ions from process waste streams.

Gopalan, A.; Jacobs, H.; Koshti, N.; Stark, P.; Huber, V.; Dasaradhi, L.; Caswell, W. [New Mexico State Univ., Las Cruces, NM (United States); Smith, P.; Jarvinen, G. [Los Alamos National Lab., NM (United States)

1995-08-01T23:59:59.000Z

283

Literature review of United States utilities computer codes for calculating actinide isotope content in irradiated fuel  

SciTech Connect

This paper reviews the accuracy and precision of methods used by United States electric utilities to determine the actinide isotopic and element content of irradiated fuel. After an extensive literature search, three key code suites were selected for review. Two suites of computer codes, CASMO and ARMP, are used for reactor physics calculations; the ORIGEN code is used for spent fuel calculations. They are also the most widely used codes in the nuclear industry throughout the world. Although none of these codes calculate actinide isotopics as their primary variables intended for safeguards applications, accurate calculation of actinide isotopic content is necessary to fulfill their function.

Horak, W.C.; Lu, Ming-Shih

1991-12-01T23:59:59.000Z

284

FY2011 Annual Report for the Actinide Isomer Detection Project  

Science Conference Proceedings (OSTI)

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 SNM. This project entails isomer identification and characterization and neutron population studies. This document summarizes activities from its third year - completion of the isomer identification characterization experiments and initialization of the neutron population experiments. The population and decay of the isomeric state in 235U remain elusive, although a number of candidate gamma rays have been identified. In the course of the experiments, a number of fission fragment isomers were populated and measured [Ressler 2010]. The decays from these isomers may also provide a suitable signature for the presence of fissile material. Several measurements were conducted throughout this project. This report focuses on the results of an experiment conducted collaboratively by PNNL, LLNL and LBNL in December 2010 at LBNL. The measurement involved measuring the gamma-rays emitted from an HEU target when bombarded with 11 MeV neutrons. This report discussed the analysis and resulting conclusions from those measurements. There was one strong candidate, at 1204 keV, of an isomeric signature of 235U. The half-life of the state is estimated to be 9.3 {mu}s. The measured time dependence fits the decay time structure very well. Other possible explanations for the 1204-keV state were investigated, but they could not explain the gamma ray. Unfortunately, the relatively limited statistics of the measurement limit, and the lack of understanding of some of the systematic of the experiment, limit the authors to labeling the 1204-keV gamma ray as a very strong candidate for isomeric transition in 235U. Regardless of the physics origins, the time structure of the 1204-keV gamma ray can be used as at a minimum as an indication of fissile material, if the 1204-keV gamma ray is attributed to a fission product, or it may be a unique signature for 235U, if it is a signature of an isomeric state in 235U.

Warren, Glen A.; Francy, Christopher J.; Ressler, Jennifer J.; Erikson, Luke E.; Tatishvili, Gocha; Hatarik, R.

2011-10-01T23:59:59.000Z

285

Solar energy conference, final report  

DOE Green Energy (OSTI)

The conference attendance, publicity and press coverage, brochure mailing, presentations, displays, exhibitors, management seminar checklist, and seminar evaluation by attendees are presented. Also included are the proposal for funding of the conference, the list of attendees, keynote speeches, agenda, and feedback questionnaire. (MHR)

none,

1977-05-24T23:59:59.000Z

286

Up and coming SIGWEB supported conferences  

Science Conference Proceedings (OSTI)

SIGWEB supports several specialized conferences, short courses, and workshops, as well as the Annual Hypertext Conference. SIGWEB sponsored conferences focus on timely topics in applied and computational hypertext and Web disciplines and provide a place ...

Yogesh Deshpande

2011-01-01T23:59:59.000Z

287

INTERNATIONAL OPEN GOVERNMENT DATA CONFERENCE  

NLE Websites -- All DOE Office Websites (Extended Search)

OPEN GOVERNMENT DATA CONFERENCE July 10 - 12, 2012 http://www.data.gov/conference Sponsored by Data.gov and the World Bank EMPOWERING PEOPLE "Sunlight is the best disinfectant." - Justice Louis Brandeis THE WORLD B ANK data.worldbank.org | @worldbankdata Welcome Attendees From Five Continents Around The World to the International Open Government Data Conference We Will Make History Together Thank You to our Speakers, International Guests Table of Contents: Conference Agenda Speakers Parking & Directions Restaurants Attractions p.02 p.08 p.37 p.38 p.39 InternatIonal open Government Data ConferenCe | 01 What to Know Meet Up and Make Connections Did you hear an interesting speaker? Find someone doing similar work? See a solution that you want to find out more about? Take

288

LANL Foundation conference draws teachers  

NLE Websites -- All DOE Office Websites (Extended Search)

LANL Foundation Conference Draws Teachers LANL Foundation Conference Draws Teachers Community Connections: Our link to Northern New Mexico Communities Latest Issue:Dec. 2013 - Jan. 2014 All Issues » submit LANL Foundation conference draws teachers The conference was made possible by a financial investment from LANS, LLC in the Foundation's Inquiry Science Education Consortium and from the Department of Energy. November 1, 2012 dummy image Read our archives Contacts Editor Linda Anderman Email Community Programs Office Kurt Steinhaus Email Close to 1,500 people, including teachers, principals, and others, attended the recent Los Alamos National Laboratory Foundation's 15th annual education conference. The speakers included Harry K. and Rosemary Wong on the subject of ""Effective Teaching."

289

Speciation and structural characterization of plutonium and actinide-organic complexes in surface and ground waters. Annual progress report, September 1996--September 1997  

SciTech Connect

'The authors proposed research is designed to study the association of actinides with dissolved organic complexes in subsurface waters. Actinide-humic matter associations in natural waters have been investigated previously, but the authors have postulated that much of the actinide binding activity may be supported by colloidal biopolymers. To investigate this, they are developing techniques to sample and identify organic constituents in groundwater, and to measure the Pu associated with different fractions of organic matter. Year 1 activities have focused on: (1) sampling techniques to minimize contamination and artifact formation, and to establish mass balances, (2) separation of Pu isotopes by oxidation state, and (3) analytical development of techniques for separation and identification of organic constituents from natural waters. The authors proposed research calls for field work at the Savannah River and Hanford Sites (SRS and HS, respectively). Towards this, they have been working on establishing protocols for ultra-clean (fg level) cross-flow filtration (CFF) techniques suitable for thermal ionization mass spectrometric (TIMS) analysis. A series of tests have been completed and the results have shown no Pu contamination from the CFF system was observable as long as the system is rigorously cleaned with acid, base and nano-pure water (Table 1). They have also collected a water sample from a pond near the laboratory in Woods Hole, MA to test blank conditions in the field, and to determine system mass balances. Blank levels were found to be satisfactory, and the mass balance is 100 \\261 10% for both {sup 239}Pu and {sup 240}Pu, the only two isotopes measurable in the sample. This is one of the major assurances for the success of the project because CFF will be the major sampling tool the authors will use to study natural Pu-organic complexes. Another important result from the field test is that > 80% of the dissolved Pu (based on the TIMS measurements) is in colloidal form.'

Buessler, K.O.; Repeta, D.J.

1997-01-01T23:59:59.000Z

290

Speciation and structural characterization of plutonium and actinide-organic complexes in surface and ground waters. Annual progress report, September 1996--September 1997  

SciTech Connect

'The authors proposed research is designed to study the association of actinides with dissolved organic complexes in subsurface waters. Actinide-humic matter associations in natural waters have been investigated previously, but they have postulated that much of the actinide binding activity may be supported by colloidal biopolymers. To investigate this, they are developing techniques to sample and identify organic constituents in groundwater, and to measure the Pu associated with different fractions of organic matter. Year 1 activities have focused on: (1) sampling techniques to minimize contamination and artifact formation, and to establish mass balances, (2) separation of Pu isotopes by oxidation state, and (3) analytical development of techniques for separation and identification of organic constituents from natural waters. Their proposed research calls for field work at the Savannah River and Hanford Sites (SRS and HS, respectively). Towards this, they have been working on establishing protocols for ultra-clean (fg level) cross-flow filtration (CFF) techniques suitable for thermal ionization mass spectrometric (TIMS) analysis. A series of tests have been completed and the results have shown no Pu contamination from the CFF system was observable as long as the system is rigorously cleaned with acid, base and nano-pure water. They have also collected a water sample from a pond near the laboratory in Woods Hole, MA to test blank conditions in the field, and to determine system mass balances. Blank levels were found to be satisfactory, and the mass balance is 100--210% for both {sup 239}Pu and {sup 240}Pu, the only two isotopes measurable in the sample. This is one of the major assurances for the success of the project because CFF will be the major sampling tool the authors will use to study natural Pu-organic complexes. Another important result from the field test is that > 80 % of the dissolved Pu (based on the TIMS measurements) is in colloidal form.'

Buessler, K.O.; Repeta, D.J.

1997-12-31T23:59:59.000Z

291

Fission Cross Section Measurements of Actinides at LANSCE  

Science Conference Proceedings (OSTI)

Fission cross sections of a range of actinides have been measured at the Los Alamos Neutron Science Center (LANSCE) in support of nuclear energy applications. By combining measurement at two LANSCE facilities, Lujan Center and the Weapons Neutron Research center (WNR), differential cross sections can be measured from sub-thermal energies up to 200 MeV. Incident neutron energies are determined using the time-of-flight method, and parallel-plate ionization chambers are used to measure fission cross sections relative to the 235U standard. Recent measurements include the 233, 238U, 239-242Pu, and 243Am neutron-induced fission cross sections. In this paper preliminary results for fission cross sections of 243Am and 233U will be presented.

F. Tovesson; A. B. Laptev; T. S. Hill

2011-08-01T23:59:59.000Z

292

Flammability Analysis For Actinide Oxides Packaged In 9975 Shipping Containers  

SciTech Connect

Packaging options are evaluated for compliance with safety requirements for shipment of mixed actinide oxides packaged in a 9975 Primary Containment Vessel (PCV). Radiolytic gas generation rates, PCV internal gas pressures, and shipping windows (times to reach unacceptable gas compositions or pressures after closure of the PCV) are calculated for shipment of a 9975 PCV containing a plastic bottle filled with plutonium and uranium oxides with a selected isotopic composition. G-values for radiolytic hydrogen generation from adsorbed moisture are estimated from the results of gas generation tests for plutonium oxide and uranium oxide doped with curium-244. The radiolytic generation of hydrogen from the plastic bottle is calculated using a geometric model for alpha particle deposition in the bottle wall. The temperature of the PCV during shipment is estimated from the results of finite element heat transfer analyses.

2013-03-21T23:59:59.000Z

293

Aqueous complexes in f-element separation science  

SciTech Connect

Powerful and/or selective extractant molecules/sorbents are a necessary component of an efficient ion exchange or solvent extraction separation process. However, selectivity in extraction and efficiency in process design often rely on reactions occurring in or moderated by the aqueous medium. The focus of this report in on the role of the aqueous phase and reaction that occur in aquo in defining separation efficiency and metal ion selectivity. As the programmatic emphasis is on actinide solution chemistry, the separations chemistry of the f-elements will be used to illustrate the principal role of aqueous chemistry in separation science. Most of the arguments developed apply to metal ion separations chemistry and processes in general. The discussion will consider the application of aqueous complexants, incorporation of aqueous complexants into the extracted complex, and the effect of properties of the aqueous medium on separation efficiency and selectivity. Several historically important separations processes will be considered along with recent efforts in these laboratories to design and characterize new water soluble complexants for improved f-element separations.

Nash, K.L. [Argonne National Lab., IL (United States). Chemistry Div.

1997-11-01T23:59:59.000Z

294

Delayed neutron measurements from fast fission of actinide waste isotopes  

E-Print Network (OSTI)

A study was performed to determine the delayed neutron emission properties from fast fission of several actinide waste isotopes. The specific isotopes evaluated were U-235, Np-237, and Am-243. A calculational technique based on the microscopic method was used to predict initial guesses for the delayed neutron parameters (group decay constants and yields). Based on these calculations, an alternate "seven-group" structure, in contrast to the traditional "six-group" structure used previously, was suggested which would yield a superior fit to the measured data. A series of measurements were performed to test the hypothesis suggested by this alternate group structure. Using a set of highly purified actinide samples (provided by Oak Ridge National Laboratory), the delayed neutron emission decay constants and yields for six groups of the "seven-group" structure were measured for U-235, Np-237, and Am-243. These experiments were performed using the Texas A&M University Nuclear Science Center Reactor, a quick pneumatic transfer system, an integrated computer control and counting system, and a specially designed in-core irradiation device. The values for the total delayed neutron yield (per 100 fissions) from fast-neutron induced fission of U-235, Np237, and Am-243 were determined to be 1.67 ?0.08, 1.14 ?0.07, 0.86 ?0.05, respectively. The newly measured values were compared with other values recommended by Keepin et al., Waldo et al., Saleh et al., and Brady and England. Good agreement was found in all cases. The "seven-group" structure was shown to yield a superior fit to the measured data, as well as, provide a more direct correlation between delayed neutron groups and their associated delayed neutron precursors.

Charlton, William S.

1997-01-01T23:59:59.000Z

295

Carbon Sequestration Conference | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Carbon Sequestration Conference Carbon Sequestration Conference May 9, 2006 - 10:37am Addthis Remarks Prepared for Energy Secretary Samuel Bodman Thank you. It's a pleasure for me...

296

System manual for conference attendance data file  

SciTech Connect

This manual describes a system which was designed to help conference planners with the record keeping aspect of conference attendance and speaker data.

Celoni, C.L.

1976-03-01T23:59:59.000Z

297

Press Conference Call Tomorrow: Agriculture Secretary Vilsack...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Press Conference Call Tomorrow: Agriculture Secretary Vilsack and Energy Secretary Chu to Discuss Efforts to Reduce U.S. Oil Dependence Press Conference Call Tomorrow: Agriculture...

298

Energy Storage Systems 2010 Update Conference Presentations ...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0 Update Conference Presentations - Day 1, Session 2 Energy Storage Systems 2010 Update Conference Presentations - Day 1, Session 2 The U.S. DOE Energy Storage Systems Program...

299

Conference of Mayors | Open Energy Information  

Open Energy Info (EERE)

of Mayors Jump to: navigation, search Name Conference of Mayors Place Washington, DC Website http:www.conferenceofmayors. References Conference of Mayors1 Information...

300

Transportation Protocols Working Group First Conference Call...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Call March 1, 1999 Conference Call Summary The first conference call of the Transportation External Coordination Working Group (TECWG) DOE Transportation Protocols Working...

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Patent Attorney Conference | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Patent Attorney Conference Patent Attorney Conference September 13-14, 2011 Washington, DC Slides Presentations Stanford v. Roche, Microsoft, and other Supreme Court Cases Patent...

302

Conference Center and APS Site Activity Coordination  

NLE Websites -- All DOE Office Websites (Extended Search)

and Emergency Management Database Maintenance Personnel Conference Center and APS Site Activity Coordination Locations Conference Center - E1100E1200, Auditorium, Gallery A1100...

303

Proceedings of the 1991 Oil Heat Technology Conference and Workshop  

Science Conference Proceedings (OSTI)

This Conference, which was the sixth held since 1984, is a key technology-transfer activity supported by the ongoing Combustion Equipment Technology program at BNL, and is aimed at providing a forum for the exchange of information among international researchers, engineers, manufacturers, and marketers of oil-fired space-conditioning equipment. The objectives of the Conference were to: Identify and evaluate the state-of-the-art and recommend; new initiatives to satisfy consumer needs cost-effectively, reliably, and safely; Foster cooperation among federal and industrial representatives with the common goal of national security via energy conservation. The 1991 Oil Technology Conference comprised: (a) two plenary sessions devoted to presentations and summations by public and private sector representatives from the United States, Europe, and Canada; and, (b) four workshops which focused on mainstream issues in oil-heating technology. Selected papers have been processed separately for inclusion in the Energy Science and Technology Database.

McDonald, R.J.

1992-07-01T23:59:59.000Z

304

Actinide transmutation; fission or fusion reactors studies: a review. [In-core transmutation  

SciTech Connect

Actinide transmutation in fission or fusion reactors is considered as a possible method of radioactive waste processing. A brief summary is presented of transmutation studies completed or in progress. (DG)

Croff, A.G.

1976-01-01T23:59:59.000Z

305

Fission of actinides and superheavy nuclei: covariant density functional theory perspective  

E-Print Network (OSTI)

The current status of the application of covariant density functional theory to the description of fission barriers in actinides and superheavy nuclei is reviewed. The achievements and open problems are discussed.

A. V. Afanasjev

2013-03-05T23:59:59.000Z

306

Analysis of the MIT research reactor fission product and actinide radioactivity inventories  

E-Print Network (OSTI)

The current analysis of the MITR core radioactivity inventory eliminates unnecessary assumptions made in previous estimates of the inventory, and revises the list of contributory isotopes to include all actinide and fission ...

Kennedy, William B. (William Blake), 1979-

2004-01-01T23:59:59.000Z

307

Fifteenth combustion research conference  

Science Conference Proceedings (OSTI)

The BES research efforts cover chemical reaction theory, experimental dynamics and spectroscopy, thermodynamics of combustion intermediates, chemical kinetics, reaction mechanisms, combustion diagnostics, and fluid dynamics and chemically reacting flows. 98 papers and abstracts are included. Separate abstracts were prepared for the papers.

