Sample records for repository leachate collection

  1. Energy Systems Laboratory: Building a Model Repository Collection

    E-Print Network [OSTI]

    Koenig, Jay; Haberl, Jeff S.; Gilman, Don; Hughes, Sherrie

    2008-06-05T23:59:59.000Z

    . The Energy Systems Laboratory collection in the Texas A&M Digital Repository is unique in a number of ways. After first contacting the library in March 2005, the ESL became one of Texas A&M's earliest adopters of the repository. The collection is very diverse...

  2. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

    E-Print Network [OSTI]

    Recanati, Catherine

    Science Arts & Métiers (SAM) is an open access repository that collects the work of Arts et Métiers-deposited version published in: http://sam.ensam.eu Handle ID: .http://hdl.handle.net/10985/7554 To cite this version : Carole BOUCHARD - Emotion finds a way to users from designers: assessing product images

  3. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Science Arts & Métiers (SAM) is an open access repository that collects the work of Arts et Métiers-deposited version published in: http://sam.ensam.eu Handle ID: .http://hdl.handle.net/10985/7602 To cite this version : Céline MOUGENOT, Carole BOUCHARD, Améziane AOUSSAT, Steve WESTERMAN - Inspiration, images

  4. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

    E-Print Network [OSTI]

    Boyer, Edmond

    Science Arts & Métiers (SAM) is an open access repository that collects the work of Arts et Métiers-deposited version published in: http://sam.ensam.eu Handle ID: .http://hdl.handle.net/10985/7554 To cite finds a way to users from designers: assessing product images to convey designer's emotion - Journal

  5. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Science Arts & Métiers (SAM) is an open access repository that collects the work of Arts et Métiers-deposited version published in: http://sam.ensam.eu Handle ID: .http://hdl.handle.net/10985/7815 To cite with the FE method using the geometry reconstruction from images of the microstructure. Nevertheless, it can

  6. Update on Hilo Landfill Leachate TUpdate on Hilo Landfill Leachate TUpdate on Hilo Landfill Leachate TUpdate on Hilo Landfill Leachate TUpdate on Hilo Landfill Leachate Treatment Studyreatment Studyreatment Studyreatment Studyreatment Study continued on p

    E-Print Network [OSTI]

    Update on Hilo Landfill Leachate TUpdate on Hilo Landfill Leachate TUpdate on Hilo Landfill Leachate TUpdate on Hilo Landfill Leachate TUpdate on Hilo Landfill Leachate Treatment Studyreatment, the County of Hawaii is considering an expansion of the South Hilo Sanitary Landfill (SHSL

  7. Open Archive Toulouse Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    to the repository administrator: staff-oatao@inp-toulouse.fr #12;Synthesis process of nanowired Al/CuO thermite M occurred at 515 and 667 1C and total energy release of this thermite is 10 kJ/cm3 . 1. Introduction- mances of the optimized Al/CuO nanowired thermite are characterized using DSC and DTA to determine

  8. Open Archive Toulouse Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    has been paid to the manage- ment of spent nuclear fuel in a safe, economic and proliferation for recovery of actinides from spent nuclear fuel. The fuel is anodically dissolved to the molten salt to direct disposal of spent fuel in deep geological repositories. Application of the P&T ap- proach would

  9. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    and Peigney, Alain (2011) Spark plasma sintering of alumina: Study of parameters, formal sintering analysis to the repository administrator: staff-oatao@inp-toulouse.fr. #12;Spark plasma sintering of alumina: Study Toulouse cedex 9, France Abstract The spark plasma sintering (SPS) of an undoped commercial a-Al2O3 powder

  10. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    , Catherine and Guérit, Nathalieand Pébère, Nadine (2010) Corrosion protection mechanisms of carbon steel to the repository administrator: staff-oatao@inp-toulouse.fr. #12;Corrosion protection mechanisms of carbon steel performed on scratched samples revealed the inhibitive action of IBA at the carbon steel/coating interface

  11. Coal pile leachate treatment

    SciTech Connect (OSTI)

    Davis, E C; Kimmitt, R R

    1982-09-01T23:59:59.000Z

    The steam plant located at the Oak Ridge National Laboratory was converted from oil- to coal-fired boilers. In the process, a diked, 1.6-ha coal storage yard was constructed. The purpose of this report is to describe the treatment system designed to neutralize the estimated 18,000 m/sup 3/ of acidic runoff that will be produced each year. A literature review and laboratory treatability study were conducted which identified two treatment systems that will be employed to neutralize the acidic runoff. The first, a manually operated system, will be constructed at a cost of $200,000 and will operate for an interim period of four years. This system will provide for leachate neutralization until a more automated system can be brought on-line. The second, a fully automated system, is described and will be constructed at an estimated cost of $650,000. This automated runoff treatment system will ensure that drainage from the storage yard meets current National Pollutant Discharge Elimination System Standards for pH and total suspended solids, as well as future standards, which are likely to include several metals along with selected trace elements.

  12. Statistical comparison of leachate from hazardous, codisposal, and municipal solid waste landfills

    SciTech Connect (OSTI)

    Gibbons, R.D.; Dolan, D.G.; May, H.; O'Leary, K.; O'Hara, R.

    1999-09-30T23:59:59.000Z

    There has been considerable debate regarding the chemical characterization of landfill leachate in general and the comparison of various types of landfill leachate (e.g., hazardous, codisposal, and municipal) in particular. For example, the preamble to the US EPA Subtitle D regulation (40 CFR Parts 257 and 258) suggests that there are no significant differences between the number and concentration of toxic constituents in hazardous versus municipal solid waste landfill leachate. The purpose of this paper is to statistically test this hypothesis in a large leachate database comprising 1490 leachate samples from 283 sample points (i.e., monitoring location such as a leachate sump) in 93 landfill waste cells (i.e., a section of a facility that took a specific waste stream or collection of similar waste streams) from 48 sites with municipal, codisposal, or hazardous waste site histories. Results of the analysis reveal clear differention between landfill leachate types, both in terms of constituents detected and their concentrations. The result of the analysis is a classification function that can estimate the probability that new leachate or ground water sample was produced by the disposal of municipal, codisposal, or hazardous waste. This type of computation is illustrated, and applications of the model to Superfund cost-allocation problems are discussed.

  13. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    or seawater and freshwater sediments or from samples collected from a wide range of different microbially rich and uranium) playing a role in bioremediation of ground- water and contaminated soil (Li et al. 2008). EABs

  14. Recirculation of municipal landfill leachate

    E-Print Network [OSTI]

    Pinkowski, Brian Jude

    1987-01-01T23:59:59.000Z

    . Under the 1984 amendments to the Resource Conservation and Recovery Act (RCRA), land disposal of hazardous waste in new facilities cannot take place unless these three conditions are met: 1. There are no other means available for disposal, 2. Double... as it passes through the landfill and liners are used to stop the migration oF the leachate into the groundwater by acting as a barrier. Style of the Water Pollution Control Federation RCRA defines hazardous waste as "a solid waste, or combination of solid...