NONE

1993-06-01T23:59:59.000Z

308

Solid-State Lighting: Conferences and Meetings  

NLE Websites -- All DOE Office Websites (Extended Search)

Conferences and Meetings to Conferences and Meetings to someone by E-mail Share Solid-State Lighting: Conferences and Meetings on Facebook Tweet about Solid-State Lighting: Conferences and Meetings on Twitter Bookmark Solid-State Lighting: Conferences and Meetings on Google Bookmark Solid-State Lighting: Conferences and Meetings on Delicious Rank Solid-State Lighting: Conferences and Meetings on Digg Find More places to share Solid-State Lighting: Conferences and Meetings on AddThis.com... Conferences & Meetings Past Conferences Presentations Publications Webcasts Videos Tools Conferences and Meetings DOE organizes three annual workshops to bring together a diverse gathering of participants-government, industry, academia, research institutions, energy efficiency organizations, utilities, retailers, and designers-to

309

Clean Cities: Clean Cities Conferences and Workshops  

NLE Websites -- All DOE Office Websites (Extended Search)

Conferences and Workshops Conferences and Workshops to someone by E-mail Share Clean Cities: Clean Cities Conferences and Workshops on Facebook Tweet about Clean Cities: Clean Cities Conferences and Workshops on Twitter Bookmark Clean Cities: Clean Cities Conferences and Workshops on Google Bookmark Clean Cities: Clean Cities Conferences and Workshops on Delicious Rank Clean Cities: Clean Cities Conferences and Workshops on Digg Find More places to share Clean Cities: Clean Cities Conferences and Workshops on AddThis.com... Conferences & Workshops Clean Cities 20th Anniversary Electric Vehicle Community Readiness Stakeholder Summit Waste-to-Wheels Plug-In Vehicle & Infrastructure Fuel & Vehicle Strategy Clean Cities Conferences and Workshops Clean Cities offers conferences and workshops about alternative fuels and

310

House Conference Report 106-1005, NIST Report Language  

Science Conference Proceedings (OSTI)

"Taken from House Conference Report 106-1005 FY 2001 Appropriations bill Conference Report…". NATIONAL INSTITUTE ...

2010-10-05T23:59:59.000Z

311

House Conference Report 108-10, General Provisions  

Science Conference Proceedings (OSTI)

"Taken from House Conference Report 108-10 FY 2003 Omnibus Appropriations Bill Conference Report…". GENERAL ...

2010-10-05T23:59:59.000Z

312

Journal and Conference Abbreviations for NIST Time and ...  

Science Conference Proceedings (OSTI)

... ICOLS Conf. Conference. Proceedings of International Society for Optical Engineering (SPIE), Proc. SPIE Conf. Conference. ...

2010-10-05T23:59:59.000Z

313

Phase Formation in Actinide Alloys: Why Ab Initio?  

Science Conference Proceedings (OSTI)

Conference Tools for 2011 TMS Annual Meeting & Exhibition ... We show that CALPHAD, combined with appropriate first-principles ... Work performed under the auspices of the U.S. DOE by LLNL under contract DE-AC52-07NA27344. ... A Heat Management Model for Hardness Uniformity of Multi-Pass Laser Heat ...

314

Calix 2007:9th International Conference on Calixarene Chemistry  

SciTech Connect

The DOE funds helped support an International Conference, Calix 2007, whose focus was on Supramolecular Chemistry. The conference was held at the University of Maryland from August 6-9, 2007 (Figure 1). The conference website is at www.chem.umd.edu/Conferences/Calix2007. This biannual conference had previously been held in the Czech Republic (2005), Canada (2003), Netherlands (2001), Australia (1999), Italy (1997), USA (Fort Worth, 1995) Japan (1993) and Germany (1991). Calixarenes are cup-shaped compounds that are a major part of Supramolecular Chemistry, for which Cram, Lehn and Pederson were awarded a Nobel Prize 20 years ago. Calixarene chemistry has expanded greatly in the last 2 decades, as these compounds are used in synthetic and mechanistic chemistry, separations science, materials science, nanoscience and biological chemistry. The organizing committee was quite happy that Calix 2007 encompassed the broad scope and interdisciplinary nature of the field. Our goal was to bring together leading scientists interested in calixarenes, molecular recognition, nanoscience and supramolecular chemistry. We believe that new research directions and collaborations resulted from an exchange of ideas between conferees. This grant from the DOE was crucial toward achieving that goal, as the funds helped cover some of the registration and accommodations costs for the speakers.

Jeffery Davis

2011-09-09T23:59:59.000Z

315

World Conference on Fabric and Home Care: Singapore 2012  

Science Conference Proceedings (OSTI)

Archive of the 2012 World Conference on Fabric and Home Care. World Conference on Fabric and Home Care: Singapore 2012 Other Conference Archives abstracts aocs conference Conference Archives courses fats industries meeting Meeting Archives meetings netwo

316

2009 conference flyer.cdr  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2900 2900 Van Ness Street, NW Washington, D.C. 300 Army-Navy Drive Crystal City, Virginia 22202 and Doubletree Hotel - Crystal City Brought to you by: National Small Town Alliance U.S. Department of Energy U.S. Department of Agriculture Howard University School of Law U.S. Environmental Protection Agency · · · · · · · · · · http://www.LM.doe.gov/env_justice/conference.htm The State of Environmental Justice in America 2009 Conference May 27-29, 2009 May 27-29, 2009 Environmental Justice Definition and Conference Details on Back. About Environmental Justice What is Environmental Justice? The State of Environmental Justice in America 2009 Conference Environmental justice is the fair treatment and meaningful involvement of all people-regardless of race, ethnicity, income or education level-in environmental decision-making. It has been more than 25 years since the

317

2010 conference flier.cdr  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

State State of Environmental Justice in America 2010 Conference May 12-14, 2010 May 12-14, 2010 Environmental Justice definition and conference details on back For more information contact Melinda Downing, Environmental Justice Program Manager, at or John Rosenthall, Conference Coordinator at . melinda.downing@hq.doe.gov ejinamerica@hotmail.com Howard University School of Law 2900 Van Ness Street, NW Washington, D.C. 775 12th Street NW Washington, DC 20005 and Washington Marriott at Metro Center About Environmental Justice What Is Environmental Justice? The State of Environmental Justice in America 2010 Conference Environmental justice is the fair treatment and meaningful involvement of all people-regardless of race, ethnicity, income or education level-in environmental decision-making. It has been more than 25 years since the Warren County, North Carolina, protest

318

Manhattan Project: Solvay Physics Conference  

Office of Scientific and Technical Information (OSTI)

SOLVAY PHYSICS CONFERENCE SOLVAY PHYSICS CONFERENCE Brussels, Belgium (October 1933) Resources > Photo Gallery Solvay Physics Conference, Brussels, 1933 The Solvay Physics Conference, held in Brussels, Belgium, October 22-29, 1933. Attendees included two future key Manhattan Project scientists (Fermi and Lawrence), the future head of the Nazi atomic bomb program (Heisenberg), and numerous leading pre-war physicists. A partial list of those attending: Niels Bohr (seated, third from left) James Chadwick (seated, farthest right) J. B. Cockroft (middle row, third from right) Marie Curie (seated, fifth from left) Enrico Fermi (middle row, fifth from left) Werner Heisenberg (middle row, fourth from left) Ernest O. Lawrence (back row, second from right) Lise Meitner (seated, second from right)

319

Quark Matter 2004 Conference Hotel  

NLE Websites -- All DOE Office Websites (Extended Search)

as the conference Hotel. It is adjacent to the Oakland Convention Center where all Quark Matter talks will be held. Quark Matter attendees can get a reduced price of 126...

320

Winter Fuels Outlook Conference 2010  

Reports and Publications (EIA)

This presentation at the 2010 Winter Fuels Outlook Conference in Washington, DC, outlined EIA's current forecast for U.S. crude oil, distillate, natural gas, propane and gasoline supply, demand, and markets over the coming winter season.

2010-10-13T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

NETL Publications: Previous Conference Proceedings  

NLE Websites -- All DOE Office Websites (Extended Search)

University Alliance Workshop Sept. 12 Air Quality III Conference Aug. 5 Rocky Mountain E&P Technology Transfer Workshop July 23-24 Electric Utilities and Water: Emerging Issues...

322

EPS Global International Cancer Conference  

NLE Websites -- All DOE Office Websites (Extended Search)

Sept.10-12th, 2010 Suzhou, China Welcome Message Dear Colleagues and Friends, It is my pleasure to announce that EPS Global International Cancer Conference will be held on...

323

The National Information Systems Security Conference ...  

Science Conference Proceedings (OSTI)

The National Information Systems Security Conference announces its Keynote and Banquet Speakers. August Bequai, Esq ...

1996-10-28T23:59:59.000Z

324

Text Analysis Conference (TAC) Related Publications  

Science Conference Proceedings (OSTI)

... Proceedings of the 3rd IEEE International Conference on Multimedia Communications, Services and Security, Krakow, Poland. ...

325

Text REtrieval Conference (TREC) System Description  

Science Conference Proceedings (OSTI)

Text REtrieval Conference (TREC) System Description. Organization Name: Los Alamos National Laboratory, Run ID: lanl981. ...

326

New Mexico Regional SBIR/STTR Conference  

New Mexico Regional SBIR/STTR Conference: Small Business Innovation Research / Small Business Technology Transfer

327

2010 Kansas Field Conference June 24, 2010  

E-Print Network (OSTI)

2010 Kansas Field Conference June 2­4, 2010 Flint Hills, Cross Timbers, and Verdigris River Valley 2 3 4 7 5 6 8 9 10 #12;2010 Field Conference Flint Hills, Cross Timbers, and Verdigris River Valley..........................................................................................1 - 2 Kansas Field Conference 2010 Field Conference Overview "Flint Hills, Cross Timbers

Peterson, Blake R.

328

International Conference Synchrotron Radiation Instrumentation SRI `94  

SciTech Connect

This report contains abstracts for the international conference on Synchrotron Radiation Instrumentation at Brookhaven National Laboratory.

Not Available

1994-10-01T23:59:59.000Z

329

Plutonium Chemistry in the UREX+ Separation Processes  

SciTech Connect

The project "Plutonium Chemistry in the UREX+ Separation Processes” is led by Dr. Alena Paulenova of Oregon State University under collaboration with Dr. George Vandegrift of ANL and Dr. Ken Czerwinski of the University of Nevada at Las Vegas. The objective of the project is to examine the chemical speciation of plutonium in UREX+ (uranium/tributylphosphate) extraction processes for advanced fuel technology. Researchers will analyze the change in speciation using existing thermodynamics and kinetic computer codes to examine the speciation of plutonium in aqueous and organic phases. They will examine the different oxidation states of plutonium to find the relative distribution between the aqueous and organic phases under various conditions such as different concentrations of nitric acid, total nitrates, or actinide ions. They will also utilize techniques such as X-ray absorbance spectroscopy and small-angle neutron scattering for determining plutonium and uranium speciation in all separation stages. The project started in April 2005 and is scheduled for completion in March 2008.

ALena Paulenova; George F. Vandegrift, III; Kenneth R. Czerwinski

2009-10-01T23:59:59.000Z

330

9. international mouse genome conference  

SciTech Connect

This conference was held November 12--16, 1995 in Ann Arbor, Michigan. The purpose of this conference was to provide a multidisciplinary forum for exchange of state-of-the-art information on genetic mapping in mice. This report contains abstracts of presentations, focusing on the following areas: mutation identification; comparative mapping; informatics and complex traits; mutagenesis; gene identification and new technology; and genetic and physical mapping.

NONE

1995-12-31T23:59:59.000Z

331

Fourth DOE Natural Phenomena Hazards Mitigation Conference: Proceedings. Volume 1  

SciTech Connect

This conference allowed an interchange in the natural phenomena area among designers, safety professionals, and managers. The papers presented in Volume I of the proceedings are from sessions I - VIII which cover the general topics of: DOE standards, lessons learned and walkdowns, wind, waste tanks, ground motion, testing and materials, probabilistic seismic hazards, risk assessment, base isolation and energy dissipation, and lifelines and floods. Individual papers are indexed separately. (GH)

Not Available

1993-12-31T23:59:59.000Z

332

The Joint Actinide Shock Physics Experimental Research Facility at the Nevada National Security Site, OAS-L-12-05  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Joint Actinide Shock Physics Joint Actinide Shock Physics Experimental Research Facility at the Nevada National Security Site OAS-L-12-05 April 2012 Department of Energy Washington, DC 20585 April 23, 2012 MEMORANDUM FOR THE MANAGER, NEVADA SITE OFFICE FROM: David Sedillo, Director Western Audits Division Office of Inspector General SUBJECT: INFORMATION: Audit Report on "The Joint Actinide Shock Physics Experimental Research Facility at the Nevada National Security Site" BACKGROUND The Department of Energy, National Nuclear Security Administration's, Joint Actinide Shock Physics Experimental Research (JASPER) facility plays an integral role in the certification of the Nation's nuclear weapons stockpile by providing a method to generate and measure data

333

LM Training & Conferences | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

LM Training & Conferences LM Training & Conferences LM Training & Conferences Current Training and Conferences Attended by LM Employees Solar Power International Conference (Chicago, IL; October 21-24, 2013) 2014 National Environmental Justice Conference and Training Program Save-the-Date (English) 2014 National Environmental Justice Conference and Training Program Save-the-Date(Spanish) Past Training and Conferences Attended by LM Employees IAEA Workshop, Note: There is also a write up in the LM Quarterly Program Update. Alaska Forum on Environment (Anchorage, AK; February 2-4 2013) Waste Management Conference (Phoenix, AZ; February 24-28, 2013) National Adaptation Forum (Denver, CO; April 2-3, 2013) National Environmental Justice Conference (Washington, DC; April 3-5, 2013)

334

Enhancing BWR Proliferation Resistance Fuel with Minor Actinides  

SciTech Connect

To reduce spent fuel for storage and enhance the proliferation resistance for the intermediate-term, there are two major approaches (a) increase the discharged spent fuel burnup in the advanced light water reactor- LWR (Gen-III Plus), which not only can reduce the spent fuel for storage, but also increase the 238Pu isotopes ratio to enhance the proliferation resistance, and (b) use of transuranic nuclides (237Np and 241Am) in the high burnup fuel, which can drastically increase the proliferation resistance isotope ratio of 238Pu/Pu. For future advanced nuclear systems, minor actinides (MA) are viewed more as a resource to be recycled, and transmuted to less hazardous and possibly more useful forms, rather than simply disposed of as a waste stream in an expensive repository facility. As a result, MAs play a much larger part in the design of advanced systems and fuel cycles, not only as additional sources of useful energy, but also as direct contributors to the reactivity control of the systems into which they are incorporated. In the study, a typical boiling water reactor (BWR) fuel unit lattice cell model with UO2 fuel pins will be used to investigate the effectiveness of minor actinide reduction approach (MARA) for enhancing proliferation resistance and improving the fuel cycle performance in the intermediate-term goal for future nuclear energy systems. To account for the water coolant density variation from the bottom (0.76 g/cm3) to the top (0.35 g/cm3) of the core, the axial coolant channel and fuel pin were divided to 24 nodes. The MA transmutation characteristics at different elevations were compared and their impact on neutronics criticality discussed. The concept of MARA, which involves the use of transuranic nuclides (237Np and/or 241Am), significantly increases the 238Pu/Pu ratio for proliferation resistance, as well as serves as a burnable absorber to hold-down the initial excess reactivity. It is believed that MARA can play an important role in atoms for peace and the intermediate-term of nuclear energy reconnaissance.

Gray S. Chang

2009-03-01T23:59:59.000Z

335

Enhancing VVER Annular Proliferation Resistance Fuel with Minor Actinides  

SciTech Connect

Key aspects of the Global Nuclear Energy Partnership (GNEP) are to significantly advance the science and technology of nuclear energy systems and the Advanced Fuel Cycle (AFC) program. The merits of nuclear energy are the high-density energy, and low environmental impacts i.e. almost zero greenhouse gas emission. Planned efforts involve near-term and intermediate-term improvements in fuel utilization and recycling in current LWR as well as the longer-term development of new nuclear energy systems that offer much improved fuel utilization and proliferation resistance, along with continued advances in operational safety. The challenges are solving the energy needs of the world, protection against nuclear proliferation, the problem of nuclear waste, and the global environmental problem. To reduce the spent fuel for storage and enhance the proliferation resistance for the intermediate-term, there are two major approaches (a) increase the discharged spent fuel burnup in the advanced LWR (Gen-III Plus), which not only can reduce the spent fuel for storage, but also increase the 238Pu and 240Pu isotopes ratio to enhance the proliferation resistance, (b) use of transuranic nuclides (237Np and 241Am) in the high burnup fuel, which can drastically increase the proliferation resistance isotope 238Pu /Pu ratio. For future advanced nuclear systems, the minor actinides are viewed more as a resource to be recycled, or transmuted to less hazardous and possibly more useful forms, rather than simply as a waste stream to be disposed of in expensive repository facilities. In this paper, a typical pressurized water reactor (PWR) VVER-1000 annular fuel unit lattice cell model with UO2 fuel pins will be used to investigate the effectiveness of minor actinide reduction approach (MARA) for enhancing proliferation resistance and improving the fuel cycle performance. We concluded that the concept of MARA, involves the use of transuranic nuclides (237Np and/or 241Am), can not only drastically increase the 238Pu/Pu ratio for proliferation resistance, but also can serve as a burnable absorber to hold-down the initial excess reactivity. It is believed that MARA can play an important role in atoms for peace and the intermediate term of nuclear energy reconnaissance.