  15. Radiocolloids in leachate from the NRC field lysimeter investigations

    SciTech Connect (OSTI)

    Brey, R.R.; Butikofer, T. [Idaho State Univ., Pocatello, ID (United States)] [Idaho State Univ., Pocatello, ID (United States); McConnell, J.W.; Rogers, R.D. [Idaho National Engineering Lab., Idaho Falls, ID (United States)] [Idaho National Engineering Lab., Idaho Falls, ID (United States)

    1998-12-31T23:59:59.000Z

    An investigation of colloidal particles has been completed on leachate samples collected from sand and soil-filled lysimeters (of the Field Lysimeter Investigation: Low-Level Waste Data Base Development Program) in which low-level radioactive waste forms were buried. An array of analytical techniques including: gamma spectroscopy, liquid scintillation spectrometry, gross alpha and beta particle proportional counting, energy dispersive X-ray analysis (EDX), neutron activation analysis (NAA), X-ray fluorescence analysis (XRF), proton induced X-ray emission analysis (PIXE), gravimetric analysis, and scanning electron microscopy (SEM), were performed on samples thought to contain colloidal particles to determine particle composition and the nature of their association with radioactive material. Several different types of particles ranging in size from 0.02 to 20 {micro}m were identified within the leachate including crystalline calcium hydroxide particles, rounded siliceous grains, angular weathered soil, and spherical particles apparently composed of an organic polymer. The primary radioactive material associated with these particles was Sr-90. About 2% of the total Sr-90 activity in the leachate is associated with colloidal particles. This information indicates that colloidal particles play a role in radioactive material transport through lysimeter soils.

  16. Modeling of leachate generation in municipal solid waste landfills

    E-Print Network [OSTI]

    Beck, James Bryan

    1994-01-01T23:59:59.000Z

    and the inclusion of compaction effects and leachate generation and movement effects by Mehevec (1994) should provide the user with a tool for estimating leachate generation values and landfill capacity figures for a variety of initial design and operational...

  17. Using tire chips as a leachate drainage layer

    SciTech Connect (OSTI)

    Duffy, D.P. [RMT, Inc., Ann Arbor, MI (United States)

    1995-09-01T23:59:59.000Z

    Old tires represent a potentially cost-effective construction material that can be used in the installation of leachate drainage and collection systems. In fact, recent studies show that using shredded tires in conjunction with granular soil materials can even enhance the long-term performance of these systems. A typical design using shredded tire chips involves the placement of a minimum 1-foot-thick layer of chips on a granular soil layer overlaying the composite liner system. However, implementation of this design is not as simple as it looks. Protecting the liner from wire protruding from the tire chips derived from belted tires is essential. Because tire chips tend to clump together, placement and spreading also must be in relatively thick lifts and performed by low-ground-pressure equipment. In addition, a significant volume reduction in the tire chip layer can be anticipated as a result of normal loadings from the overlying waste. Equivalent internal friction angles and cohesiveness for the tire chips should be estimated for factors of safety against side-slope failure. Despite theses concerns, however,the advantages of constructing a tire-chip drainage layer often can outweigh the disadvantages, as long as the chips` long-term permeability characteristics and resistance to clogging -- a result of biological activity -- are at least equal to that of typical granular soil materials commonly used in leachate drainage and collection systems.

  18. Metals in Municipal Landfill Leachate And Their Health Effects

    E-Print Network [OSTI]

    Laughlin, Robert B.

    raw leachate contains concentrations of heavy metals in excess ofthe drinking water standards of the un- saturated zone. If municipal solid waste is placed di- rectly into ground water, or if leachateMetals in Municipal Landfill Leachate And Their Health Effects STEPHEN C. JAMES, BS, MSCE Abstract

  19. Metal speciation in landfill leachates with a focus on the influence of organic matter

    SciTech Connect (OSTI)

    Claret, Francis, E-mail: f.claret@brgm.fr [BRGM, 3 avenue C. Guillemin, BP 6009, 45060 Orleans (France); Tournassat, Christophe; Crouzet, Catherine; Gaucher, Eric C. [BRGM, 3 avenue C. Guillemin, BP 6009, 45060 Orleans (France); Schaefer, Thorsten [Karlsruhe Institute of Technology (KIT), Institute for Nuclear Waste Disposal (INE), P.O. Box 3640, 76021 Karlsruhe (Germany); Freie Universitaet Berlin, Institute of Geological Sciences, Department of Earth Sciences, Hydrogeology Group, D-12249 Berlin (Germany); Braibant, Gilles; Guyonnet, Dominique [BRGM, 3 avenue C. Guillemin, BP 6009, 45060 Orleans (France)

    2011-09-15T23:59:59.000Z

    Highlights: > This study characterises the heavy-metal content in leachates collected from eight landfills in France. > Most of the metals are concentrated in the <30 kDa fraction, while Pb, Cu and Cd are associated with larger particles. > Metal complexation with OM is not sufficient to explain apparent supersaturation of metals with sulphide minerals. - Abstract: This study characterises the heavy-metal content in leachates collected from eight landfills in France. In order to identify heavy metal occurrence in the different size fractions of leachates, a cascade filtration protocol was applied directly in the field, under a nitrogen gas atmosphere to avoid metal oxidation. The results of analyses performed on the leachates suggest that most of the metals are concentrated in the <30 kDa fraction, while lead, copper and cadmium show an association with larger particles. Initial speciation calculations, without considering metal association with organic matter, suggest that leachate concentrations in lead, copper, nickel and zinc are super-saturated with respect to sulphur phases. Speciation calculations that account for metal complexation with organic matter, considered as fulvic acids based on C1(s) NEXAFS spectroscopy, show that this mechanism is not sufficient to explain such deviation from equilibrium conditions. It is therefore hypothesized that the deviation results also from the influence of biological activity on the kinetics of mineral phase precipitation and dissolution, thus providing a dynamic system. The results of chemical analyses of sampled fluids are compared with speciation calculations and some implications for the assessment of metal mobility and natural attenuation in a context of landfill risk assessment are discussed.

  20. Repository performance confirmation.

    SciTech Connect (OSTI)

    Hansen, Francis D.

    2011-09-01T23:59:59.000Z

    Repository performance confirmation links the technical bases of repository science and societal acceptance. This paper explores the myriad aspects of what has been labeled performance confirmation in U.S. programs, which involves monitoring as a collection of distinct activities combining technical and social significance in radioactive waste management. This paper is divided into four parts: (1) A distinction is drawn between performance confirmation monitoring and other testing and monitoring objectives; (2) A case study illustrates confirmation activities integrated within a long-term testing and monitoring strategy for Yucca Mountain; (3) A case study reviews compliance monitoring developed and implemented for the Waste Isolation Pilot Plant; and (4) An approach for developing, evaluating and implementing the next generation of performance confirmation monitoring is presented. International interest in repository monitoring is exhibited by the European Commission Seventh Framework Programme 'Monitoring Developments for Safe Repository Operation and Staged Closure' (MoDeRn) Project. The MoDeRn partners are considering the role of monitoring in a phased approach to the geological disposal of radioactive waste. As repository plans advance in different countries, the need to consider monitoring strategies within a controlled framework has become more apparent. The MoDeRn project pulls together technical and societal experts to assimilate a common understanding of a process that could be followed to develop a monitoring program. A fundamental consideration is the differentiation of confirmation monitoring from the many other testing and monitoring activities. Recently, the license application for Yucca Mountain provided a case study including a technical process for meeting regulatory requirements to confirm repository performance as well as considerations related to the preservation of retrievability. The performance confirmation plan developed as part of the Yucca Mountain license application identified a broad suite of monitoring activities. A revision of the plan was expected to winnow the number of activities down to a manageable size. As a result, an objective process for the next stage of performance confirmation planning was developed as an integral part of an overarching long-term testing and monitoring strategy. The Waste Isolation Pilot Plant compliance monitoring program at once reflects its importance to stakeholders while demonstrating adequate understanding of relevant monitoring parameters. The compliance criteria were stated by regulation and are currently monitored as part of the regulatory rule for disposal. At the outset, the screening practice and parameter selection were not predicated on a direct or indirect correlation to system performance metrics, as was the case for Yucca Mountain. Later on, correlation to performance was established, and the Waste Isolation Pilot Plant continues to monitor ten parameters originally identified in the compliance certification documentation. The monitoring program has proven to be effective for the technical intentions and societal or public assurance. The experience with performance confirmation in the license application process for Yucca Mountain helped identify an objective, quantitative methodology for this purpose. Revision of the existing plan would be based on findings of the total system performance assessment. Identification and prioritization of confirmation activities would then derive from performance metrics associated with performance assessment. Given the understanding of repository performance confirmation, as reviewed in this paper, it is evident that the performance confirmation program for the Yucca Mountain project could be readily re-engaged if licensing activities resumed.

  1. Metal Speciation in Landfill Leachates with a Focus on the Influence of Organic Matter

    SciTech Connect (OSTI)

    F Claret; C Tournassat; C Crouzet; E Gaucher; T Schäfer; G Braibant; D Guyonnet

    2011-12-31T23:59:59.000Z

    This study characterizes the heavy-metal content in leachates collected from eight landfills in France. In order to identify heavy metal occurrence in the different size fractions of leachates, a cascade filtration protocol was applied directly in the field, under a nitrogen gas atmosphere to avoid metal oxidation. The results of analyses performed on the leachates suggest that most of the metals are concentrated in the <30 kDa fraction, while lead, copper and cadmium show an association with larger particles. Initial speciation calculations, without considering metal association with organic matter, suggest that leachate concentrations in lead, copper, nickel and zinc are super-saturated with respect to sulphur phases. Speciation calculations that account for metal complexation with organic matter, considered as fulvic acids based on C1(s) NEXAFS spectroscopy, show that this mechanism is not sufficient to explain such deviation from equilibrium conditions. It is therefore hypothesized that the deviation results also from the influence of biological activity on the kinetics of mineral phase precipitation and dissolution, thus providing a dynamic system. The results of chemical analyses of sampled fluids are compared with speciation calculations and some implications for the assessment of metal mobility and natural attenuation in a context of landfill risk assessment are discussed.

  2. Midland Core Repository

    SciTech Connect (OSTI)

    Tyler, Noel

    2000-08-14T23:59:59.000Z

    This report summarizes activities for the repository during this quarter. The repository holds drill cores and cuttings samples from oil wells that can be viewed or checked out by users.

  3. Impact of nitrate-enhanced leachate recirculation on gaseous releases from a landfill bioreactor cell

    SciTech Connect (OSTI)

    Tallec, G.; Bureau, C. [Cemagref, UR HBAN, Parc de Tourvoie, BP44, F-92163 Antony (France); Peu, P.; Benoist, J.C. [Cemagref, UR GERE, 17 Avenue de Cucille, CS 64427, F-35044 Rennes (France); Lemunier, M. [Suez-Environnement, CIRADE, 38 Av. Jean Jaures, 78440 Gargenville (France); Budka, A.; Presse, D. [SITA France, 132 Rue des 3 Fontanot, 92000 Nanterre Cedex (France); Bouchez, T. [Cemagref, UR HBAN, Parc de Tourvoie, BP44, F-92163 Antony (France)], E-mail: theodore.bouchez@cemagref.fr

    2009-07-15T23:59:59.000Z

    This study evaluates the impact of nitrate injection on a full scale landfill bioreactor through the monitoring of gaseous releases and particularly N{sub 2}O emissions. During several weeks, we monitored gas concentrations in the landfill gas collection system as well as surface gas releases with a series of seven static chambers. These devices were directly connected to a gas chromatograph coupled to a flame ionisation detector and an electron capture detector (GC-FID/ECD) placed directly on the field. Measurements were performed before, during and after recirculation of raw leachate and nitrate-enhanced leachate. Raw leachate recirculation did not have a significant effect on the biogas concentrations (CO{sub 2}, CH{sub 4} and N{sub 2}O) in the gas extraction network. However, nitrate-enhanced leachate recirculation induced a marked increase of the N{sub 2}O concentrations in the gas collected from the recirculation trench (100-fold increase from 0.2 ppm to 23 ppm). In the common gas collection system however, this N{sub 2}O increase was no more detectable because of dilution by gas coming from other cells or ambient air intrusion. Surface releases through the temporary cover were characterized by a large spatial and temporal variability. One automated chamber gave limited standard errors over each experimental period for N{sub 2}O releases: 8.1 {+-} 0.16 mg m{sup -2} d{sup -1} (n = 384), 4.2 {+-} 0.14 mg m{sup -2} d{sup -1} (n = 132) and 1.9 {+-} 0.10 mg m{sup -2} d{sup -1} (n = 49), during, after raw leachate and nitrate-enhanced leachate recirculation, respectively. No clear correlation between N{sub 2}O gaseous surface releases and recirculation events were evidenced. Estimated N{sub 2}O fluxes remained in the lower range of what is reported in the literature for landfill covers, even after nitrate injection.

  4. Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2009

    SciTech Connect (OSTI)

    R.L. Weiss, B.L. Lawrence, D.W. Woolery

    2010-07-08T23:59:59.000Z

    This document reports the findings of the groundwater and leachate monitoring and sampling at the Environmental restoration Disposal Facility for calendar year 2009. The purpose of this annual monitoring report is to evaluate the conditions of and identify trends for groundwater beneath the ERDF and report leachate results in fulfillment of the requirements specified in the ERDF ROD and the ERDF Amended ROD.

  5. Modelling Geospatial Application Databases using UML-based Repositories Aligned with International Standards in Geomatics

    E-Print Network [OSTI]

    Modelling Geospatial Application Databases using UML-based Repositories Aligned with International Abstract: This paper presents the result of recent work on the use of geospatial repositories to store and database concepts, a geospatial repository can be defined as a collection of (meta) data structured

  6. Grey/Gray Matter: The Role of Institutional Repositories

    E-Print Network [OSTI]

    Mercer, Holly

    2011-04-15T23:59:59.000Z

    The speaker defines the role of an institutional repository and explains how it aids in preservation and scholarship. The session reviews trends in preservation services, providing remote access to collections, and facilitating scholarly...