G. S. Chang

2007-06-01T23:59:59.000Z

336

Americium separation from nuclear fuel dissolution using higher oxidation states.  

Science Conference Proceedings (OSTI)

Much of the complexity in current AFCI proposals is driven by the need to separate the minor actinides from the lanthanides. Partitioning and recycling Am, but not Cm, would allow for significant simplification because Am has redox chemistry that may be exploited while Cm does not. Here, we have explored methods based on higher oxidation states of Am (AmV and AmVI) to partition Am from the lanthanides. In a separate but related approach we have also initiated an investigation of the utility of TRUEX Am extraction from thiocyanate solution. The stripping of loaded TRUEX by Am oxidation or SCN- has not yet proved successful; however, the partitioning of inextractable AmV by TRUEX shows promise.

Bruce J. Mincher

2009-09-01T23:59:59.000Z

337

Proceedings: National conference on environmental externalities  

Science Conference Proceedings (OSTI)

This report is the proceedings of the National Conference on Environmental Externalities. A environmental externality is the environmental impact of a process or a plant that society must endure. It is a social cost and is paid, but not by the company who produced it or the company`s customers who endure it. The main purpose of this report is to gather the many designs and ideas of how and why to internalize the externalities into the pricing systems of the public utility commissions, especially that of the electric utilities. Economic and sociological aspects of the internalization of these externalities are given in these proceedings. Individual papers are processed separately for databases. (MB)

Not Available

1990-12-31T23:59:59.000Z

338

Tenth oil recovery conference  

SciTech Connect

The Tertiary Oil Recovery Project is sponsored by the State of Kansas to introduce Kansas producers to the economic potential of enhanced recovery methods for Kansas fields. Specific objectives include estimation of the state-wide tertiary oil resource, identification and evaluation of the most applicable processes, dissemination of technical information to producers, occasional collaboration on recovery projects, laboratory studies on Kansas applicable processes, and training of students and operators in tertiary oil recovery methods. Papers have been processed separately for inclusion on the data base.

Sleeper, R. (ed.)

1993-01-01T23:59:59.000Z

339

PROCEEDINGS OF THE UNIVERSITY SUBCRITICAL ASSEMBLIES CONFERENCE HELD AT GATLINBURG, TENNESSEE, AUGUST 28-30, 1961  

SciTech Connect

Seventeen papers are included which were presented at the 1961 University Subcritical Assemblies conference, whose purpose was to review the status, significance and service of various subcritical assemblies for college and university research and teaching programs in nuclear science and engineering. Separate abstracts were prepared for 15 of the papers; the other two are a summary of the conference and a banquet address on the relationship between the national laboratory and the university. (D.L.C.)

1962-01-01T23:59:59.000Z

340

Proceedings: Second Annual Pacific Northwest Alternative and Renewable Energy Resources Conference.  

DOE Green Energy (OSTI)

Papers presented at the conference are published in this volume. The purpose of the conference was to solicit regional cooperation in the promoting of near-term development of such alternative and renewable energy resources in the Pacific Northwest as: cogeneration; biomass; wind; small hydro; solar end-use applications; and geothermal direct heat utilization. Separate abstracts of selected papers were prepared for inclusion in the Energy Data Base.

None

1980-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Demonstration of the TRUEX process for partitioning of actinides from actual ICPP tank waste using centrifugal contactors in a shielded cell facility  

Science Conference Proceedings (OSTI)

TRUEX is being evaluated at Idaho Chemical Processing Plant (ICPP) for separating actinides from acidic radioactive waste stored at ICPP; efforts have culminated in a recent demonstration with actual tank waste. A continuous countercurrent flowsheet test was successfully completed at ICPP using waste from tank WM-183. This demonstration was performed using 24 states of 2-cm dia centrifugal contactors in the shielded hot cell at the ICPP Remote Analytical Laboratory. The flowsheet had 8 extraction stages, 5 scrub stages, 6 strip stages, 3 solvent wash stages, and 2 acid rinse stages. A centrifugal contactor stage in the scrub section was not working during testing, and the scrub feed (aqueous) solution followed the solvent into the strip section, eliminating the scrub section in the flowsheet. An overall removal efficiency of 99.97% was obtained for the actinides, reducing the activity from 457 nCi/g in the feed to 0.12 nCi/g in the aqueous raffinate, well below the NRC Class A LLW requirement of 10 nCi/g for non-TRU waste.The 0.04 M HEDPA strip section back-extracted 99.9998% of the actinide from the TRUEX solvent. Removal efficiencies of >99. 90, 99.96, 99.98, >98.89, 93.3, and 89% were obtained for {sup 241}Am, {sup 238}Pu, {sup 239}Pu, {sup 235}U, {sup 238}U, and {sup 99}Tc. Fe was partially extracted by the TRUEX solvent, resulting in 23% of the Fe exiting in the strip product. Hg was also extracted by the TRUEX solvent (73%) and stripped from the solvent in the 0.25 M Na2CO3 wash section. Only 1.4% of the Hg exited with the high activity waste strip product.

Law, J.D.; Brewer, K.N.; Herbst, R.S.; Todd, T.A.

1996-09-01T23:59:59.000Z

342

Demonstration of an optimized TRUEX flowsheet for partitioning of actinides from actual ICPP sodium-bearing waste using centrifugal contactors in a shielded cell facility  

Science Conference Proceedings (OSTI)

The TRUEX process is being evaluated at the Idaho Chemical Processing Plant (ICPP) for the separation of the actinides from acidic radioactive wastes stored at the ICPP. These efforts have culminated in recent demonstrations of the TRUEX process with actual tank waste. The first demonstration was performed in 1996 using 24 stages of 2-cm diameter centrifugal contactors and waste from tank WM-183. Based on the results of this flowsheet demonstration, the flowsheet was optimized and a second flowsheet demonstration was performed. This test also was performed using 2-cm diameter centrifugal contactors and waste from tank WM-183. However, the total number of contactor stages was reduced from 24 to 20. Also, the concentration of HEDPA in the strip solution was reduced from 0.04 M to 0.01 M in order to minimize the amount of phosphate in the HLW fraction, which would be immobilized into a glass waste form. This flowsheet demonstration was performed using centrifugal contactors installed in the shielded hot cell at the ICPP Remote Analytical Laboratory. The flowsheet tested consisted of six extraction stages, four scrub stages, six strip stages, two solvent was stages, and two acid rinse stages. An overall removal efficiency of 99.79% was obtained for the actinides. As a result, the activity of the actinides was reduced from 540 nCi/g in the feed to 0.90 nCi/g in the aqueous raffinate, which is well below the NRC Class A LLW requirement of 10 nCi/g for non-TRU waste. Removal efficiencies of 99.84%, 99.97%, 99.97%, 99.85%, and 99.76% were obtained for {sup 241}Am, {sup 238}Pu, {sup 239}Pu, {sup 235}U, and {sup 238}U, respectively.

Law, J.D.; Brewer, K.N.; Herbst, R.S.; Todd, T.A.; Olson, L.G.

1998-01-01T23:59:59.000Z

343

RAPID SEPARATION METHOD FOR EMERGENCY WATER AND URINE SAMPLES  

SciTech Connect

The Savannah River Site Environmental Bioassay Lab participated in the 2008 NRIP Emergency Response program administered by the National Institute for Standards and Technology (NIST) in May, 2008. A new rapid column separation method was used for analysis of actinides and {sup 90}Sr the NRIP 2008 emergency water and urine samples. Significant method improvements were applied to reduce analytical times. As a result, much faster analysis times were achieved, less than 3 hours for determination of {sup 90}Sr and 3-4 hours for actinides. This represents a 25%-33% improvement in analysis times from NRIP 2007 and a {approx}100% improvement compared to NRIP 2006 report times. Column flow rates were increased by a factor of two, with no significant adverse impact on the method performance. Larger sample aliquots, shorter count times, faster cerium fluoride microprecipitation and streamlined calcium phosphate precipitation were also employed. Based on initial feedback from NIST, the SRS Environmental Bioassay Lab had the most rapid analysis times for actinides and {sup 90}Sr analyses for NRIP 2008 emergency urine samples. High levels of potential matrix interferences may be present in emergency samples and rugged methods are essential. Extremely high levels of {sup 210}Po were found to have an adverse effect on the uranium results for the NRIP-08 urine samples, while uranium results for NRIP-08 water samples were not affected. This problem, which was not observed for NRIP-06 or NRIP-07 urine samples, was resolved by using an enhanced {sup 210}Po removal step, which will be described.

Maxwell, S.; Culligan, B.

2008-08-27T23:59:59.000Z

344

Modeling Solute Thermokinetics in LiCI-KCI Molten Salt for Nuclear Waste Separation  

SciTech Connect

Recovery of actinides is an integral part of a closed nuclear fuel cycle. Pyrometallurgical nuclear fuel recycling processes have been developed in the past for recovering actinides from spent metallic and nitride fuels. The process is essentially to dissolve the spent fuel in a molten salt and then extract just the actinides for reuse in a reactor. Extraction is typically done through electrorefining, which involves electrochemical reduction of the dissolved actinides and plating onto a cathode. Knowledge of a number of basic thermokinetic properties of salts and salt-fuel mixtures is necessary for optimizing present and developing new approaches for pyrometallurgical waste processing. The properties of salt-fuel mixtures are presently being studied, but there are so many solutes and varying concentrations that direct experimental investigation is prohibitively time consuming and expensive (particularly for radioactive elements like Pu). Therefore, there is a need to reduce the number of required experiments through modeling of salt and salt-fuel mixture properties. This project will develop first-principles-based molecular modeling and simulation approaches to predict fundamental thermokinetic properties of dissolved actinides and fission products in molten salts. The focus of the proposed work is on property changes with higher concentrations (up to 5 mol%) of dissolved fuel components, where there is still very limited experimental data. The properties predicted with the modeling will be density, which is used to assess the amount of dissolved material in the salt; diffusion coefficients, which can control rates of material transport during separation; and solute activity, which determines total solubility and reduction potentials used during electrorefining. The work will focus on La, Sr, and U, which are chosen to include the important distinct categories of lanthanides, alkali earths, and actinides, respectively. Studies will be performed using LiCl-KCl salt at the eutectic composition (58 mol% LiCl, 42 mol% KCl), which is used for treating spent EBR-II fuel. The same process being used for EBRII fuel is currently being studied for widespread international implementation. The methods will focus on first-principles and first- principles derived interatomic potential based simulations, primarily using molecular dynamics. Results will be validated against existing literature and parallel ongoing experimental efforts. The simulation results will be of value for interpreting experimental results, validating analytical models, and for optimizing waste separation by potentially developing new salt configurations and operating conditions.

Morgan, Dane; Eapen, Jacob

2013-10-01T23:59:59.000Z

345

Actinide recycle potential in the IFR (Integral Fast Reactor)  

SciTech Connect

Rising concern about the greenhouse effect reinforces the need to reexamine the question of a next-generation reactor concept that can contribute significantly toward substitution for fossil-based energy generation. Even with only the nuclear capacity on-line today, world-wide reasonably assured uranium resources would last for only about 50 years. If nuclear is to make a significant contribution, breeding is a fundamental requirement. Uranium resources can then be extended by two orders of magnitude, making nuclear essentially a renewable energy source. The key technical elements of the IFR concept are metallic fuel and fuel cycle technology based on pyroprocessing. Pyroprocessing is radically different from the conventional PUREX reprocessing developed for the LWR oxide fuel. Chemical feasibility of pyroprocessing has been demonstrated. The next major step in the IFR development program will be the full-scale pyroprocessing demonstration to be carried out in conjunction with EBR-II. IFR fuel cycle closure based on pyroprocessing can also have a dramatic impact on the waste management options, and in particular on the actinide recycling. 6 figs.

Chang, Y.I.

1989-01-01T23:59:59.000Z

346

512-S Facility, Actinide Removal Process Radiological Design Summary Report  

SciTech Connect

This report contains top-level requirements for the various areas of radiological protection for workers. Detailed quotations of the requirements for applicable regulatory documents can be found in the Radiological Design Summary Report Implementation Guide. For the purposes of demonstrating compliance with these requirements, per Engineering Standard 01064, ''shall consider / shall evaluate'' indicates that the designer must examine the requirement for the design and either incorporate or provide a technical justification as to why the requirement is not incorporated. This report describes how the Building 512-S, Actinide Removal Process meets the required radiological design criteria and requirements based on 10CFR835, DOE Order 420.1A, WSRC Manual 5Q and various other DOE guides and handbooks. The analyses supporting this Radiological Design Summary Report initially used a source term of 10.6 Ci/gallon of Cs-137 as the basis for bulk shielding calculations. As the project evolved, the source term was reduced to 1.1 Ci/gallon of Cs-137. This latter source term forms the basis for later dose rate evaluations.

Nathan, S.J.

2004-04-21T23:59:59.000Z

347

Application of chemical structure and bonding of actinide oxide materials for forensic science  

SciTech Connect

We are interested in applying our understanding of actinide chemical structure and bonding to broaden the suite of analytical tools available for nuclear forensic analyses. Uranium- and plutonium-oxide systems form under a variety of conditions, and these chemical species exhibit some of the most complex behavior of metal oxide systems known. No less intriguing is the ability of AnO{sub 2} (An: U, Pu) to form non-stoichiometric species described as AnO{sub 2+x}. Environmental studies have shown the value of utilizing the chemical signatures of these actinide oxide materials to understand transport following release into the environment. Chemical speciation of actinide-oxide samples may also provide clues as to the age, source, or process history of the material. The scientific challenge is to identify, measure and understand those aspects of speciation of actinide analytes that carry information about material origin and history most relevant to forensics. Here, we will describe our efforts in material synthesis and analytical methods development that we will use to provide the fundamental science to characterize actinide oxide molecular structures for forensic science. Structural properties and initial results to measure structural variability of uranium oxide samples using synchrotron-based X-ray Absorption Fine Structure will be discussed.

Wilkerson, Marianne Perry [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

348

Plutonium and minor actinide utilisation in a pebble-bed high temperature reactor  

SciTech Connect

This paper contains results of the analysis of the pebble-bed high temperature gas-cooled PUMA reactor loaded with plutonium and minor actinide (Pu/MA) fuel. Starting from knowledge and experience gained in the Euratom FP5 projects HTR-N and HTR-N1, this study aims at demonstrating the potential of high temperature reactors to utilize or transmute Pu/MA fuel. The work has been performed within the Euratom FP6 project PUMA. A number of different fuel types and fuel configurations have been analyzed and compared with respect to incineration performance and safety-related reactor parameters. The results show the excellent plutonium and minor actinide burning capabilities of the high temperature reactor. The largest degree of incineration is attained in the case of an HTR fuelled by pure plutonium fuel as it remains critical at very deep burnup of the discharged pebbles. Addition of minor actinides to the fuel leads to decrease of the achievable discharge burnup and therefore smaller fraction of actinides incinerated during reactor operation. The inert-matrix fuel design improves the transmutation performance of the reactor, while the 'wallpaper' fuel does not have advantage over the standard fuel design in this respect. After 100 years of decay following the fuel discharge, the total amount of actinides remains almost unchanged for all of the fuel types considered. Among the plutonium isotopes, only the amount of Pu-241 is reduced significantly due to its relatively short half-life. (authors)

Petrov, B. Y.; Kuijper, J. C.; Oppe, J.; De Haas, J. B. M. [Nuclear Research and Consultancy Group, Westerduinweg 3, 1755 ZG Petten (Netherlands)

2012-07-01T23:59:59.000Z

349

Technical requirements for the actinide source-term waste test program  

SciTech Connect

This document defines the technical requirements for a test program designed to measure time-dependent concentrations of actinide elements from contact-handled transuranic (CH TRU) waste immersed in brines similar to those found in the underground workings of the Waste Isolation Pilot Plant (WIPP). This test program wig determine the influences of TRU waste constituents on the concentrations of dissolved and suspended actinides relevant to the performance of the WIPP. These influences (which include pH, Eh, complexing agents, sorbent phases, and colloidal particles) can affect solubilities and colloidal mobilization of actinides. The test concept involves fully inundating several TRU waste types with simulated WIPP brines in sealed containers and monitoring the concentrations of actinide species in the leachate as a function of time. The results from this program will be used to test numeric models of actinide concentrations derived from laboratory studies. The model is required for WIPP performance assessment with respect to the Environmental Protection Agency`s 40 CFR Part 191B.

Phillips, M.L.F.; Molecke, M.A.

1993-10-01T23:59:59.000Z

350

Extraction of actinide (III, IV, V, VI) ions and TcO4- byN,N,N',N'- tetraisobutyl-3-oxa-glutaramide  

SciTech Connect

The extraction behavior of U(VI), Np(V), Pu(IV), Am(III), and TcO{sub 4}{sup -} with N, N, N', N'-tetraisobutyl-3-oxa-glutaramide (TiBOGA) were investigated. An organic phase of 0.2 mol/L TiBOGA in 40/60% (V/V) 1-octanol/kerosene showed good extractability for actinides (III, IV, V VI) and TcO{sub 4}{sup -}from aqueous solutions of HNO{sub 3} (0.1 to 4 mol/L). At 25 C, the distribution ratio of the actinide ions (D{sub An}) generally increased as the concentration of HNO{sub 3} in the aqueous phase was increased from 0.1 to 4 mol/L, while the D{sub Tc} at first increased, then decreased, with a maximum of 3.0 at 2 mol/L HNO{sub 3}. Based on the slope analysis of the dependence of D{sub M} (M = An or Tc) on the concentrations of reagents, the formula of extracted complexes were assumed to be UO{sub 2}L{sub 2}(NO{sub 3}){sub 2}, NpO{sub 2}L{sub 2}(NO{sub 3}), PuL(NO{sub 3}){sub 4}, AmL{sub 3}(NO{sub 3}){sub 3}, and HL{sub 2}(TcO{sub 4}) where L = TiBOGA. The enthalpy and entropy of the corresponding extraction reactions, {Delta}{sub r}H and {Delta}{sub r}S, were calculated from the dependence of D on temperature in the range of 15-55 C. For U(VI), Np(V), Am(III) and TcO{sub 4}{sup -}, the extraction reactions are enthalpy driven and disfavored by entropy ({Delta}{sub r}H < 0 and {Delta}{sub r}S < 0). In contrast, the extraction reaction of Pu(IV) is entropy driven and disfavored by enthalpy ({Delta}{sub r}H > 0 and {Delta}{sub r}S > 0). A test run with 0.2 mol/L TiBOGA in 40/60% 1-octanol/kerosene was performed to separate actinides and TcO{sub 4}{sup -} from a simulated acidic high-level liquid waste (HLLW), using tracer amounts of {sup 238}U(VI), {sup 237}Np(V), {sup 239}Pu(VI), {sup 241}Am(III) and {sup 99}TcO{sub 4}{sup -}. The distribution ratios of U(VI), Np(V), Pu(VI), Am(III) and TcO{sub 4}{sup -} were 12.4, 3.9, 87, > 1000 and 1.5, respectively, confirming that TiBOGA is a promising extractant for the separation of all actinides and TcO{sub 4}{sup -} from acidic HLLW. It is noteworthy that the extractability of TiBOGA for Np(V) from acidic HLLW (D{sub Np(V)} = 3.9) is much higher than that of many other extractants that have been studies for the separation of actinides from HLLW.

Tian, Guoxin; Zhang, Ping; Wang, Jianchen; Rao, Linfeng

2005-05-01T23:59:59.000Z

351

CERA Conference | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

CERA Conference CERA Conference CERA Conference February 14, 2007 - 10:15am Addthis Remarks as Prepared for Energy Secretary Samuel Bodman Thank you, Dan. I consider this event to be the premier gathering of opinion leaders on energy issues and I'm quite pleased to be here with all of you. What I plan to do this morning is first discuss how I see the world's energy challenges - and why President Bush believes addressing them must be at the top of our global agenda and then I'd like to focus on solutions and the best path forward. As we all well know, the demand for energy is rising rapidly and will continue to do so in the coming decades. I trust you've heard the sobering projections many times - for example, that by 2030 global energy consumption will grow by over 50 percent, with 70 percent of that growth

352

Events and Conferences | Partnerships | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

University Partnerships University Partnerships Events and Conferences Success Stories Video Newsletters Staff Contacts Partnerships Home | Connect with ORNL | For Industry | Partnerships | Events and Conferences Events and Conferences Show Events for: to and/or search events 1-10 of 10 Results Prev 1 Next Nov 19 2013 SPARK! 2013 Technology Forum Market focused presentations on Oak Ridge National Lab's most promising inventions. 01:00 PM - 06:30 PM Oct 25 2013 CW 2013 Composites World - Carbon Fiber 12:00 AM - 04:00 PM Sep 04 2013 Energy Storage Solutions Industrial Symposium Energy Storage Solutions Industrial Symposium - Wednesday September 4, 2013 09:00 AM - 05:30 PM Mar 05 2013 Bridging the Gap 2013 Oak Ridge National Laboratory hosted the third annual Bridging the Gap on March 5-6, 2013. This event brought entrepreneurs, scientists, and

353

10th Radiation Physics and Protection Conference  

NLE Websites -- All DOE Office Websites (Extended Search)

Atomic Energy Authority National Network of Radiation Physics Atomic Energy Authority National Network of Radiation Physics 10 th Radiation Physics and Protection Conference Special Topic Elements of Regulating Nuclear and Radiation Activities Egyptian Law 26 -30 November 2010 To be held at EAEA Headquarter Nasr City Cairo - Egypt (www.rphysp.com) INVITATION The conference organizing committee invites scientists from the Atomic Energy , Research Centers , Universities Institutes , and all those involved in radiation Physics and its Applications in Egypt , Arab countries and abroad to participate in scientific activities of the conference . The official working language of the conference in English Conference Honorary Chairman Conference Scientific Secretary

354

Spelman College 7th Annual Spelman College Leadership Conference  

Energy.gov (U.S. Department of Energy (DOE))

Theme for this year's conference is still being developed - last year, the conference focused on "best practices to help women achieve better personal and professional sustainability. Conference...

355

EM SSAB Chairs Conference Calls | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

SSAB Chairs Conference Calls EM SSAB Chairs Conference Calls June 18, 2013 EM SSAB Conference Calls - June 18, 2013 Minutes and highlights of the Environmental Management (EM) Site...

356

EM SSAB Chairs Conference Calls | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Communication & Engagement EM SSAB EM SSAB Chairs Conference Calls EM SSAB Chairs Conference Calls October 25, 2007 EM SSAB Conference Calls - October 25, 2007 Special...

357

National Conference of Black Mayors, Inc. | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

National Conference of Black Mayors, Inc. National Conference of Black Mayors, Inc. The cooperative agreement enhances the National Conference of Black Mayors, Inc., members'...

358

2013 NEJC Post-Conference Summary | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NEJC Post-Conference Summary 2013 NEJC Post-Conference Summary Another Successful Year for the 2013 National Environmental Justice Conference and Training Program 2013 NEJC...

359

EIA - Energy Conferences & Presentations.  

U.S. Energy Information Administration (EIA) Indexed Site

5 5 EIA Conference 2009 Session 5: Renewable Energy in the Transportation and Power Sectors Listen to Session: Audio of Session 1 from 2009 EIA Conference Full Session Transcript PDF Icon pdf Moderator: Michael Schaal (EIA) Speakers: Denise Bode (American Wind Energy Association) Bryan Hannegan (Electric Power Research Institute) Matt Hartwig (Renewable Fuels Association) David Humbird (National Renewable Energy Laboratory) Note: Concurrent sessions used a variety of presentation and round table discussion formats. All available presentations have been posted. Moderator and Speaker Bios and Presentations Michael Schaal, Director of the Energy Information Administration's Oil and Gas Division Renewable Energy in the Transportation and Power Sectors PDF Icon pdf Powerpoint Icon

360

Fusion Techniques for the Oxidation of Refractory Actinide Oxides  

Science Conference Proceedings (OSTI)

Small-scale experiments were performed to demonstrate the feasibility of fusing refractory actinide oxides with a series of materials commonly used to decompose minerals, glasses, and other refractories as a pretreatment to dissolution and subsequent recovery operations. In these experiments, 1-2 g of plutonium or neptunium oxide (PuO2 or NpO2) were calcined at 900 degrees Celsius, mixed and heated with the fusing reagent(s), and dissolved. For refractory PuO2, the most effective material tested was a lithium carbonate (Li2CO3)/sodium tetraborate (Na2B4O7) mixture which aided in the recovery of 90 percent of the plutonium. The fused product was identified as a lithium plutonate (Li3PuO4) by x-ray diffraction. The use of a Li2CO3/Na2B4O7 mixture to solubilize high-fired NpO2 was not as effective as demonstrated for refractory PuO2. In a small-scale experiment, 25 percent of the NpO2 was oxidized to a neptunium (VI) species that dissolved in nitric acid. The remaining neptunium was then easily recovered from the residue by fusing with sodium peroxide (Na2O2). Approximately 70 percent of the neptunium dissolved in water to yield a basic solution of neptunium (VII). The remainder was recovered as a neptunium (VI) solution by dissolving the residue in 8M nitric acid. In subsequent experiments with Na2O2, the ratio of neptunium (VII) to (VI) was shown to be a function of the fusion temperature, with higher temperatures (greater than approximately 400 degrees C) favoring the formation of neptunium (VII). The fusion of an actual plutonium-containing residue with Na2O2 and subsequent dissolution was performed to demonstrate the feasibility of a pretreatment process on a larger scale. Sodium peroxide was chosen due to the potential of achieving higher actinide recoveries from refractory materials. In this experiment, nominally 10 g of a graphite-containing residue generated during plutonium casting operations was initially calcined to remove the graphite. Removal of combustible material prior to a large-scale fusion with Na2O2 is needed due to the large amount of heat liberated during oxidation. Two successive fusions using the residue from the calcination and the residue generated from the initial dissolution allowed recovery of 98 percent of the plutonium. The fusion of the residue following the first dissolution was performed at a higher temperature (600 degrees Celsius versus 450 degrees Celsius during the first fusion). The ability to recover most of the remaining plutonium from the residue suggest the oxidation efficiency of the Na2O2 fusion improves with higher temperatures similar to results observed with NpO2 fusion.

Rudisill, T.S.

1999-04-15T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
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361

Proceedings of the 2013 conference on Internet measurement conference  

Science Conference Proceedings (OSTI)

Welcome to the 2013 edition of the Internet Measurement Conference. The 42 papers you will hear presented over the next three days represent some of the year's best work in network measurement and we hope you enjoy their contributions! This year the ...

Konstantina (Dina) Papagiannaki, Krishna Gummadi, Craig Partridge

2013-10-01T23:59:59.000Z

362

Final Project Report INERT-MATRIX FUEL: ACTINIDE "BURNING" AND DIRECT DISPOSAL  

Office of Scientific and Technical Information (OSTI)

Project Report Project Report INERT-MATRIX FUEL: ACTINIDE "BURNING" AND DIRECT DISPOSAL Nuclear Engineering Education Research Program (grant # DE-FG07-99ID13767) Rodney C. Ewing (co-PI) Lumin Wang (co-PI) October 30,2002 For the Period of 07/01/1999 to 06/30/2002 Department of Nuclear Engineering and Radiological Sciences University of Michigan Ann Arbor, MI 48109 1 1. Background Excess actinides result from the dismantlement of nuclear weapons (239Pu) and the reprocessing of commercial spent nuclear fuel (mainly 241Am, Cm and 237Np). In Europe, Canada and Japan studies have determined much improved efficiencies for burn- up of actinides using inert-matrix fuels. This innovative approach also considers the properties of the inert-matrix fuel as a nuclear waste form for direct disposal after one-

363

Minor Actinides Loading Optimization for Proliferation Resistant Fuel Design - BWR  

Science Conference Proceedings (OSTI)

One approach to address the United States Nuclear Power (NP) 2010 program for the advanced light water reactor (LWR) (Gen-III+) intermediate-term spent fuel disposal need is to reduce spent fuel storage volume while enhancing proliferation resistance. One proposed solution includes increasing burnup of the discharged spent fuel and mixing minor actinide (MA) transuranic nuclides (237Np and 241Am) in the high burnup fuel. Thus, we can reduce the spent fuel volume while increasing the proliferation resistance by increasing the isotopic ratio of 238Pu/Pu. For future advanced nuclear systems, MAs are viewed more as a resource to be recycled, and transmuted to less hazardous and possibly more useful forms, rather than simply disposed of as a waste stream in an expensive repository facility. MAs play a much larger part in the design of advanced systems and fuel cycles, not only as additional sources of useful energy, but also as direct contributors to the reactivity control of the systems into which they are incorporated. A typical boiling water reactor (BWR) fuel unit lattice cell model with UO2 fuel pins will be used to investigate the effectiveness of adding MAs (237Np and/or 241Am) to enhance proliferation resistance and improve fuel cycle performance for the intermediate-term goal of future nuclear energy systems. However, adding MAs will increase plutonium production in the discharged spent fuel. In this work, the Monte-Carlo coupling with ORIGEN-2.2 (MCWO) method was used to optimize the MA loading in the UO2 fuel such that the discharged spent fuel demonstrates enhanced proliferation resistance, while minimizing plutonium production. The axial averaged MA transmutation characteristics at different burnup were compared and their impact on neutronics criticality and the ratio of 238Pu/Pu discussed.

G. S. Chang; Hongbin Zhang

2009-09-01T23:59:59.000Z

364

Battery separator material  

SciTech Connect

A novel, improved battery separator material particularly adaptable for use in maintenance free batteries. The battery separator material includes a diatomaceous earth filler, an acrylate copolymer binder and a combination of fibers comprising polyolefin, polyester and glass fibers.

Bodendorf, W. J.

1985-07-16T23:59:59.000Z

365

Some activities in the United States concerning the physics aspects of actinide waste recycling  

SciTech Connect

Reactor types being considered in the United States for the purpose of actinide waste recycling are discussed briefly. The reactor types include thermal reactors operating on the 3.3 percent $sup 235$U--$sup 238$U and the $sup 233$U--$sup 232$Th fuel cycles, liquid metal fast breeder reactors, reactors fueled entirely by actinide wastes, gaseous fuel reactors, and fusion reactors. Cross section measurements in progress or planned toward providing basic data for testing the recycle concept are also discussed. (auth)

Raman, S.

1975-01-01T23:59:59.000Z

366

Proceedings of the Winter Simulation Conference  

Science Conference Proceedings (OSTI)

Welcome to the 2012 Winter Simulation Conference (WSC), recognized as the premiere international conference for simulation professionals in discrete and combined discrete-continuous simulation. Our venue of Berlin this year continues the trend of new ...

Oliver Rose; Adelinde M. Uhrmacher

2012-12-01T23:59:59.000Z

367

Energy Storage Systems 2010 Update Conference Presentations ...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3 Energy Storage Systems 2010 Update Conference Presentations - Day 2, Session 3 The U.S. DOE Energy Storage Systems Program (ESS) conducted a record-breaking Update Conference at...

368

Energy Storage Systems 2010 Update Conference Presentations ...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3 Energy Storage Systems 2010 Update Conference Presentations - Day 1, Session 3 The U.S. DOE Energy Storage Systems Program (ESS) conducted a record-breaking Update Conference at...

369

Energy Storage Systems 2010 Update Conference Presentations ...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4 Energy Storage Systems 2010 Update Conference Presentations - Day 2, Session 4 The U.S. DOE Energy Storage Systems Program (ESS) conducted a record-breaking Update Conference at...

370

Energy Storage Systems 2010 Update Conference Presentations ...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4 Energy Storage Systems 2010 Update Conference Presentations - Day 1, Session 4 The U.S. DOE Energy Storage Systems Program (ESS) conducted a record-breaking Update Conference at...

371

Energy Storage Systems 2010 Update Conference Presentations ...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3 Energy Storage Systems 2010 Update Conference Presentations - Day 3, Session 3 The U.S. DOE Energy Storage Systems Program (ESS) conducted a record-breaking Update Conference at...

372

1995 International Sherwood Fusion Theory Conference  

Science Conference Proceedings (OSTI)

This book is a guide to the 1995 International Sherwood Fusion Theory Conference. It consists largely of abstracts of the oral and poster presentations that were to be made, and gives some general information about the conference and its schedule.

NONE

1995-07-01T23:59:59.000Z

373

BNL PHYSICS DEPARTMENT TRAINING FOR CONFERENCE ATTENDEES  

NLE Websites -- All DOE Office Websites (Extended Search)

PHYSICS DEPARTMENT TRAINING FOR CONFERENCE ATTENDEES This training is intended for conference or meeting attendees who are onsite less than 1 week and who will not be working in a...

374

2013 White House Tribal Nations Conference  

Energy.gov (U.S. Department of Energy (DOE))

On Wednesday, November 13, President Obama will host the White House Tribal Nations Conference at the Department of the Interior. The conference will provide leaders from the 566 federally...

375

Proceedings: Geomagnetically Induced Currents Conference  

Science Conference Proceedings (OSTI)

Magnetic storms can induce currents in power networks, causing serious consequences for electric utilities. In response to problems experienced by several utilities during the severe magnetic storm of March 13, 1989, EPRI held a conference on geomagnetically induced currents to help define the problems and develop ideas for needed R&D.

1992-06-01T23:59:59.000Z

376

Condenser Technology: Seminar and Conference  

Science Conference Proceedings (OSTI)

Steam surface condensers and associated systems cause significant loss of availability and heat rate degradation in both nuclear and fossil-fired power plants. Nineteen papers, presented at a 2002 conference, discussed industrial experience and case histories of condenser problems and solutions.

2002-08-22T23:59:59.000Z

377

Proceedings: Cooling Tower Technology Conference  

Science Conference Proceedings (OSTI)

Cooling towers and associated systems performance strongly affect availability and heat rate in fossil and nuclear power plants. Twenty-two papers presented at the 1997 Cooling Tower Technology Conference discuss research results, industry experience, and case histories of cooling tower problems and solutions.