  7. Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2008

    SciTech Connect (OSTI)

    R. L. Weiss; D. W. Woolery

    2009-09-03T23:59:59.000Z

    The purpose of this annual monitoring report is to evaluate the conditions of and identify trends for groundwater beneath the ERDF, to report leachate results in fulfillment of the requirements specified in the ERDF ROD and the ERDF Amended ROD.

  8. Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2006

    SciTech Connect (OSTI)

    R. L. Weiss

    2007-05-30T23:59:59.000Z

    The purpose of this annual monitoring report is to evaluate the conditions of and identify trends for groundwater beneath the ERDF and to report leachate results in fulfillment of the requirements specified in the ERDF ROD.

  9. Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2006

    SciTech Connect (OSTI)

    R. L. Weiss

    2007-12-05T23:59:59.000Z

    The purpose of this annual monitoring report is to evaluate the conditions of and identify trends for groundwater beneath the ERDF and to report leachate results in fulfillment of the requirements specified in the ERDF ROD.

  10. Mutagenicity and genotoxicity of coal fly ash water leachate

    SciTech Connect (OSTI)

    Chakraborty, R.; Mukherjee, A. [University of Calcutta, Calcutta (India). Dept. of Botany

    2009-03-15T23:59:59.000Z

    Fly ash is a by-product of coal-fired electricity generation plants. The prevalent practice of disposal is as slurry of ash and water to storage or ash ponds located near power stations. This has lain to waste thousands of hectares of land all over the world. Since leaching is often the cause of off-site contamination and pathway of introduction into the human environment, a study on the genotoxic effects of fly ash leachate is essential. Leachate prepared from the fly ash sample was analyzed for metal content, and tested for mutagenicity and genotoxicity. Analyses of metals show predominance of the metals - sodium, silicon, potassium, calcium, magnesium, iron, manganese, zinc, and sulphate. The Ames Salmonella mutagenicity assay, a short-term bacterial reverse mutation assay, was conducted on two-tester strains of Salmonella typhimurium strains TA97a and TA102. For genotoxicity, the alkaline version of comet assay on fly ash leachate was carried in vitro on human blood cells and in vivo on Nicotiana plants. The leachate was directly mutagenic and induced significantconcentration-dependent increases in DNA damage in whole blood cells, lymphocytes, and in Nicotiana plants. The comet parameters show increases in tail DNA percentage (%), tail length (mu m), and olive tail moment (arbitrary units). Our results indicate that leachate from fly ash dumpsites has the genotoxic potential and may lead to adverse effects on vegetation and on the health of exposed human populations.

  11. Acute and chronic toxicity of municipal landfill leachate as determined with bioassays and chemical analysis

    E-Print Network [OSTI]

    Schrab, Gregory Ernst

    1990-01-01T23:59:59.000Z

    municipal landfill leachates were determined to have mean estimated cumulative cancer risks on the same order of magnitude (10 4) as leachates from co-disposal and hazardous waste landfills. The use of a battery of acute and chronic toxicity bioassays..., chemical analysis, and an estimated cancer risk calculation resulted in data providing evidence that municipal solid waste landfill leachates are as acutely and chronically toxic as co-disposal and hazardous waste landfill leachates. ACKNOWLEDGEMENTS...

  12. Reduction of COD in leachate from a hazardous waste landfill adjacent to a coke-making facility

    SciTech Connect (OSTI)

    Banerjee, K.; O`Toole, T.J. [Chester Environmental, Moon Township, PA (United States)

    1995-12-01T23:59:59.000Z

    A hazardous waste landfill adjacent to a coke manufacturing facility was in operation between July 1990 and December 1991. A system was constructed to collect and treat the leachate from the landfill prior to discharge to the river. Occasionally, the discharge from the treatment facility exceeded the permit limitations for Chemical Oxygen Demand (COD), Biochemical Oxygen Demand (BOD), and Total Organic Carbon (TOC). The objectives of this study were to determine treatment methods which would enable compliance with the applicable discharge limits; to establish the desired operating conditions of the process; and to investigate the effect of various parameters such as pH, catalyst dosage, and reaction time on the COD destruction efficiency. The characteristics of the landfill leachate in question were significantly variable in terms of chemical composition. A review of the influent quality data suggests that the COD concentration ranges between 80 and 390 mg/l. The oxidation processes using Fenton`s reagent or a combination of UV/hydrogen peroxide/catalyst are capable of reducing the COD concentration of the leachate below the discharge limitation of 35 mg/l. The estimated capital cost associated with the Fenton`s reagent process is approximately $525,000, and the annual operating and maintenance cost is $560,000. The estimated capital cost for the UV/hydrogen peroxide/catalyst treatment system is $565,000. The annual operating and maintenance cost of this process would be approximately $430,000.

  13. Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2007

    SciTech Connect (OSTI)

    R. L. Weiss; T. A. Lee

    2008-06-25T23:59:59.000Z

    The purpose of this annual monitoring report is to evaluate the conditions of and identify trends for groundwater beneath the Environmental Restoration Disposal Facility and to report leachate results in fulfillment of the requirements specified in the ERDF Record of Decision and the ERDF Amended Record of Decision.

  14. EVALUATION OF LEACHATE QUALITY FROM PENTACHLOROPHENOL, CREOSOTE AND ACA

    E-Print Network [OSTI]

    observed in this study are those from leachates produced by direct contact of water with the treated wood and by sprinklers with tap water. The sampling schedule was based on accumulated rainfall with samples taken differences between the experimental setup and the actual conditions at the treatment facilities. The releases

  15. Progress Towards International Repositories

    SciTech Connect (OSTI)

    McCombie, C.; Chapman, N.

    2002-02-27T23:59:59.000Z

    The nuclear fuel cycle is designed to be very international, with some specialist activities (e.g. fuel fabrication, reprocessing, etc.) being confined to a few countries. Nevertheless, political and public opposition has in the past been faced by proposals to internationalise the back-end of the cycle, in particular waste disposal. Attitudes, however, have been changing recently and there is now more acceptance of the general concept of shared repositories and of specific proposals such as that of Pangea. However, as for national facilities, progress towards implementation of shared repositories will be gradual. Moreover, the best vehicle for promoting the concept may not be a commercial type of organization. Consequently the Pangea project team are currently establishing a widely based Association for this purpose.

  16. Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2010

    SciTech Connect (OSTI)

    Weiss, R. L.; Lawrence, B. L.

    2011-06-09T23:59:59.000Z

    The purpose of this annual monitoring report is to evaluate the conditions of and identify trends for groundwater beneath the ERDF and report leachate results in fulfillment of the requirements specified in the ERDF ROD2 and the ERDF Amended ROD (EPA 1999). The overall objective of the groundwater monitoring program is to determine whether ERDF has impacted the groundwater. This objective is complicated by the fact that the ERDF is situated downgradient of the numerous groundwater contamination plumes originating from the 200 West Area.

  17. Measuring and Comparing Participation Patterns In Digital Repositories, Repositories by the Numbers Part I

    E-Print Network [OSTI]

    Thomas, Chuck; McDonald, Robert H.