1997-08-13T23:59:59.000Z

378

CIEE 1993 annual conference: Program  

Science Conference Proceedings (OSTI)

The California Institute for Energy efficiency`s third annual conference highlights the results of CIEE-sponsored multiyear research in three programs: Building Energy Efficiency, Air Quality Impacts of Energy Efficiency, and End-Use Resource Planning. Results from scoping studies, Director`s discretionary research, and exploratory research are also featured.

Not Available

1993-08-01T23:59:59.000Z

379

International Conference on "Developing Unconventional  

E-Print Network (OSTI)

Gas hydrate o Shale gas o Lignite Exploration and production o Peat Gas o Biodiesel o Oil sand o in 2009 to train manpower and to pursue research in the area of upstream Oil & Gas explorationInternational Conference on "Developing Unconventional Oil & Gas Resources" (DUOG 2013) st nd 1 , 2

Bhashyam, Srikrishna

380

EJ Conference, Inc. Presents Environmental Justice  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Presents Presents Environmental Justice The State of in America 2010 Conference Message from the Department of Energy's Environmental Justice Program Manager Welcome to "The State of Environmental Justice in America 2010 Conference". This is the fourth conference in this series that began in 2007. The Department of Energy (DOE) is pleased to be a sponsor of this conference series. Environmental justice is actually a principal of American democracy that combines civil rights

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

1994 International Sherwood Fusion Theory Conference  

SciTech Connect

This report contains the abstracts of the paper presented at the 1994 International Sherwood Fusion Theory Conference.

NONE

1994-04-01T23:59:59.000Z

382

Natural Gas Supply Conference - Energy Information Administration  

U.S. Energy Information Administration (EIA)

Natural Gas Supply Conference. William Trapmann Energy Information Administration. American Public Gas Association January 30 & 31, 2001

383

Third International Conference on Grain Growth  

Science Conference Proceedings (OSTI)

AT-MEETING TECHNICAL PROGRAM AS A .PDF FILE (View using Adobe Acrobat) TECHNICAL PROGRAM IN THE CONFERENCE MANAGEMENT SYSTEM

384

Overview of the 2010 Text Analysis Conference  

Science Conference Proceedings (OSTI)

... Text Analysis Conference Hoa Trang Dang ... needs of modern NLP systems • To increase communication among industry, academia, and ...

2011-03-18T23:59:59.000Z

385

ITL Publishes Proceedings of Text Retrieval Conference ...  

Science Conference Proceedings (OSTI)

... The Information Access Division has published the proceedings of the fifteenth annual Text REtrieval Conference, TREC 2006, as NIST Special ...

386

Adams and Reese Annual Energy Conference  

Reports and Publications (EIA)

Adams and Reese Annual Energy Conference, New Orleans, LA - Jay E. Hakes, Administrator, Energy Information Administration - November 20, 1998

Information Center

1998-11-20T23:59:59.000Z

387

Fifth Annual Health Information Security Conference Runs ...  

Science Conference Proceedings (OSTI)

... conference is an opportunity for HIPAA security rule implementers; security, privacy and compliance officers; assessment teams and audit staff in ...

2012-04-17T23:59:59.000Z

388

May Conference to Discuss Safeguarding Health Information ...  

Science Conference Proceedings (OSTI)

... conference is an opportunity for HIPAA security rule implementers; security, privacy and compliance officers; assessment teams and audit staff in ...

2013-05-03T23:59:59.000Z

389

Environmental Degradation 2011 Conference: Technical Program  

Science Conference Proceedings (OSTI)

Environmental Degradation 2011 Conference: Technical Program August 7-11, 2011 * Cheyenne Mountain Resort * Colorado Springs, Colorado. The purpose ...

390

Fifth Power Delivery Asset Management Conference  

Science Conference Proceedings (OSTI)

The Electric Power Research (EPRI) Asset Management Conference is part of EPRI's Power Delivery Asset Management program. The Asset Management Conference helps members manage their corporate culture by incorporating asset management best practices and aligning organizational processes around asset management goals. This report details EPRI's fifth Power Delivery Asset Management (PDAM) Conference.

2011-11-29T23:59:59.000Z

391

Governor's energy conference - Hawaii's energy options for the 80s  

Science Conference Proceedings (OSTI)

The purpose of the conference was to share with the people of Hawaii the latest knowledge in the fields of energy conservation, alternate energy development, and related legal and financial considerations. Representatives from government, private industry, and the scientific community were among the speakers. The conference program was presented in six sessions: public-sector conservation; private-sector conservation; public-sector alternate energy; private-sector alternate energy; liquid and gas fuels and fuel cells; and legal and financial considerations. At the luncheon and banquet sessions, nationally-known speakers discussed the Strategic Petroleum Reserve and global aspects of energy supply and demand. A separate abstract was prepared for each of 47 individual presentations.

Fowler, N.; Sorenson, K.

1982-01-01T23:59:59.000Z

392

Second annual clean coal technology conference: Proceedings. Volume 1  

Science Conference Proceedings (OSTI)

The Second Annual Clean Coal Technology Conference was held at Atlanta, Georgia, September 7--9, 1993. The Conference, cosponsored by the US Department of Energy (USDOE) and the Southern States Energy Board (SSEB), seeks to examine the status and role of the Clean Coal Technology Demonstration Program (CCTDP) and its projects. The Program is reviewed within the larger context of environmental needs, sustained economic growth, world markets, user performance requirements and supplier commercialization activities. This will be accomplished through in-depth review and discussion of factors affecting domestic and international markets for clean coal technology, the environmental considerations in commercial deployment, the current status of projects, and the timing and effectiveness of transfer of data from these projects to potential users, suppliers, financing entities, regulators, the interested environmental community and the public. Individual papers have been entered separately.

Not Available

1993-09-09T23:59:59.000Z

393

Proceedings of the 1993 oil heat technology conference and workshop  

SciTech Connect

This report documents the proceedings of the 1993 Oil Heat Technology Conference and Workshop, held on March 25--26 at Brookhaven National Laboratory (BNL), and sponsored by the US Department of Energy - Office of Building Technologies (DOE-OBT), in cooperation with the Petroleum Marketers Association of America. This Conference, which was the seventh held since 1984, is a key technology-transfer activity supported by the ongoing Combustion Equipment Technology (Oil-Heat R&D) program at BNL, and is aimed at providing a forum for the exchange of information among international researchers, engineers, manufacturers, and marketers of oil-fired space- conditioning equipment. Selected papers have been processed separately for inclusion in the Energy Science and Technology Database.

McDonald, R.J.

1993-09-01T23:59:59.000Z

394

2013-09-18: USNWG on Taximeters Web-conference  

Science Conference Proceedings (OSTI)

USNWG on Taximeters Web-conference. Purpose: ... Specific agenda items will be circulated prior to the web-conference. Details: ...

2013-08-06T23:59:59.000Z

395

ELECTROCHEMICALLY-MODULATED SEPARATIONS FOR SAFEGUARDS MEASUREMENTS  

Science Conference Proceedings (OSTI)

A critical objective of materials accountability in safeguards is the accurate and timely analysis of fuel reprocessing streams to detect both abrupt and prolonged diversions of nuclear materials. For this reason both on-line nondestructive (NDA) and destructive analysis (DA) approaches are sought-after. Current methods for DA involve grab sampling and laboratory based column extractions that are costly, hazardous, and time consuming. While direct on-line gamma measurements of Pu are desirable, they are not possible due to contributions from other actinides and fission products. Researchers at Pacific Northwest National Laboratory are currently investigating electrochemically-modulated separation (EMS) as a straightforward, cost-effective technology for selective separation of Pu or U from aqueous reprocessing streams. The EMS selectivity is electrochemically controlled and results from the sorption of Pu4+ and U4+ redox states onto the anodized target electrode, allowing for selective accumulation of U or Pu from nitric acid streams to be turned “on” or “off.” It is envisioned that this technology can be utilized to isolate Pu for both NDA and DA analysis. For the NDA approach, rapid Pu analysis by gamma-ray spectroscopy could be performed after chemical clean-up of activation and fission products by EMS. Likewise, in the DA approach, EMS could be used to retain and concentrate the Pu in nanogram quantities on the electrode surface to be transported to the lab for analysis using high precision mass spectrometry. Due to the challenges associated with complex matrices, a systematic investigation of the redox-dependent accumulation of Pu using EMS was necessary, and results will be presented. Approaches to mitigate interelement effects using large surface area cells will also be discussed. The EMS chemistry and spectroscopy for Pu isolation and measurement will be presented, proof-of-principle measurements will be described, and the application of this approach for materials accountability will be discussed.

Green, Michael A.; Arrigo, Leah M.; Liezers, Martin; Orton, Christopher R.; Douglas, Matthew; Peper, Shane M.; Schwantes, Jon M.; Hazelton, Sandra G.; Duckworth, Douglas C.

2010-08-11T23:59:59.000Z

396

Demonstration of a Universal Solvent Extraction Process for the Separation of Cesium and Strontium from Actual Acidic Tank Waste at the INEEL  

Science Conference Proceedings (OSTI)

A universal solvent extraction process is being evaluated for the simultaneous separation of Cs, Sr, and the actinides from acidic high-activity tank waste at the Idaho National Engineering and Environmental Laboratory (INEEL) with the goal of minimizing the high-activity waste volume to be disposed in a deep geological repository. The universal solvent extraction process is being developed as a collaborative effort between the INEEL and the Khlopin Radium Institute in St. Petersburg, Russia. The process was recently demonstrated at the INEEL using actual radioactive, acidic tank waste in 24 stages of 2-cm-diameter centrifugal contactors located in a shielded cell facility. With the testing, removal efficiencies of 99.95%, 99.985%, and 95.2% were obtained for Cs-137, Sr-90, and total alpha, respectively. This is sufficient to reduce the activities of Cs-137 and Sr-90 to below NRC Class A LLW requirements. The total alpha removal efficiency was not sufficient to reduce the activity of the tank waste to below NRC Class A non-TRU requirements. The lower than expected removal efficiency for the actinides is due to loading of the Ph2Bu2CMPO in the universal solvent with actinides and metals (Zr, Fe, and Mo). Also, the carryover of aqueous solution (flooding) with the solvent exiting the actinide strip section and entering the wash section resulted in the recycle of the actinides back to the extraction section. This recycle of the actinides contributed to the low removal efficiency. Significant amounts of the Zr (>97.7%), Ba (>87%), Pb (>98.5%), Fe (>6.9%), Mo (19%), and K (17%) were also removed from the feed with the universal solvent extraction flowsheet.

B. N. Zaitsev (Khlopin Radium Institute); D. J. Wood (INEEL); I. V. Smirnov; J. D. Law; R. S. Herbst; T. A. Todd; V. A. Babain; V. M. Esimantovskiy; V. N. Romanovskiy

1999-08-01T23:59:59.000Z

397

Microscopic Description of Nuclear Fission: Fission Barrier Heights of Even-Even Actinides  

E-Print Network (OSTI)

We evaluate the performance of modern nuclear energy density functionals for predicting inner and outer fission barrier heights and energies of fission isomers of even-even actinides. For isomer energies and outer barrier heights, we find that the self-consistent theory at the HFB level is capable of providing quantitative agreement with empirical data.

J. McDonnell; N. Schunck; W. Nazarewicz

2013-01-31T23:59:59.000Z

398

Method of loading organic materials with group III plus lanthanide and actinide elements  

DOE Patents (OSTI)

Disclosed is a composition of matter comprising a tributyl phosphate complex of a group 3, lanthanide, actinide, or group 13 salt in an organic carrier and a method of making the complex. These materials are suitable for use in solid or liquid organic scintillators, as in x-ray absorption standards, x-ray fluorescence standards, and neutron detector calibration standards.

Bell, Zane W. (Oak Ridge, TN); Huei-Ho, Chuen (Oak Ridge, TN); Brown, Gilbert M. (Knoxville, TN); Hurlbut, Charles (Sweetwater, TX)

2003-04-08T23:59:59.000Z

399

Microscopic Description of Nuclear Fission: Fission Barrier Heights of Even-Even Actinides  

E-Print Network (OSTI)

We evaluate the performance of modern nuclear energy density functionals for predicting inner and outer fission barrier heights and energies of fission isomers of even-even actinides. For isomer energies and outer barrier heights, we find that the self-consistent theory at the HFB level is capable of providing quantitative agreement with empirical data.

McDonnell, J; Nazarewicz, W

2013-01-01T23:59:59.000Z

400

Colloidal products and actinide species in leachate from spent nuclear fuel  

Science Conference Proceedings (OSTI)

Two well-characterized types of spent nuclear fuel (ATM-103 and ATM-106) were subjected to unsaturated leach tests with simulated groundwater at 90{degrees}C. The actinides present in the leachate were determined at the end of two successive periods of {approximately}60 days and after an acid strip done at the end of the second period. Both colloidal and soluble actinide species were detected in the leachates which had pHs ranging from 4 to 7. The uranium phases identified in the colloids were schoepite and soddyite. In addition, the actinide release behavior of the two fuels appeared to be different for both the total amount of material released and the relative amount of each isotope released. This paper will focus on the detection and identification of the colloidal species observed in the leachate that was collected after each of the first two successive testing periods of approximately 60 days each. In addition, preliminary values for the total actinide release for these two periods are reported.

Finn, P.A.; Buck, E.C.; Gong, M.; Hoh, J.C.; Emery, J.W.; Hafenrichter, L.D.; Bates, J.K.

1993-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Possible experimental signature of octupole correlations in the 0$^+_2$ states of the actinides  

E-Print Network (OSTI)

$J^{\\pi}$= 0$^+$ states have been investigated in the actinide nucleus ${}^{240}$Pu up to an excitation energy of 3 MeV with a high-resolution (p,t) experiment at $E_{p}$= 24 MeV. To test the recently proposed $J^{\\pi}$= 0$^+_2$ double-octupole structure, the phenomenological approach of the spdf-interacting boson model has been chosen. In addition, the total 0$^+$ strength distribution and the $0^+$ strength fragmentation have been compared to the model predictions as well as to the previously studied (p,t) reactions in the actinides. The results suggest that the structure of the 0$^+_2$ states in the actinides might be more complex than the usually discussed pairing isomers. Instead, the octupole degree of freedom might contribute significantly. The signature of two close-lying 0$^+$ states below the 2-quasiparticle energy is presented as a possible manifestation of strong octupole correlations in the structure of the 0$^+_2$ states in the actinides.

M. Spieker; D. Bucurescu; J. Endres; T. Faestermann; R. Hertenberger; S. Pascu; S. Skalacki; S. Weber; H. -F. Wirth; N. -V. Zamfir; A. Zilges

2013-10-21T23:59:59.000Z

402

Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide as an extractant for actinides from nitric acid waste  

SciTech Connect

The ability of neutral bifunctional organophosphorus compounds to extract trivalent actinides, specifically Am(III), from nitric acid solution has stimulated investigations into the processing of PUREX high level liquid waste. The authors' work in this area has focused primarily on derivatives of carbamoylmethylphosphine oxide (CMPO). The authors of this paper have found that the best extractant of this type is octyl(phenyl)-N,N-diisobutylmethylphosphine oxide (abbrev. O phi D (IB)CMPO). This extractant has a unique combination of substituent groups which impart to the resulting molecule substantially improved ability to extract actinides from acidic nitrate media and to withstand hydrolytic and radiolytic degradation. At the same time good selectivity of Am(III) actinides over fission products and favorable solubility properties on actinide loading are maintained. This paper describes the application of O phi D (IB) CMPO to the extraction of transuranium elements (Np, Pu, and Am) and fission product rare earths (F.P.R.E.) from evaporated highly acidic (5 M HNO/sub 3/) PUREX waste. Additional information on the influence of phenyl substitution in CMPO's and mixed CMPO-TBP extractant solutions on D/sub Am/ is also presented. 3 figures, 2 tables.

Horwitz, E.P.; Diamond, H.; Kalina, D.G.; Kaplan, L.; Mason, G.W.

1983-01-01T23:59:59.000Z

403

TOPICAL REPORT ON ACTINIDE-ONLY BURNUP CREDIT FOR PWR SPENT NUCLEAR FUEL PACKAGES  

Science Conference Proceedings (OSTI)

A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay. A set of chemical assay benchmarks is presented for this purpose as well as a method for assessing the calculational bias and uncertainty, and conservative correction factors for each isotope. (2) Validate a computer code system to predict the subcritical multiplication factor, k{sub eff}, of a spent nuclear fuel package. Fifty-seven UO{sub 2}, UO{sub 2}/Gd{sub 2}O{sub 3}, and UO{sub 2}/PuO{sub 2} critical experiments have been selected to cover anticipated conditions of SNF. The method uses an upper safety limit on k{sub eff} (which can be a function of the trending parameters) such that the biased k{sub eff}, when increased for the uncertainty is less than 0.95. (3) Establish bounding conditions for the isotopic concentration and criticality calculations. Three bounding axial profiles have been established to assure the ''end effect'' is accounted for conservatively. (4) Use the validated codes and bounding conditions to generate package loading criteria (burnup credit loading curves). Burnup credit loading curves show the minimum burnup required for a given initial enrichment. The utility burnup record is compared to this requirement after the utility accounts for the uncertainty in its record. Separate curves may be generated for each assembly design, various minimum cooling times and burnable absorber histories. (5) Verify that SNF assemblies meet the package loading criteria and confirm proper assembly selection prior to loading. A measurement of the average assembly burnup is required and that measurement must be within 10% of the utility burnup record for the assembly to be accepted. The measurement device must be accurate to within 10%. Each step is described in detail for use with any computer code system and is then demonstrated with the SCALE 4.2 computer code package using 27BURNUPLIB cross sections.

DOE

1997-04-01T23:59:59.000Z

404

Isotope separation by photochromatography  

DOE Patents (OSTI)

An isotope separation method which comprises physically adsorbing an isotopically mixed molecular species on an adsorptive surface and irradiating the adsorbed molecules with radiation of a predetermined wavelength which will selectively excite a desired isotopic species. Sufficient energy is transferred to the excited molecules to desorb them from the surface and thereby separate them from the unexcited undesired isotopic species. The method is particularly applicable to the separation of hydrogen isotopes.

Suslick, Kenneth S. (Stanford, CA)

1977-01-01T23:59:59.000Z

405

NETL: Air Quality III Conference  

NLE Websites -- All DOE Office Websites (Extended Search)

Air Quality III Conference - September 12, 2002 Air Quality III Conference - September 12, 2002 Table of Contents Disclaimer Papers and Presentations Disclaimer This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government or any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

406

EIA - Energy Conferences & Presentations.  

U.S. Energy Information Administration (EIA) Indexed Site

3 3 EIA Conference 2009 Session 3: Meeting the Growing Demand for Liquids Listen to Session: Audio of Session 1 from 2009 EIA Conference Full Session Transcript PDF Icon pdf Moderator: Glen Sweetnam (EIA) Speakers: Eduardo González-Pier (PEMEX) David Knapp (Energy Intelligence Group) Fareed Mohamedi (PFC Energy) Note: Concurrent sessions used a variety of presentation and round table discussion formats. All available presentations have been posted. Moderator and Speaker Bios and Presentations Meeting the Growing Demand for Liquids PDF Icon pdf Powerpoint Icon ppt Glen Sweetnam is the Director of the International, Economic, and Greenhouse Gases Division of the Energy Information Administration. This Division produces the International Energy Outlook, the macroeconomic

407

Information Resources: Conferences and Meetings  

NLE Websites -- All DOE Office Websites (Extended Search)

Conferences and Meetings Conferences and Meetings DOE organizes three annual workshops to bring together a diverse gathering of participants-government, industry, academia, research institutions, energy efficiency organizations, utilities, retailers, and designers-to share insights, ideas, and updates on the rapidly evolving SSL market. Which Annual DOE SSL Workshops Are Right For You? R&D Manufacturing R&D Market Introduction When you must know... Latest breakthroughs from DOE-funded R&D projects Scientific pathways to improving performance and reducing costs New ideas for tough technical challenges Challenges of manufacturing LEDs, luminaires, drivers, and electronics New ideas to improve LED and OLED manufacturing processes, equipment, and costs Latest on product performance, selection, efficiency, quality, reliability, and cost effectiveness

408

EIA - Energy Conferences & Presentations.  

U.S. Energy Information Administration (EIA) Indexed Site

EIA Conference 2009 Session 1: The Future for Transport Demand Listen to Session: Audio of Session 1 from 2009 EIA Conference Full Session Transcript PDF Icon pdf Moderator: Andy Kydes (EIA) Speakers: Lew Fulton (International Energy Agency) David Greene (Oak Ridge National Laboratory) Lee Schipper (Precourt Institute, Stanford University) Note: Concurrent sessions used a variety of presentation and round table discussion formats. All available presentations have been posted. Moderator and Speaker Bios and Presentations The Future of Transport Demand PDF Icon pdf Powerpoint Icon ppt Andy S. Kydes is the Senior Technical Advisor to the Office of Integrated Analysis and Forecasting. He performs quality assurance for the design and development of the National Energy Modeling System and acts as senior

409

EIA - Energy Conferences & Presentations.  

U.S. Energy Information Administration (EIA) Indexed Site

8 8 EIA Conference 2009 Session 8: Energy and the Media Listen to Session: Audio of Session 1 from 2009 EIA Conference Full Session Transcript PDF Icon pdf Moderator: John Anderson (Resources for the Future) Speakers: Barbara Hagenbaugh (USA Today) Steven Mufson (Washington Post) Eric Pooley (Harvard University) Robert Rapier (R-SQUARED Energy blog) Note: Concurrent sessions used a variety of presentation and round table discussion formats. All available presentations have been posted. Moderator and Speaker Bios and Presentations John Anderson, Resources for the Future John W. Anderson was a reporter and editorial writer for the Washington Post for several decades. On the editorial page he frequently wrote about energy and economic policy. Since 1996 he has been at Resources for the

410

EIA - Energy Conferences & Presentations.  

U.S. Energy Information Administration (EIA) Indexed Site

9 9 EIA Conference 2009 Session 9: Investing in Oil and Natural Gas - Opportunities and Barriers Listen to Session: Audio of Session 1 from 2009 EIA Conference Full Session Transcript PDF Icon pdf Moderator: Bruce Bawks (EIA) Speakers: Susan Farrell (PFC Energy) John Felmy (American Petroleum Institute) Michelle Foss (University of Texas) Paul Sankey (Deutsche Bank) Note: Concurrent sessions used a variety of presentation and round table discussion formats. All available presentations have been posted. Moderator and Speaker Bios and Presentations Bruce Bawks, EIA Investing in Oil and Natural Gas Opportunities and Barriers PDF Icon pdf Powerpoint Icon ppt Bruce Bawks joined the Energy Information Administration in 1984. Since February 2004, he has been the team leader of EIA's financial analysis

411

EIA - Energy Conferences & Presentations.  

U.S. Energy Information Administration (EIA) Indexed Site

6 6 EIA Conference 2009 Session 6: Financial Markets and Short-Term Energy Prices Listen to Session: Audio of Session 1 from 2009 EIA Conference Full Session Transcript PDF Icon pdf Moderator: Tancred Lidderdale (EIA) Speakers: Jeffrey Harris (Commodity Futures Trading Commission) Robert McCullough (McCullough Research) Adam E. Sieminski (Deutsche Bank) Robert Weiner (George Washington University) Note: Concurrent sessions used a variety of presentation and round table discussion formats. All available presentations have been posted. Moderator and Speaker Bios and Presentations Tancred Lidderdale, EIA Tancred Lidderdale is the supervisor of the team that produces that the Short-Term Energy Outlook for the Energy Information Administration. Before joining EIA in 1991, he worked for 12 years with Atlantic Richfield Company

412

EIA - Energy Conferences & Presentations.  

U.S. Energy Information Administration (EIA) Indexed Site

4 4 EIA Conference 2009 Session 4: Electric Power Infrastructure: Status and Challenges for the Future Listen to Session: Audio of Session 1 from 2009 EIA Conference Full Session Transcript PDF Icon pdf Moderator: Scott Sitzer (EIA) Speakers: P. Kumar Agarwal (Federal Energy Regulatory Commission) Timothy J. Brennan (University of Maryland) Mark G. Lauby (North American Electric Reliability Corporation) Note: Concurrent sessions used a variety of presentation and round table discussion formats. All available presentations have been posted. Moderator and Speaker Bios and Presentations Scott Sitzer, Director of the Office of Coal, Nuclear, Electric and Alternate Fuels Scott Sitzer is Director of the Office of Coal, Nuclear, Electric and Alternate Fuels of the Energy Information Administration (EIA). He has been

413

EIA - Energy Conferences & Presentations.  

U.S. Energy Information Administration (EIA) Indexed Site

7 7 EIA Conference 2009 Session 7: Energy Data Needs Listen to Session: Audio of Session 1 from 2009 EIA Conference Full Session Transcript PDF Icon pdf Moderator: Margot Anderson (EIA) Speakers: Jeff Genzer (Duncan, Weinberg, Genzer & Pembroke, P.C.) Philip Hanser (Brattle Group) Shirley Neff (Center for Strategic and International Studies) Frank Rusco (U.S. Government Accountability Office Note: Concurrent sessions used a variety of presentation and round table discussion formats. All available presentations have been posted. Moderator and Speaker Bios and Presentations Margot Anderson Margot Anderson, Director of the Office of Energy Markets and End Use, Energy Information Administration. Prior to joining the Energy Information Administration, she was Deputy Assistant Secretary for Policy Analysis,

414

EIA - Energy Conferences & Presentations.  

U.S. Energy Information Administration (EIA) Indexed Site

0 0 EIA Conference 2009 Session 10: Greenhouse Gas Emissions: What's Next? Listen to Session: Audio of Session 1 from 2009 EIA Conference Full Session Transcript PDF Icon pdf Moderator: Howard Gruenspecht (EIA) Speakers: Joe Aldy (Executive Office of the President) Greg Dotson (House Committee on Energy and Commerce) Joe Goffman (Senate Committee on Environment and Public Works) Andrea Spring (House Committee on Energy and Commerce) Note: Concurrent sessions used a variety of presentation and round table discussion formats. All available presentations have been posted. Moderator and Speaker Bios and Presentations Howard Gruenspecht is Acting Administrator of the Energy Information Administration. Over the past 25 years, he has worked extensively on electricity policy issues, regulations affecting motor fuels and vehicles,

415

Second United Nations International Conference  

NLE Websites -- All DOE Office Websites (Extended Search)

Confidential until official release during Conference Confidential until official release during Conference A/CONF 15/P/729 Abstract (USA) 7 March 1958 ORIGINAL: ENGLISH HIGH-ENERGY PHYSICS WITH HYDROGEN BUBBLE CHAMBERS~ Prepared by Abstract , _ - - ' ~ u i s W. Akvarez . I e - 4 - - a c bubble chambers in high-energy physics experiments. This paper @.scusses recent experience with liquid hydrogen # - . . . 1 sify of California, Berkeley, California / This document is DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process

416

2011 Heat Rate Improvement Conference  

Science Conference Proceedings (OSTI)

With the rising cost of fuel and the strong possibility of CO2 emissions regulations and limitations in the near future, utilities and power generation companies are focusing on power plant heat rate and performance. The Electric Power Research Institute (EPRI) 17th Heat Rate Improvement Conference is the latest in a series of meetings designed to assist attendees in addressing problems with power plant performance and in identifying cost-effective solutions for achieving and sustaining heat rate improve...

2011-03-28T23:59:59.000Z

417

Fifth international fungus spore conference  

DOE Green Energy (OSTI)

This folio contains the proceedings of the Fifth International Fungal Spore Conference held August 17-21, 1991 at the Unicoi State Park at Helen, Georgia. The volume contains abstracts of each oral presentation as well as a collection of abstracts describing the poster sessions. Presentations were organized around the themes (1) Induction of Sporulation, (2) Nuclear Division, (3) Spore Formation, (4) Spore Release and Dispersal, and (4) Spore Germination.

Timberlake, W.E.

1993-04-01T23:59:59.000Z

418

The contrasting fission potential-energy structure of actinides and mercury isotopes  

E-Print Network (OSTI)

Fission-fragment mass distributions are asymmetric in fission of typical actinide nuclei for nucleon number $A$ in the range $228 \\lnsim A \\lnsim 258$ and proton number $Z$ in the range $90\\lnsim Z \\lnsim 100$. For somewhat lighter systems it has been observed that fission mass distributions are usually symmetric. However, a recent experiment showed that fission of $^{180}$Hg following electron capture on $^{180}$Tl is asymmetric. We calculate potential-energy surfaces for a typical actinide nucleus and for 12 even isotopes in the range $^{178}$Hg--$^{200}$Hg, to investigate the similarities and differences of actinide compared to mercury potential surfaces and to what extent fission-fragment properties, in particular shell structure, relate to the structure of the static potential-energy surfaces. Potential-energy surfaces are calculated in the macroscopic-microscopic approach as functions of fiveshape coordinates for more than five million shapes. The structure of the surfaces are investigated by use of an immersion technique. We determine properties of minima, saddle points, valleys, and ridges between valleys in the 5D shape-coordinate space. Along the mercury isotope chain the barrier heights and the ridge heights and persistence with elongation vary significantly and show no obvious connection to possible fragment shell structure, in contrast to the actinide region, where there is a deep asymmetric valley extending from the saddle point to scission. The mechanism of asymmetric fission must be very different in the lighter proton-rich mercury isotopes compared to the actinide region and is apparently unrelated to fragment shell structure. Isotopes lighter than $^{192}$Hg have the saddle point blocked from a deep symmetric valley by a significant ridge. The ridge vanishes for the heavier Hg isotopes, for which we would expect a qualitatively different asymmetry of the fragments.

Takatoshi Ichikawa; Akira Iwamoto; Peter Möller; Arnold J. Sierk

2012-03-09T23:59:59.000Z

419

Proceedings of the twenty-second annual conference on explosives and blasting technique. Volume 1  

Science Conference Proceedings (OSTI)

These proceedings contain 30 papers presented at the conference. Topics relate to productivity blasting in surface mining, dragline effectiveness, evaluation of production blasts, environmental effects of blast induced immissions, accidental explosions in blasting operations, explosive safety, tunnel excavation, and the use of video technology for shot analysis. Most papers have been processed separately for inclusion on the data base.

NONE

1996-12-01T23:59:59.000Z

420

Proceedings of the twenty-first annual conference on explosives and blasting technique. Volume 1  

SciTech Connect

These proceedings contain 34 papers presented at the conference. Topics relate to explosive fracturing for construction projects (tunnels, pipelines, dams), rock drilling for explosive fracturing, surface mining, rock fragmentation, environmental impacts, storage and transport of high explosives, underwater blasting, toxic fumes, and explosives malfunctions. Most papers have been processed separately for inclusion on the data base.

1995-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Proceedings of the twenty-first annual conference on explosives and blasting technique. Volume 2  

SciTech Connect

These proceedings contain 28 papers presented at the conference. Topics relate to drilling for explosive fracturing, pre-blast surveys, blasting regulations, underground and surface mining, tunneling, efficiency and optimization of explosive fracturing, blasting accidents, blast damage control, environmental control, and the use of explosive fracturing in remedial action. Many papers were processed separately for inclusion on the data base.

1995-12-31T23:59:59.000Z

422

Proceedings of the seventeenth annual conference on explosives and blasting technique. Volume 2  

SciTech Connect

Papers from this conference dealt with the following topics: surface and underground mine blasting, ground vibrations and blast effects, design for explosive fracturing of rock, sequential timing for blasting control, design for production optimization, use of blasting for abandoned mine reclamation, chemical explosives, lightning warning systems, magazine security, fire safety, and drilling equipment. Papers have been indexed separately for inclusion on the data base.

1991-01-01T23:59:59.000Z

423

Proceedings of the 2011 IEEE international vacuum electronics conference: book of abstracts  

Science Conference Proceedings (OSTI)

This book includes a unique panorama of latest advances in vacuum electronic devices and applications covered in plenary talks, contributed papers and posters. High power microwaves and microwave tubes were the two themes for the pre-conference tutorials. Papers relevant to INIS are indexed separately.

NONE

2011-07-01T23:59:59.000Z

424

1987 Oak Ridge model conference: Proceedings: Volume I, Part 2, Waste Management  

SciTech Connect

A conference sponsored by the United States Department of Energy (DOE) was held on Waste Mangement. Topics discussed were waste stabilization technologies regulations and standards, innovative treatment technology, waste stabilization projects. Individual projects are processed separately for the data bases. (CBS)

1987-01-01T23:59:59.000Z

425

1987 Oak Ridge model conference: Proceedings: Volume I, Part 3, Waste Management  

SciTech Connect

A conference sponsored by the United States Department of Energy (DOE), was held on waste management. Topics of discussion were transuranic waste management, chemical and physical treatment technologies, waste minimization, land disposal technology and characterization and analysis. Individual projects are processed separately for the data bases. (CBS)

1987-01-01T23:59:59.000Z

426

Twenty-ninth ORNL/DOE conference on analytical chemistry in energy technology. Abstracts of papers  

Science Conference Proceedings (OSTI)

This booklet contains separate abstracts of 55 individual papers presented at this conference. Different sections in the book are titled as follows: laser techniques; resonance ionization spectroscopy; laser applications; new developments in mass spectrometry; analytical chemistry of hazardous waste; and automation and data management. (PLG)

Not Available

1986-01-01T23:59:59.000Z

427

Second biomass conference of the Americas: Energy, environment, agriculture, and industry. Proceedings  

DOE Green Energy (OSTI)

This volume provides the proceedings for the Second Biomass Conference of the Americas: Energy, Environment, Agriculture, and Industry which was held August 21-24, 1995. The volume contains copies of full papers as provided by the researchers. Individual papers were separately indexed and abstracted for the database.

NONE

1995-01-01T23:59:59.000Z

428

Relational separation logic  

Science Conference Proceedings (OSTI)

In this paper, we present a Hoare-style logic for specifying and verifying how two pointer programs are related. Our logic lifts the main features of separation logic, from an assertion to a relation, and from a property about a single program to a relationship ... Keywords: Program verification, Relational reasoning, Schorr—Waite graph marking algorithm, Separation logic

Hongseok Yang

2007-05-01T23:59:59.000Z

429

Method for separating isotopes  

DOE Patents (OSTI)

Isotopes are separated by contacting a feed solution containing the isotopes with a cyclic polyether wherein a complex of one isotope is formed with the cyclic polyether, the cyclic polyether complex is extracted from the feed solution, and the isotope is thereafter separated from the cyclic polyether.