    2007-01-01T23:59:59.000Z

    library. (Wash. , D.C: Digital Library Federation). digital repositories certainly will be an important part of future "distributed libraries" (Digital Repositories, Repositories by the Numbers Part I Chuck Thomas, Florida Center for Library

  18. Groundwater and Leachate Monitoring and Sampling at the Environmental Restoration Disposal Facility, Calendar Year 2005

    SciTech Connect (OSTI)

    D.A. St. John, R.L. Weiss

    2006-05-04T23:59:59.000Z

    The purpose of this annual monitoring report is to evaluate the conditions of and identify trends for groundwater beneath the ERDF and to report leachate results in accordance with the requirements specified in the ERDF ROD.

  19. Overburden effects on waste compaction and leachate generation in municipal landfills

    E-Print Network [OSTI]

    Mehevec, Adam Wade

    1994-01-01T23:59:59.000Z

    This thesis presents a model to predict the effects of overburden pressure on the formation of leachate within municipal solid waste landfills. In addition, it estimates the compaction and subsequent settlement that the waste will undergo due...

  20. Acute and chronic toxicity of municipal landfill leachate as determined with bioassays and chemical analysis 

    E-Print Network [OSTI]

    Schrab, Gregory Ernst

    1990-01-01T23:59:59.000Z

    ACUTE AND CHRONIC TOXICITY OF MUNICIPAL LANDFILL LEACHATE AS DETERMINED WITH BIOASSAYS AND CHEMICAL ANALYSIS A Thesis by GREGORY ERNST SCHRAB Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment... of the requirements for the degree of MASTER OF SCIENCE May 1990 Major Subject: Soil Science ACUTF AND CHRONIC TOXICITY OF MUNICIPAL LANDFILL LEACHATE AS DETERMINED WITH BIOASSAYS AND CHEMICAL ANALYSIS A Thesis by GREGORY ERNST SCHRAB Approved as to style...

  1. US/German Collaboration in Salt Repository Research, Design and Operation - 13243

    SciTech Connect (OSTI)

    Steininger, Walter [Karlsruhe Institute of Technology, Project Management Agency Karlsruhe - (PTKA-WTE) Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany)] [Karlsruhe Institute of Technology, Project Management Agency Karlsruhe - (PTKA-WTE) Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Hansen, Frank [Sandia National Laboratories, Albuquerque NM USA 87111 (United States)] [Sandia National Laboratories, Albuquerque NM USA 87111 (United States); Biurrun, Enrique; Bollingerfehr, Wilhelm [DBE TECHNOLOGY GmbH, Eschenstr. 55, 31224 Peine (Germany)] [DBE TECHNOLOGY GmbH, Eschenstr. 55, 31224 Peine (Germany)

    2013-07-01T23:59:59.000Z

    Recent developments in the US and Germany [1-3] have precipitated renewed efforts in salt repository investigations and related studies. Both the German rock salt repository activities and the US waste management programs currently face challenges that may adversely affect their respective current and future state-of-the-art core capabilities in rock salt repository science and technology. The research agenda being pursued by our respective countries leverages collective efforts for the benefit of both programs. The topics addressed by the US/German salt repository collaborations align well with the findings and recommendations summarized in the January 2012 US Blue Ribbon Commission on America's Nuclear Future (BRC) report [4] and are consistent with the aspirations of the key topics of the Strategic Research Agenda of the Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP) [5]. Against this background, a revival of joint efforts in salt repository investigations after some years of hibernation has been undertaken to leverage collective efforts in salt repository research, design, operations, and related issues for the benefit of respective programs and to form a basis for providing an attractive, cost-effective insurance against the premature loss of virtually irreplaceable scientific expertise and institutional memory. (authors)

  2. Thermomechanical response of WIPP repositories

    SciTech Connect (OSTI)

    Maxwell, D.E.; Wahi, K.K.; Dial, B.

    1980-05-01T23:59:59.000Z

    Coarsely zoned STEALTH 2D calculations were used to investigate two candidate WIPP repositories. The grid was designed for one hundred thousand years of response with modest computing costs. As a result, the early time mechanical response was compromised by non-real oscillations that could not be damped completely before a few thousand years. In spite of these oscillations, it was possible to see that the dominant effects of stress and strain peaked between one and two thousand years, at the time of maximum heat in the site. This time corresponded to the condition that the surface heat loss rate balanced the heat generation rate. Though the creep strains were quite small, a large volume of salt was involved and the effects were significant. The peak surface uplift of 75HLW was increased by about 25% due to creep. However, the deviatoric stress relaxation due to creep produced large changes in the stress fields. The Rustler layer survived reasonable failure criterion for the 75HLW case with creep, and failed both in tension and shear, according to these same criterion, when the calculation was repeated without creep. The deviatoric stress fields, with and without salt creep, concentrated near the repository as expected and also in the Rustler layer due to its relatively high Young's modulus compared to the neighboring layers. Since the time of interest is so much smaller than the 100,000 years this calculation was designed to examine, it is possible to model the WIPP stratigraphy in much more detail and still be able to calculate the response for the time of interest. A finer zoned calculation of the response of the WIPP stratigraphy to a repository similar to the 75 K watt/acre repository is modeled in this report. In this calculation the Rustler formation is modeled as a five layered formation using material properties derived from data taken at the Nome site.

  3. Physical processes of magmatism and effects on the potential repository: Synthesis of technical work through Fiscal Year 1995

    SciTech Connect (OSTI)

    Valentine, G.A.

    1996-09-01T23:59:59.000Z

    This chapter summarizes data collection and model calculations through FY 95 under Study Plan 8.3.1.8.1.2 Physical Processes of Magmatism and Effects on the Potential Repository. The focus of this study plan is to gather information that ultimately constrains the consequences of small-volume, basaltic magmatic activity at or near a potential repository. This is then combined with event probability estimates, described elsewhere in this synthesis report, to yield a magmatic risk assessment. Tere are two basic classes of effects of magmatisms that are considered here: (1) Eruptive effects, whereby rising magma intersects a potential repository, entrains radioactive waste, and erupts it onto the earth`s surface. (2) Subsurface effects, which includes a wide range of processes such as hydrothermal flow, alteration of mineral assemblages in the potential repository system, and alteration of hydrologic flow properties of the rocks surrounding a potential repository.

  4. Repository Services for Research Data Management 

    E-Print Network [OSTI]

    Uribe, Luis Martinez

    2008-07-31T23:59:59.000Z

    Repository Services for Research Data Management - findings from interviews and workshop to capture Oxford researchers' requirements for services to help them manage their data

  5. Laboratory measurements of contaminant attenuation of uranium mill tailings leachates by sediments and clay liners

    SciTech Connect (OSTI)

    Serne, R.J.; Peterson, S.R.; Gee, G.W.

    1983-04-01T23:59:59.000Z

    We discuss FY82 progress on the development of laboratory tools to aid in the prediction of migration potential of contaminants present in acidic uranium mill tailings leachate. Further, empirical data on trace metal and radionuclide migration through a clay liner are presented. Acidic uranium mill tailings solution from a Wyoming mill was percolated through a composite sediment called Morton Ranch Clay liner. These laboratory columns and subsequent sediment extraction data show: (1) As, Cr, Pb, Ag, Th and V migrate very slowly; (2) U, Cd, Ni, Zn, Fe, Mn and similar transition metals are initially immobilized during acid neutralization but later are remobilized as the tailings solution exhausts the clay liner's acid buffering capacity. Such metals remain immobilized as long as the effluent pH remains above a pH value of 4 to 4.5, but they become mobile once the effluent pH drops below this range; and (3) fractions of the Se and Mo present in the influent tailings solution are very mobile. Possible controlling mechanisms for the pH-dependent immobilization-mobilization of the trace metals are discussed. More study is required to understand the controlling mechanisms for Se and Mo and Ra for which data were not successfully collected. Using several column lengths (from 4.5 to 65 cm) and pore volume residence times (from 0.8 to 40 days) we found no significant differences in contaminant migration rates or types and extent of controlling processes. Thus, we conclude that the laboratory results may be capable of extrapolation to actual disposal site conditions.

  6. Garbage Collection (Garbage collection)

    E-Print Network [OSTI]

    Bshouty, Nader

    1 1 1 1 #12;9Garbage Collection : , leftright . :{u,r,l} . :root -w )-rootGarbage Collection )( U U U U U U Lparent w U U U U L U L parent w #12;©cs,Technion 12Garbage Collection )( U U L U L U L parent wU U U U L U L parent w #12;©cs,Technion 13Garbage Collection )( U U L U L U

  7. EXTENDING GEOSPATIAL REPOSITORIES WITH GEOSEMANTIC PROXIMITY FUNCTIONALITIES

    E-Print Network [OSTI]

    EXTENDING GEOSPATIAL REPOSITORIES WITH GEOSEMANTIC PROXIMITY FUNCTIONALITIES TO FACILITATE THE INTEROPERABILITY OF GEOSPATIAL DATA Jean Brodeur a, b , Yvan Bédard a a Centre for Research in Geomatics, Laval.Bedard@scg.ulaval.ca Commission IV, WG IV/1 KEY WORDS: Geospatial data interoperability, Geospatial repository, Geosemantic

  8. Reference repository design concept for bedded salt

    SciTech Connect (OSTI)

    Carpenter, D.W.; Martin, R.W.

    1980-10-08T23:59:59.000Z

    A reference design concept is presented for the subsurface portions of a nuclear waste repository in bedded salt. General geologic, geotechnical, hydrologic and geochemical data as well as descriptions of the physical systems are provided for use on generic analyses of the pre- and post-sealing performance of repositories in this geologic medium. The geology of bedded salt deposits and the regional and repository horizon stratigraphy are discussed. Structural features of salt beds including discontinuities and dissolution features are presented and their effect on repository performance is discussed. Seismic hazards and the potential effects of earthquakes on underground repositories are presented. The effect on structural stability and worker safety during construction from hydrocarbon and inorganic gases is described. Geohydrologic considerations including regional hydrology, repository scale hydrology and several hydrological failure modes are presented in detail as well as the hydrological considerations that effect repository design. Operational phase performance is discussed with respect to operations, ventilation system, shaft conveyances, waste handling and retrieval systems and receival rates of nuclear waste. Performance analysis of the post sealing period of a nuclear repository is discussed, and parameters to be used in such an analysis are presented along with regulatory constraints. Some judgements are made regarding hydrologic failure scenarios. Finally, the design and licensing process, consistent with the current licensing procedure is described in a format that can be easily understood.

  9. Characteristics of potential repository wastes

    SciTech Connect (OSTI)

    Notz, K.J.

    1989-01-01T23:59:59.000Z

    The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the spent fuels and other wastes that will be disposed of in a geologic repository. The two major sources of these materials are commercial light-water reactor (LWR) spent fuel and immobilized high-level waste (HLW). Other wastes that may require long-term isolation include non-LWR spent fuels and miscellaneous sources such as activated metals. Detailed characterizations are required for all of these potential repository wastes. These characterizations include physical, chemical, and radiological properties. The latter must take into account decay as a function of time. This information has been extracted from primary data sources, evaluated, and assembled in a Characteristics Data Base which provides data in four formats: hard copy standard reports, menu-driven personal computer (PC) data bases, program-level PC data bases, and mainframe computer files. The Characteristics Data Base provides a standard set of self-consistent data to the various areas of responsibility including systems integration and waste stream analysis, storage, transportation, and geologic disposal. The data will be used for design studies, evaluation of alternatives, and system optimization by OCRWM and supporting contractors. 7 refs., 5 figs., 7 tabs.

  10. Turning The Web Into An Effective Knowledge Repository INESC-ID / IST

    E-Print Network [OSTI]

    Ferreira, Paulo

    . This includes safely preserving static and dynamic content as well as performing stor- age managementTurning The Web Into An Effective Knowledge Repository Luis Veiga INESC-ID / IST Rua Alves Redol, 9 management, web proxy, detecting distributed cycles, distributed garbage collection. Abstract: To fulfill

  11. Optimisation of sanitary landfill leachate treatment in a sequencing batch reactor

    E-Print Network [OSTI]

    Optimisation of sanitary landfill leachate treatment in a sequencing batch reactor A. Spagni, S al. 1988; Kjeldsen et al. 2002). Among several technologies, sequen- cing batch reactors (SBRs) haveH and oxidation-reduction potential (ORP) have been frequently used for monitoring and control of batch reactors

  12. Nitrogen removal via nitrite in a sequencing batch reactor treating sanitary landfill leachate

    E-Print Network [OSTI]

    Ammonium rich wastewater Fuzzy logic Biological nutrient removal a b s t r a c t The present paper reports and biological pro- cesses (Lema et al., 1988). Among several biological treatment sys- tems, sequencing batch confirm the effectiveness of the nitrite route for nitrogen removal optimisation in leachate treatment

  13. Characteristics of potential repository wastes

    SciTech Connect (OSTI)

    Cowart, C.G.; Notz, K.J.

    1992-10-01T23:59:59.000Z

    This report presents the results of a fully documented peer review of DOE/RW-0184, Rev. 1, Characteristics of Potential Repository Wastes''. The peer review was chaired and administered by oak Ridge National Laboratory (ORNL) for the Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) and was conducted in accordance with OCRWM QA procedure QAAP 3.3 Peer Review'' for the purpose of quailing the document for use in OCRWM quality-affecting work. The peer reviewers selected represent a wide range of experience and knowledge particularly suitable for evaluating the subject matter. A total of 596 formal comments were documented by the seven peer review panels, and all were successfully resolved. The peers reached the conclusion that DOE/RW-0184, Rev. 1, is quality determined and suitable for use in quality-affecting work.