Jepson, B.E.

1975-10-21T23:59:59.000Z

430

URANIUM SEPARATION PROCESS  

DOE Patents (OSTI)

The separation of uranium from an aqueous solution containing a water soluble uranyl salt is described. The process involves adding an alkali thiocyanate to the aqueous solution, contacting the resulting solution with methyl isobutyl ketons and separating the resulting aqueous and organic phase. The uranium is extracted in the organic phase as UO/sub 2/(SCN)/sub/.

McVey, W.H.; Reas, W.H.

1959-03-10T23:59:59.000Z

431

Substituted polyacetylene separation membrane  

DOE Patents (OSTI)

A separation membrane useful for gas separation, particularly separation of C.sub.2+ hydrocarbons from natural gas. The invention encompasses the membrane itself, methods of making it and processes for using it. The membrane comprises a polymer having repeating units of a hydrocarbon-based, disubstituted polyacetylene, having the general formula: ##STR1## wherein R.sub.1 is chosen from the group consisting of C.sub.1 -C.sub.4 alkyl and phenyl, and wherein R.sub.2 is chosen from the group consisting of hydrogen and phenyl. In the most preferred embodiment, the membrane comprises poly(4-methyl-2-pentyne) ›PMP!. The membrane exhibits good chemical resistance and has super-glassy properties with regard to separating certain large, condensable permeant species from smaller, less-condensable permeant species. The membranes may also be useful in other fluid separations.

Pinnau, Ingo (Palo Alto, CA); Morisato, Atsushi (Tokyo, JP)

1998-01-13T23:59:59.000Z

432

Separators for flywheel rotors  

DOE Patents (OSTI)

A separator forms a connection between the rotors of a concentric rotor assembly. This separator allows for the relatively free expansion of outer rotors away from inner rotors while providing a connection between the rotors that is strong enough to prevent disassembly. The rotor assembly includes at least two rotors referred to as inner and outer flywheel rings or rotors. This combination of inner flywheel ring, separator, and outer flywheel ring may be nested to include an arbitrary number of concentric rings. The separator may be a segmented or continuous ring that abuts the ends of the inner rotor and the inner bore of the outer rotor. It is supported against centrifugal loads by the outer rotor and is affixed to the outer rotor. The separator is allowed to slide with respect to the inner rotor. It is made of a material that has a modulus of elasticity that is lower than that of the rotors. 10 figs.

Bender, D.A.; Kuklo, T.C.

1998-07-07T23:59:59.000Z

433

Separators for flywheel rotors  

DOE Patents (OSTI)

A separator forms a connection between the rotors of a concentric rotor assembly. This separator allows for the relatively free expansion of outer rotors away from inner rotors while providing a connection between the rotors that is strong enough to prevent disassembly. The rotor assembly includes at least two rotors referred to as inner and outer flywheel rings or rotors. This combination of inner flywheel ring, separator, and outer flywheel ring may be nested to include an arbitrary number of concentric rings. The separator may be a segmented or continuous ring that abuts the ends of the inner rotor and the inner bore of the outer rotor. It is supported against centrifugal loads by the outer rotor and is affixed to the outer rotor. The separator is allowed to slide with respect to the inner rotor. It is made of a material that has a modulus of elasticity that is lower than that of the rotors.

Bender, Donald A. (Dublin, CA); Kuklo, Thomas C. (Oakdale, CA)

1998-01-01T23:59:59.000Z

434

Substituted polyacetylene separation membrane  

DOE Patents (OSTI)

A separation membrane is described which is useful for gas separation, particularly separation of C{sub 2+} hydrocarbons from natural gas. The invention encompasses the membrane itself, methods of making it and processes for using it. The membrane comprises a polymer having repeating units of a hydrocarbon-based, disubstituted polyacetylene, having the general formula shown in the accompanying diagram, wherein R{sub 1} is chosen from the group consisting of C{sub 1}-C{sub 4} alkyl and phenyl, and wherein R{sub 2} is chosen from the group consisting of hydrogen and phenyl. In the most preferred embodiment, the membrane comprises poly(4-methyl-2-pentyne) [PMP]. The membrane exhibits good chemical resistance and has super-glassy properties with regard to separating certain large, condensable permeant species from smaller, less-condensable permeant species. The membranes may also be useful in other fluid separations. 4 figs.

Pinnau, I.; Morisato, Atsushi

1998-01-13T23:59:59.000Z

435

Krakow conference on low emissions sources: Proceedings  

SciTech Connect

The Krakow Conference on Low Emission Sources presented the information produced and analytical tools developed in the first phase of the Krakow Clean Fossil Fuels and Energy Efficiency Program. This phase included: field testing to provide quantitative data on missions and efficiencies as well as on opportunities for building energy conservation; engineering analysis to determine the costs of implementing pollution control; and incentives analysis to identify actions required to create a market for equipment, fuels, and services needed to reduce pollution. Collectively, these Proceedings contain reports that summarize the above phase one information, present the status of energy system management in Krakow, provide information on financing pollution control projects in Krakow and elsewhere, and highlight the capabilities and technologies of Polish and American companies that are working to reduce pollution from low emission sources. It is intended that the US reader will find in these Proceedings useful results and plans for control of pollution from low emission sources that are representative of heating systems in central and Eastern Europe. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Pierce, B.L.; Butcher, T.A. [eds.

1995-12-31T23:59:59.000Z

436

eConf: Electronic Conference Proceedings Archive  

NLE Websites -- All DOE Office Websites (Extended Search)

eConf - Electronic Conference Proceedings Archive eConf - Electronic Conference Proceedings Archive Electronic Conference Proceedings Archive eConf Home Purpose & Philosophy Search eConf How to Cite For Editors For Librarians This site provides a fully electronic, Web-accessible archive for the proceedings of scientific conferences in High-Energy Physics and related fields. In its present stage, the site is maintained by Technical Information Services at SLAC as a free service to the scientific community. Our intention is to provide a home for electronically published conference proceedings. Through this, we hope to promote a permanent change in the way that scientific conference proceedings are published and accessed. bullet Purpose and philosophy bullet Search for an eConf proceedings or proceedings article

437

Chromatographic hydrogen isotope separation  

DOE Patents (OSTI)

Intermetallic compounds with the CaCu.sub.5 type of crystal structure, particularly LaNiCo.sub.4 and CaNi.sub.5, exhibit high separation factors and fast equilibrium times and therefore are useful for packing a chromatographic hydrogen isotope separation colum. The addition of an inert metal to dilute the hydride improves performance of the column. A large scale mutli-stage chromatographic separation process run as a secondary process off a hydrogen feedstream from an industrial plant which uses large volumes of hydrogen can produce large quantities of heavy water at an effective cost for use in heavy water reactors.

Aldridge, Frederick T. (Livermore, CA)

1981-01-01T23:59:59.000Z

438

Potentiometric Sensor for Real-Time Remote Surveillance of Actinides in Molten Salts  

SciTech Connect

A potentiometric sensor is being developed at the Idaho National Laboratory for real-time remote surveillance of actinides during electrorefining of spent nuclear fuel. During electrorefining, fuel in metallic form is oxidized at the anode while refined uranium metal is reduced at the cathode in a high temperature electrochemical cell containing LiCl-KCl-UCl3 electrolyte. Actinides present in the fuel chemically react with UCl3 and form stable metal chlorides that accumulate in the electrolyte. This sensor will be used for process control and safeguarding of activities in the electrorefiner by monitoring the concentrations of actinides in the electrolyte. The work presented focuses on developing a solid-state cation conducting ceramic sensor for detecting varying concentrations of trivalent actinide metal cations in eutectic LiCl-KCl molten salt. To understand the basic mechanisms for actinide sensor applications in molten salts, gadolinium was used as a surrogate for actinides. The ß?-Al2O3 was selected as the solid-state electrolyte for sensor fabrication based on cationic conductivity and other factors. In the present work Gd3+-ß?-Al2O3 was prepared by ion exchange reactions between trivalent Gd3+ from GdCl3 and K+-, Na+-, and Sr2+-ß?-Al2O3 precursors. Scanning electron microscopy (SEM) was used for characterization of Gd3+-ß?-Al2O3 samples. Microfocus X-ray Diffraction (µ-XRD) was used in conjunction with SEM energy dispersive X-ray spectroscopy (EDS) to identify phase content and elemental composition. The Gd3+-ß?-Al2O3 materials were tested for mechanical and chemical stability by exposing them to molten LiCl-KCl based salts. The effect of annealing on the exchanged material was studied to determine improvements in material integrity post ion exchange. The stability of the ß?-Al2O3 phase after annealing was verified by µ-XRD. Preliminary sensor tests with different assembly designs will also be presented.

Natalie J. Gese; Jan-Fong Jue; Brenda E. Serrano; Guy L. Fredrickson

2012-07-01T23:59:59.000Z

439

NETL: Conference Proceedings - 2007 Mercury Control Technology Conference  

NLE Websites -- All DOE Office Websites (Extended Search)

2007 Mercury Control Technology Conference 2007 Mercury Control Technology Conference December 11-13, 2007 Table of Contents Disclaimer Papers and Presentations Overview Sorbent Injection Panel Discussion #1: Sorbents for Mercury Control Mercury Oxidaton and Co-Removal with FGD Systems By-Product Characterization/Management Panel Discussion #2: Mercury Measurements / CEMS Other Mercury Control Technology Panel Discussion #3: Non-Sorbent Mercury Control Poster Presentations Disclaimer This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government or any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

440

Establishment of uncertainty ranges and probability distributions of actinide solubilities for performance assessment in the Waste Isolation Pilot Plant (WIPP).  

Science Conference Proceedings (OSTI)

The Fracture-Matrix Transport (FMT) code developed at Sandia National Laboratories solves chemical equilibrium problems using the Pitzer activity coefficient model with a database containing actinide species. The code is capable of predicting actinide solubilities at 25 C in various ionic-strength solutions from dilute groundwaters to high-ionic-strength brines. The code uses oxidation state analogies, i.e., Am(III) is used to predict solubilities of actinides in the +III oxidation state; Th(IV) is used to predict solubilities of actinides in the +IV state; Np(V) is utilized to predict solubilities of actinides in the +V state. This code has been qualified for predicting actinide solubilities for the Waste Isolation Pilot Plant (WIPP) Compliance Certification Application in 1996, and Compliance Re-Certification Applications in 2004 and 2009. We have established revised actinide-solubility uncertainty ranges and probability distributions for Performance Assessment (PA) by comparing actinide solubilities predicted by the FMT code with solubility data in various solutions from the open literature. The literature data used in this study include solubilities in simple solutions (NaCl, NaHCO{sub 3}, Na{sub 2}CO{sub 3}, NaClO{sub 4}, KCl, K{sub 2}CO{sub 3}, etc.), binary mixing solutions (NaCl+NaHCO{sub 3}, NaCl+Na{sub 2}CO{sub 3}, KCl+K{sub 2}CO{sub 3}, etc.), ternary mixing solutions (NaCl+Na{sub 2}CO{sub 3}+KCl, NaHCO{sub 3}+Na{sub 2}CO{sub 3}+NaClO{sub 4}, etc.), and multi-component synthetic brines relevant to the WIPP.

Long, Jennifer; Nowak, Jim; Ismail, Ahmed E.; Brush, Laurence H.; Xiong, Yongliang

2010-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

2012 EPRI Fossil Life Assessment Conference Proceedings  

Science Conference Proceedings (OSTI)

The International Conference on Advances in Condition and Remaining Life Assessment for Fossil Power plants – Coal, Gas and HRSG was hosted in October 2012 in Hilton Head, SC, USA.  This conference was the latest of a series of conferences addressing aging equipment in Fossil Power Plants dating back to the early 1980’s.  Condition and remaining life assessment (historically referred to as CARLA) technology has assumed great importance in the context of the reliability, ...

2013-12-23T23:59:59.000Z

442

EIA - Energy Conferences & Presentations.  

U.S. Energy Information Administration (EIA) Indexed Site

Presentations, Testimony, Events Presentations, Testimony, Events EIA Conference 2009 Tuesday, April 7 See each session for audio and video presentations! Plenary Session Welcome - Howard Gruenspecht Acting Administrator, Energy Information Administration Keynote Address; The Energy Problem - Dr. Steven Chu, Secretary of Energy The Economics of an Integrated World Oil Market - William D. Nordhaus, Sterling Professor of Economics, Yale University Energy in a Carbon-Constrained World - John W. Rowe, Chairman and Chief Executive Officer, Exelon Corporation Concurrent Sessions 1. The Future for Transport Demand 2. What's Ahead for Natural Gas Markets? Moderator: Andy Kydes (EIA) Moderator: Steve Harvey (EIA) Speakers: Lew Fulton (International Energy Agency) David Greene (Oak Ridge National Laboratory)

443

Proceedings of NHA Annual Conferences  

SciTech Connect

The Proceedings of "Hydrogen: A Clean Energy Choice" and the 16th Annual U.S. Hydrogen Conference, "Partnering for the Global Hydrogen Future" include the presentations of high-level keynote speakers from the U.S. Department of Energy, the state government of California, Ambassadors and Executives of large corporations and emerging companies all presenting their vision on a future fueled by hydrogen. Parallel technical sessions informed attendees of developments in hydrogen technology R&D, commercial product development and market readiness. Persentations of the Student Design Competition Finalists are also included.

Debbi L. Smith

2004-06-30T23:59:59.000Z

444

Proceedings of the sixteenth ACM conference on Conference on information and knowledge management  

Science Conference Proceedings (OSTI)

It is my great pleasure to welcome you to CIKM 2007 -- the 16th ACM Conference on Information and Knowledge Management. The Organizing Committee assumed the role of affirming CIKM as the premier conference at the confluence of information retrieval, ...

Mário J. Silva; André O. Falcăo; Alberto H. F. Laender; Ricardo Baeza-Yates; Deborah L. McGuinness; Bjorn Olstad; Řystein Haug Olsen

2007-11-01T23:59:59.000Z

445

Separation by solvent extraction  

DOE Patents (OSTI)

17. A process for separating fission product values from uranium and plutonium values contained in an aqueous solution, comprising adding an oxidizing agent to said solution to secure uranium and plutonium in their hexavalent state; contacting said aqueous solution with a substantially water-immiscible organic solvent while agitating and maintaining the temperature at from -1.degree. to -2.degree. C. until the major part of the water present is frozen; continuously separating a solid ice phase as it is formed; separating a remaining aqueous liquid phase containing fission product values and a solvent phase containing plutonium and uranium values from each other; melting at least the last obtained part of said ice phase and adding it to said separated liquid phase; and treating the resulting liquid with a new supply of solvent whereby it is practically depleted of uranium and plutonium.

Holt, Jr., Charles H. (Kennewick, WA)

1976-04-06T23:59:59.000Z

446

Optimal distance separating halfspace  

E-Print Network (OSTI)

Plastria & Carrizosa / Optimal distance separating halfspace. 2. 1 Gauge Distance to a Hyperplane. Let ? be a gauge on Rd with unit ball B, i.e. B is a compact ...

447

Gas-separation process  

DOE Patents (OSTI)

A process for separating condensable organic components from gas streams. The process makes use of a membrane made from a polymer material that is glassy and that has an unusually high free volume within the polymer material.

Toy, Lora G. (San Francisco, CA); Pinnau, Ingo (Palo Alto, CA); Baker, Richard W. (Palo Alto, CA)

1994-01-01T23:59:59.000Z

448

Molten salt electrolyte separator  

DOE Patents (OSTI)

A molten salt electrolyte/separator for battery and related electrochemical systems including a molten electrolyte composition and an electrically insulating solid salt dispersed therein, to provide improved performance at higher current densities and alternate designs through ease of fabrication.

Kaun, Thomas D. (New Lenox, IL)

1996-01-01T23:59:59.000Z

449

DIAMIDE DERIVATIVES OF DIPICOLINIC ACID AS ACTINIDE AND LANTHANIDE EXTRACTANTS IN A VARIATION OF THE UNEX PROCESS  

SciTech Connect

The Universal Extraction (UNEX) process has been developed for simultaneous extraction of cesium, strontium, and actinides from acidic solutions. This process utilizes an extractant consisting of 0.08 M chlorinated cobalt dicarbollide (HCCD), 0.007-0.02 M polyethylene glycol (PEG-400), and 0.02 M diphenyl-N,N-di-n-butylcarbamoylmethylphosphine oxide (Ph2CMPO) in the diluent trifluoromethylphenyl sulfone (CF3C6H5SO2, designated FS-13) and provides simultaneous extraction of Cs, Sr, actinides, and lanthanides from HNO3 solutions. The UNEX process is of limited utility for processing acidic solutions containing large quantities of lanthanides and/or actinides, such as dissolved spent nuclear fuel solutions. These constraints are primarily attributed to the limited concentrations of CMPO (a maximum of ~0.02 M) in the organic phase and limited solubility of the CMPO-metal complexes. As a result, alternative actinide and lanthanide extractants are being investigated for use with HCCD as an improvement for waste processing and for applications where higher concentrations of the metals are present. Our preliminary results indicate that diamide derivatives of dipicolinic acid may function as efficient actinide and lanthanide extractants. The results to be presented indicate that, of the numerous diamides studied to date, the tetrabutyldiamide of dipicolinic acid, TBDPA, shows the most promise as an alternative actinide/lanthanide extractant in the UNEX process.

D. R. Peterman; R. S. Herbst; J. D. Law; R. D. Tillotson; T. G. Garn; T. A. Todd; V. N. Romanovskiy; V. A. Babain; M. Yu. Alyapyshev; I. V. Smirnov

2007-09-01T23:59:59.000Z

450

DOE National Interest Electric Transmission Corridors Conference  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

National Interest Electric Transmission Corridors Conference March 29, 2006 Hilton Garden Hotel Chicago, IL William H. Whitehead General Manager, Transmission Strategy PJM...

451

Conference Information Data Service | Data.gov  

NLE Websites -- All DOE Office Websites (Extended Search)

Challenges Resources Blogs Let's Talk Energy Beta You are here Data.gov Communities Energy Data Conference Information Data Service Dataset Summary Description Contains...

452

EM SSAB Conference Calls- November 20, 2008  

Energy.gov (U.S. Department of Energy (DOE))

Minutes and highlights of the Environmental Management (EM) Site Specific Advisory Board's (SSAB) Bi-Monthly conference call including Participants, DOE-HQ Representatives, Opening Remarks, Program...

453

EM SSAB Conference Calls- December 7, 2011  

Energy.gov (U.S. Department of Energy (DOE))

Minutes and highlights of the Environmental Management (EM) Site Specific Advisory Board's (SSAB) Bi-Monthly conference call including Participants, DOE-HQ Representatives, Opening Remarks, Program...

454

20th National Information Systems Security Conference  

Science Conference Proceedings (OSTI)

... 7 and banquet on Oct. 8. The fee for the pre-conference workshops on Oct. 6 is $100. To receive registration information, contact: ...

455

Special Features Program - 23rd NISS Conference  

Science Conference Proceedings (OSTI)

... 7 pm : Banquet The conference banquet will be held on Wednesday evening, beginning with a cash bar reception at 6pm, and followed by dinner ...

2001-07-05T23:59:59.000Z

456

The Gordon conference on mammalian DNA repair  

SciTech Connect

A brief overview of the Gordon Conference on Mammalian Repair held February 1-5, 1993 in Ventura, California is presented.

Cleaver, J.E.; Smerdon, M.J.

1993-12-31T23:59:59.000Z

457

Energy Storage Systems 2010 Update Conference Presentations ...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

by SNL's Stan Atcitty, are below. ESS 2010 Update Conference - Demonstration of Microgrids with Storage & Senior Design Class - Satish Ranade, NMSU.pdf ESS 2010 Update...

458

2005 American Conference on Theoretical Chemistry  

Science Conference Proceedings (OSTI)

The materials uploaded are meant to serve as final report on the funds provided by DOE-BES to help sponsor the 2005 American Conference on Theoretical Chemistry.

Carter, Emily A

2006-11-19T23:59:59.000Z

459

1999 Oil & Gas Conference Proceedings - Contents  

NLE Websites -- All DOE Office Websites (Extended Search)

Energy's Federal Energy Technology Center and National Petroleum Technology Office 1999 Oil & Gas Technology Options Conference Proceedings for Producer Survival Contents This...

460

2000 Electronic Materials Conference: Airline Information  

Science Conference Proceedings (OSTI)

Sponsored by the Electronic Materials Committee of The Minerals, Metals & Materials Society (TMS), the 42nd Electronic Materials Conference (EMC) will be

Note: This page contains sample records for the topic "actinide separations conference" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


461

60th Annual Device Research Conference  

Science Conference Proceedings (OSTI)

I plan to attend the conference. Please send me future announcements. Name. Affiliation. Address. City. State/Province. Zip/Postal Code. Country. Telephone.

462

Text REtrieval Conference (TREC) Frequently Asked ...  

Science Conference Proceedings (OSTI)

... The TREC Conference series is co-sponsored by the NIST Information Technology Laboratory's (ITL) Retrieval Group of the Information Access ...

463

EM SSAB Conference Calls- August 15, 2012  

Energy.gov (U.S. Department of Energy (DOE))

Minutes and highlights of the Environmental Management (EM) Site Specific Advisory Board's (SSAB) Bi-Monthly conference call including Participants, DOE-HQ Representatives, Opening Remarks, Program...

464

EIA Energy Conferences & Presentations, April 8, 2009  

U.S. Energy Information Administration (EIA) Indexed Site

EIA Energy Conferences & Presentations, April 8, 2009 Session 7: "Energy Data Needs" Note: Recorders did not pick up introduction of panel (see biographies for details on the...

465

6th World Conference on Detergents  

Science Conference Proceedings (OSTI)

Presentations from the 6th World Conference on Detergents, Defining and Designing our Future , 9-12 October 2006, Montreux, Switzerland. ...

466

EM SSAB Conference Calls- September 19, 2011  

Energy.gov (U.S. Department of Energy (DOE))

Minutes and highlights of the Environmental Management (EM) Site Specific Advisory Board's (SSAB) Bi-Monthly conference call including Participants, DOE-HQ Representatives, Opening Remarks, Program...

467

2000 Electronic Materials Conference: Destination Information and ...  

Science Conference Proceedings (OSTI)

... 2000 · 42ND ELECTRONIC MATERIALS CONFERENCE · Denver, Colorado ... will be held June 21-23, 2000, at the University of Denver in Denver, Colorado.

468

000 Electronic Materials Conference: Student Information  

Science Conference Proceedings (OSTI)

... 2000 · 42ND ELECTRONIC MATERIALS CONFERENCE · Denver, Colorado ... will be held June 21-23, 2000, at the University of Denver in Denver, Colorado.

469

LATINO Magazine Nuestro Futuro Latino Education Conference  

Energy.gov (U.S. Department of Energy (DOE))

"Conference participants will join in discussions with experts drawn from academia, business, government, and Hispanic organizations such as SHPE and Great minds in STEM. Invited panelists and...

470

FOURTH ANNUAL CONFERENCE ON FIRE RESEARCH  

Science Conference Proceedings (OSTI)

... NOTE: The Annual Conference on Fire Research held October 22-24 ... We are now replacing the laser with a high intensity black ... Program Objectives ...

2008-11-20T23:59:59.000Z

471

20th National Information Systems Security Conference  

Science Conference Proceedings (OSTI)

... NIST does not accept any other credit cards. ... and CD-ROM of the conference proceedings will be ... In January 1981, the National Computer Security ...

472

successfully demonstrated the separation  

NLE Websites -- All DOE Office Websites (Extended Search)

successfully demonstrated the separation and capture of 90 percent successfully demonstrated the separation and capture of 90 percent of the c arbon dioxide (CO 2 ) from a pulve rized coal plant. In t he ARRA-funded project, Membrane Technology and Research Inc. (MTR) and its partners tested the Polaris(tm) membrane system, which uses a CO 2 -selective polymeric membrane material and module to capture CO 2 from a plant's flue gas. Since the Polaris(tm) membranes

473

The State of Environmental Justice in America 2009 Conference | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

09 Conference 09 Conference The State of Environmental Justice in America 2009 Conference The State of Environmental Justice in America 2009 Conference EJ Conference, Inc. Presents The State of Environmental Justice in America 2009 Conference To volunteer or for sponsorship opportunities and additional information, contact: John Rosenthall. E-mail: ejinamerica@hotmail.com 2009 Environmental Justice Conference Environmental Justice Blog Draft Agenda and Call for Presentations (updated 05/15/2009) Conference Flier Newsletter - First Issue Newsletter - Second Issue Newsletter - Third Issue Newsletter - Fourth Issue (Special Earth Day Edition) Newsletter - Fifth Issue (Driving Directions) Newsletter - Sixth Issue (Conference Summary) Meet the Agencies and Exhibit Registration Form

474

Method for extracting lanthanides and actinides from acid solutions by modification of Purex solvent  

DOE Patents (OSTI)

A process is described for the recovery of actinide and lanthanide values from aqueous solutions with an extraction solution containing an organic extractant having the formula as shown in a diagram where [phi] is phenyl, R[sup 1] is a straight or branched alkyl or alkoxyalkyl containing from 6 to 12 carbon atoms and R[sup 2] is an alkyl containing from 3 to 6 carbon atoms and phase modifiers in a water-immiscible hydrocarbon diluent. The addition of the extractant to the Purex process extractant, tri-n-butylphosphate in normal paraffin hydrocarbon diluent, will permit the extraction of multivalent lanthanide and actinide values from 0.1 to 12.0 molar acid solutions. 6 figs.

Horwitz, E.P.; Kalina, D.G.

1986-03-04T23:59:59.000Z

475

Joint Actinide Shock Physics Experimental Research Facility Restart Operational Readiness Review Pre- Visit  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NNSS-2011-04-28 NNSS-2011-04-28 Site: Nevada National Security Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Joint Actinide Shock Physics Experimental Research Facility Restart Operational Readiness Review Pre- Visit Dates of Activity: 04/25/2011 - 04/28/2011 Report Preparer William Macon Activity Description/Purpose: In coordination with the National Nuclear Security Administration (NNSA) Service Center, the Office of Health, Safety and Security (HSS) site lead participated in a pre-visit for the NNSA Operational Readiness Review (ORR) of the Joint Actinide Shock Physics Experimental Research (JASPER) facility restart conducted April 25-28, 2011. The site lead also participated

476

Dounreay PFR irradiation history for the joint US/UK actinide sample exposures  

Science Conference Proceedings (OSTI)

The operating history of the Dounreay Prototype Fast Reactor is presented to the extent that it is relevant to the irradiation of actinide specimens that were subsequently analyzed at Oak Ridge National Laboratory (ORNL). Three fuel pins with actinide samples were irradiated from July 1982 to July 1988 and returned to ORNL for analysis. They contained isotopes of elements from thorium to curium. The times when each of these fuel pins were in the reactor core are described as are the operating power levels and neutron spectra. The appendices give daily power levels of the reactor as well as six-group neutron energy spectra for various times and axial positions in the core.

Raman, S.; Murphy, B.D.; Nestor, C.W. Jr. [and others

1995-07-01T23:59:59.000Z

477

Method for extracting lanthanides and actinides from acid solutions by modification of purex solvent  

SciTech Connect

A process for the recovery of actinide and lanthanide values from aqueous solutions with an extraction solution containing an organic extractant having the formula: ##STR1## where .phi. is phenyl, R.sup.1 is a straight or branched alkyl or alkoxyalkyl containing from 6 to 12 carbon atoms and R.sup.2 is an alkyl containing from 3 to 6 carbon atoms and phase modifiers in a water-immiscible hydrocarbon diluent. The addition of the extractant to the Purex process extractant, tri-n-butylphosphate in normal paraffin hydrocarbon diluent, will permit the extraction of multivalent lanthanide and actinide values from 0.1 to 12.0 molar acid solutions.

Horwitz, E. Philip (Naperville, IL); Kalina, Dale G. (Naperville, IL)

1986-01-01T23:59:59.000Z

478

Evaluation of extractants and chelating resins in polishing actinide-contaminated waste streams  

SciTech Connect

At the Los Alamos National Laboratory Plutonium Facility, anion exchange is used for recovering plutonium from nitric acid solutions. Although this approach recovers >99%, the trace amounts of plutonium and other actinides remaining in the effluent require additional processing. We are doing research to develop a secondary unit operation that can directly polish the effluent so that actinide levels are reduced to below the maximum allowed for facility discharge. We selected solvent extraction, the only unit operation that can meet the stringent process requirements imposed; several carbonyl and phosphoryl extractants were evaluated and their performance characterized. We also investigated various engineering approaches for solvent extraction; the most promising was a chelating resin loaded with extractant. Our research now focuses on the synthesis of malonamides, and our goal is to bond these extractants to a resin matrix. 7 refs., 12 figs., 1 tab.

Schreiber, S.B.; Dunn, S.L.; Yarbro, S.L.

1991-06-01T23:59:59.000Z

479

Fission barriers in actinides in covariant density functional theory: the role of triaxiality  

E-Print Network (OSTI)

Relativistic mean field theory allowing for triaxial deformations is applied for a systematic study of fission barriers in the actinide region. Different pairing schemes are studied in details and it is shown that covariant density functional theory is able to describe fission barriers on a level of accuracy comparable with non-relativistic calculations, even with the best phenomenological macroscopic+microscopic approaches. Triaxiality in the region of the first saddle plays a crucial role in achieving that.

H. Abusara; A. V. Afanasjev; P. Ring

2010-10-09T23:59:59.000Z

480

Mantle Helium And Carbon Isotopes In Separation Creek Geothermal Springs,  

Open Energy Info (EERE)

Mantle Helium And Carbon Isotopes In Separation Creek Geothermal Springs, Mantle Helium And Carbon Isotopes In Separation Creek Geothermal Springs, Three Sisters Area, Central Oregon- Evidence For Renewed Volcanic Activity Or A Long Term Steady State System(Question) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Conference Paper: Mantle Helium And Carbon Isotopes In Separation Creek Geothermal Springs, Three Sisters Area, Central Oregon- Evidence For Renewed Volcanic Activity Or A Long Term Steady State System(Question) Details Activities (1) Areas (1) Regions (0) Abstract: Here we present the helium and carbon isotope results from the initial study of a fluid chemistry-monitoring program started in the summer of 2001 near the South Sister volcano in central Oregon. The Separation Creek area which is several miles due west of the volcano is the locus of

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481

Fundamental Thermodynamics of Actinide-Bearing Mineral Waste Forms - Final Report  

Science Conference Proceedings (OSTI)

The end of the Cold War raised the need for the technical community to be concerned with the disposition of excess nuclear weapon material. The plutonium will either be converted into mixed-oxide fuel for use in nuclear reactors or immobilized in glass or ceramic waste forms and placed in a repository. The stability and behavior of plutonium in the ceramic materials as well as the phase behavior and stability of the ceramic material in the environment is not well established. In order to provide technically sound solutions to these issues, thermodynamic data are essential in developing an understanding of the chemistry and phase equilibria of the actinide-bearing mineral waste form materials proposed as immobilization matrices. Mineral materials of interest include zircon, zirconolite, and pyrochlore. High temperature solution calorimetry is one of the most powerful techniques, sometimes the only technique, for providing the fundamental thermodynamic data needed to establish optimum material fabrication parameters, and more importantly understand and predict the behavior of the mineral materials in the environment. The purpose of this project is to experimentally determine the enthalpy of formation of actinide orthosilicates, the enthalpies of formation of actinide substituted zirconolite and pyrochlore, and develop an understanding of the bonding characteristics and stabilities of these materials.

Williamson, Mark A.; Ebbinghaus, Bartley B.; Navrotsky, Alexandra

2001-03-01T23:59:59.000Z

482

JOWOG 22/2 - Actinide Chemical Technology (July 9-13, 2012)  

Science Conference Proceedings (OSTI)

The Plutonium Science and Manufacturing Directorate provides world-class, safe, secure, and reliable special nuclear material research, process development, technology demonstration, and manufacturing capabilities that support the nation's defense, energy, and environmental needs. We safely and efficiently process plutonium, uranium, and other actinide materials to meet national program requirements, while expanding the scientific and engineering basis of nuclear weapons-based manufacturing, and while producing the next generation of nuclear engineers and scientists. Actinide Process Chemistry (NCO-2) safely and efficiently processes plutonium and other actinide compounds to meet the nation's nuclear defense program needs. All of our processing activities are done in a world class and highly regulated nuclear facility. NCO-2's plutonium processing activities consist of direct oxide reduction, metal chlorination, americium extraction, and electrorefining. In addition, NCO-2 uses hydrochloric and nitric acid dissolutions for both plutonium processing and reduction of hazardous components in the waste streams. Finally, NCO-2 is a key team member in the processing of plutonium oxide from disassembled pits and the subsequent stabilization of plutonium oxide for safe and stable long-term storage.

Jackson, Jay M. [Los Alamos National Laboratory; Lopez, Jacquelyn C. [Los Alamos National Laboratory; Wayne, David M. [Los Alamos National Laboratory; Schulte, Louis D. [Los Alamos National Laboratory; Finstad, Casey C. [Los Alamos National Laboratory; Stroud, Mary Ann [Los Alamos National Laboratory; Mulford, Roberta Nancy [Los Alamos National Laboratory; MacDonald, John M. [Los Alamos National Laboratory; Turner, Cameron J. [Los Alamos National Laboratory; Lee, Sonya M. [Los Alamos National Laboratory

2012-07-05T23:59:59.000Z

483

Configuration adjustment potential of the Very High Temperature Reactor prismatic cores with advanced actinide fuels  

E-Print Network (OSTI)

Minor actinides represent the long-term radiotoxicity of nuclear wastes. As one of their potential incineration options, partitioning and transmutation in fission reactors are seriously considered worldwide. If implemented, these technologies could also be a source of nuclear fuel materials required for sustainability of nuclear energy. The objective of this research was to evaluate performance characteristics of Very High Temperature Reactors (VHTRs) and their variations due to configuration adjustments targeting achievability of spectral variations. Th