  14. A study of tritium in municipal solid waste leachate and gas

    SciTech Connect (OSTI)

    Mutch Jr, R. D. [HydroQual, Inc., 1200 MacArthur Blvd., Mahwah, NJ 07430 (United States); Manhattan College, Riverdale, NY (United States); Columbia Univ., New York, NY (United States); Mahony, J. D. [HydroQual, Inc., 1200 MacArthur Blvd., Mahwah, NJ 07430 (United States); Manhattan College, Riverdale, NY (United States)

    2008-07-15T23:59:59.000Z

    It has become increasingly clear in the last few years that the vast majority of municipal solid waste landfills produce leachate that contains elevated levels of tritium. The authors recently conducted a study of landfills in New York and New Jersey and found that the mean concentration of tritium in the leachate from ten municipal solid waste (MSW) landfills was 33,800 pCi/L with a peak value of 192,000 pCi/L. A 2003 study in California reported a mean tritium concentration of 99,000 pCi/L with a peak value of 304,000 pCi/L. Studies in Pennsylvania and the UK produced similar results. The USEPA MCL for tritium is 20,000 pCi/L. Tritium is also manifesting itself as landfill gas and landfill gas condensate. Landfill gas condensate samples from landfills in the UK and California were found to have tritium concentrations as high as 54,400 and 513,000 pCi/L, respectively. The tritium found in MSW leachate is believed to derive principally from gaseous tritium lighting devices used in some emergency exit signs, compasses, watches, and even novelty items, such as 'glow stick' key chains. This study reports the findings of recent surveys of leachate from a number of municipal solid waste landfills, both open and closed, from throughout the United States and Europe. The study evaluates the human health and ecological risks posed by elevated tritium levels in municipal solid waste leachate and landfill gas and the implications to their safe management. We also assess the potential risks posed to solid waste management facility workers exposed to tritium-containing waste materials in transfer stations and other solid waste management facilities. (authors)

  15. Cost-Effective Cementitious Material Compatible with Yucca Mountain Repository Geochemistry

    SciTech Connect (OSTI)

    Dole, LR

    2004-12-17T23:59:59.000Z

    The current plans for the Yucca Mountain (YM) repository project (YMP) use steel structures to stabilize the disposal drifts and connecting tunnels that are collectively over 100 kilometers in length. The potential exist to reduce the underground construction cost by 100s of millions of dollars and improve the repository's performance. These economic and engineering goals can be achieved by using the appropriate cementitious materials to build out these tunnels. This report describes the required properties of YM compatible cements and reviews the literature that proves the efficacy of this approach. This report also describes a comprehensive program to develop and test materials for a suite of underground construction technologies.

  16. Quality Classifiers for Open Source Software Repositories

    E-Print Network [OSTI]

    Tsatsaronis, George; Giakoumakis, Emmanouel A

    2009-01-01T23:59:59.000Z

    Open Source Software (OSS) often relies on large repositories, like SourceForge, for initial incubation. The OSS repositories offer a large variety of meta-data providing interesting information about projects and their success. In this paper we propose a data mining approach for training classifiers on the OSS meta-data provided by such data repositories. The classifiers learn to predict the successful continuation of an OSS project. The `successfulness' of projects is defined in terms of the classifier confidence with which it predicts that they could be ported in popular OSS projects (such as FreeBSD, Gentoo Portage).

  17. REPOSITORY RECONFIGURATION OF PANELS 9 AND 10

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ventilation system of the WIPP repository for various configurations to support the mining and operation of the proposed Panels 9A and 10A. The MVS ventilation modeling verifies...

  18. DSpace: An Open Source Dynamic Digital Repository

    E-Print Network [OSTI]

    Smith, MacKenzie

    For the past two years the Massachusetts Institute of Technology (MIT) Libraries and Hewlett-Packard Labs have been collaborating on the development of an open source system called DSpaceâ?¢ that functions as a repository ...

  19. The institutional repository in the digital library 

    E-Print Network [OSTI]

    MacColl, John; Jones, Richard D; Andrew, Theo

    We begin by looking at the concept of institutional repositories within the broader context of digital libraries. ‘Digital libraries’ can mean many things, but we consider them to be libraries first and foremost, and ...

  20. MOST – Multiple Objective Spanning Trees Repository Project

    E-Print Network [OSTI]

    2008-01-24T23:59:59.000Z

    This repository is open to the general participation of the interested communities, mainly in terms of ..... 5: Set ?ei?E : z1(ei) = ?Xi?. 6: Set ?ei?E : z2(ei) = ?Yi ...

  1. Use of impervious covers and carbon adsorption for the control of leachate production in municipal landfills

    E-Print Network [OSTI]

    Carmichael, Richard Charles

    1979-01-01T23:59:59.000Z

    engineering in charac)er and therefore should be entrusted to engineers. The above quote could have come from any recent hearing or meeting concerning solid waste management. Instead it came from a paper read by Mr. W. N. Baker before the League... waters. The phenomenon of potential leachate pollution hss only recently received recognition. The Office of Solid Waste Manage- ment Programs and Office of Water Supply reported to Congress in 1976 that& "Waste disposal practices have contaminated...

  2. Coupling fuel cycles with repositories: how repository institutional choices may impact fuel cycle design

    SciTech Connect (OSTI)

    Forsberg, C. [Massachusetts Institute of Technology, 77 Massachusetts Ave., Room 24-207A Cambridge, MA 02139 (United States); Miller, W.F. [Texas A.M. University System, MS 3133 College Station, TX 77843-3133 (United States)

    2013-07-01T23:59:59.000Z

    The historical repository siting strategy in the United States has been a top-down approach driven by federal government decision making but it has been a failure. This policy has led to dispatching fuel cycle facilities in different states. The U.S. government is now considering an alternative repository siting strategy based on voluntary agreements with state governments. If that occurs, state governments become key decision makers. They have different priorities. Those priorities may change the characteristics of the repository and the fuel cycle. State government priorities, when considering hosting a repository, are safety, financial incentives and jobs. It follows that states will demand that a repository be the center of the back end of the fuel cycle as a condition of hosting it. For example, states will push for collocation of transportation services, safeguards training, and navy/private SNF (Spent Nuclear Fuel) inspection at the repository site. Such activities would more than double local employment relative to what was planned for the Yucca Mountain-type repository. States may demand (1) the right to take future title of the SNF so if recycle became economic the reprocessing plant would be built at the repository site and (2) the right of a certain fraction of the repository capacity for foreign SNF. That would open the future option of leasing of fuel to foreign utilities with disposal of the SNF in the repository but with the state-government condition that the front-end fuel-cycle enrichment and fuel fabrication facilities be located in that state.

  3. Organic and nitrogen removal from landfill leachate in aerobic granular sludge sequencing batch reactors

    SciTech Connect (OSTI)

    Wei Yanjie [School of Environmental Science and Engineering, Tianjin University, Tianjin 300072 (China); Key Laboratory of Environmental Protection in Water Transport Engineering Ministry of Communications, Tianjin Research Institute of Water Transport Engineering, Tianjin 300456 (China); Ji Min, E-mail: jmtju@yahoo.cn [School of Environmental Science and Engineering, Tianjin University, Tianjin 300072 (China); Li Ruying [School of Environmental Science and Engineering, Tianjin University, Tianjin 300072 (China); Qin Feifei [Tianjin Tanggu Sino French Water Supply Co. Ltd., Tianjin 300450 (China)

    2012-03-15T23:59:59.000Z

    Highlights: Black-Right-Pointing-Pointer Aerobic granular sludge SBR was used to treat real landfill leachate. Black-Right-Pointing-Pointer COD removal was analyzed kinetically using a modified model. Black-Right-Pointing-Pointer Characteristics of nitrogen removal at different ammonium inputs were explored. Black-Right-Pointing-Pointer DO variations were consistent with the GSBR performances at low ammonium inputs. - Abstract: Granule sequencing batch reactors (GSBR) were established for landfill leachate treatment, and the COD removal was analyzed kinetically using a modified model. Results showed that COD removal rate decreased as influent ammonium concentration increasing. Characteristics of nitrogen removal at different influent ammonium levels were also studied. When the ammonium concentration in the landfill leachate was 366 mg L{sup -1}, the dominant nitrogen removal process in the GSBR was simultaneous nitrification and denitrification (SND). Under the ammonium concentration of 788 mg L{sup -1}, nitrite accumulation occurred and the accumulated nitrite was reduced to nitrogen gas by the shortcut denitrification process. When the influent ammonium increased to a higher level of 1105 mg L{sup -1}, accumulation of nitrite and nitrate lasted in the whole cycle, and the removal efficiencies of total nitrogen and ammonium decreased to only 35.0% and 39.3%, respectively. Results also showed that DO was a useful process controlling parameter for the organics and nitrogen removal at low ammonium input.

  4. Polybrominated diphenyl ethers (PBDEs) in leachates from selected landfill sites in South Africa

    SciTech Connect (OSTI)

    Odusanya, David O. [Department of Environmental, Water and Earth Sciences, Faculty of Science, Tshwane University of Technology, Private Bag X680, 175 Nelson Mandela Drive, Arcadia, Pretoria 0001 (South Africa); Okonkwo, Jonathan O. [Department of Environmental, Water and Earth Sciences, Faculty of Science, Tshwane University of Technology, Private Bag X680, 175 Nelson Mandela Drive, Arcadia, Pretoria 0001 (South Africa)], E-mail: OkonkwoOJ@tut.ac.za; Botha, Ben [Department of Environmental, Water and Earth Sciences, Faculty of Science, Tshwane University of Technology, Private Bag X680, 175 Nelson Mandela Drive, Arcadia, Pretoria 0001 (South Africa)

    2009-01-15T23:59:59.000Z

    The last few decades have seen dramatic growth in the scale of production and the use of polybrominated diphenyl ethers (PBDEs) as flame retardants. Consequently, PBDEs such as BDE -28, -47, -66, -71, -75, -77, -85, -99, -100, -119, -138, -153, -154, and -183 have been detected in various environmental matrices. Generally, in South Africa, once the products containing these chemicals have outlived their usefulness, they are discarded into landfill sites. Consequently, the levels of PBDEs in leachates from landfill sites may give an indication of the general exposure and use of these compounds. The present study was aimed at determining the occurrence and concentrations of most common PBDEs in leachates from selected landfill sites. The extraction capacities of the solvents were also tested. Spiked landfill leachate samples were used for the recovery tests. Separation and determination of the PBDE congeners were carried out with a gas chromatograph equipped with Ni{sup 63} electron capture detector. The mean percentage recoveries ranged from 63% to 108% (n = 3) for landfill leachate samples with petroleum ether giving the highest percentage extraction. The mean concentrations of PBDEs obtained ranged from ND to 2670 pg l{sup -1}, ND to 6638 pg l{sup -1}, ND to 7230 pg l{sup -1}, 41 to 4009 pg l{sup -1}, 90 to 9793 pg l{sup -1} for the Garankuwa, Hatherly, Kwaggarsrand, Soshanguve and Temba landfill sites, respectively. Also BDE -28, -47, -71 and BDE-77 were detected in the leachate samples from all the landfill sites; and all the congeners were detected in two of the oldest landfill sites. The peak concentrations were recorded for BDE-47 at three sites and BDE-71 and BDE-75 at two sites. The highest concentration, 9793 {+-} 1.5 pg l{sup -1}, was obtained for the Temba landfill site with the highest BOD value. This may suggest some influence of organics on the level of PBDEs. Considering the leaching characteristics of brominated flame retardants, there is a high possibility that with time these compounds may infiltrate into the groundwater around the sites since most of the sites are not adequately lined.

  5. Adding OAI-ORE Support to Repository Platforms

    E-Print Network [OSTI]

    Maslov, Alexey; Mikeal, Adam; Phillips, Scott; Leggett, John; McFarland, Mark

    2009-05-17T23:59:59.000Z

    ETD repository and the mapping of the OAI-ORE data model to the DSpace architecture. We discuss our implementation that adds both dissemination and harvesting functionality to the repository. We conclude by discussing the architectural flexibility...

  6. BUOYANCY FLOW IN FRACTURES INTERSECTING A NUCLEAR WASTE REPOSITORY

    E-Print Network [OSTI]

    Wang, J.S.Y.

    2010-01-01T23:59:59.000Z

    11112 "Heat Transfer to Nuclear Waste Disposal", ASME WinterIN FPACTUHES INTERSECTING A NUCLEAR WASTE REPOSITORY J.S.Y.Heat released from a nuclear waste repository in a

  7. Cost analysis of German waste repositories

    SciTech Connect (OSTI)

    Berg, H.P.; Debski, H.J. [Bundesamt fuer Strahlenschutz, Salzgitter (Germany)

    1993-12-31T23:59:59.000Z

    In forecasting costs of final disposal for radioactive waste, the determined disposal concept and operational aspects such as the necessary amount for personnel to operate the repository are important. Even for the German deep geological concept, there are large differences resulting from the assessment to select an already existing mine or a completely new formation as a disposal site. Based on actual planning, the expected total costs of the running waste repository projects in the Federal Republic of Germany are presented including their distribution to single aspects like project management, underground investigation, licensing work and construction. Moreover, the actual expenditures for the different waste repositories are given and as far as possible the prices per m{sup 3}.

  8. National Geoscience Data Repository System -- Phase III: Implementation and Operation of the Repository

    SciTech Connect (OSTI)

    Keane, Christopher M.

    2002-05-28T23:59:59.000Z

    The National Geoscience Data Repository System, Phase III was an operational project focused on coordinating and facilitating transfers of at-risk geoscience data from the private sector to the public domain.

  9. Optimization of stabilized leachate treatment using ozone/persulfate in the advanced oxidation process

    SciTech Connect (OSTI)

    Abu Amr, Salem S. [School of Civil Engineering, Engineering Campus, Universiti Sains Malaysia, 14300 Nibong Tebal, Penang (Malaysia); Aziz, Hamidi Abdul, E-mail: cehamidi@eng.usm.my [School of Civil Engineering, Engineering Campus, Universiti Sains Malaysia, 14300 Nibong Tebal, Penang (Malaysia); Adlan, Mohd Nordin [School of Civil Engineering, Engineering Campus, Universiti Sains Malaysia, 14300 Nibong Tebal, Penang (Malaysia)

    2013-06-15T23:59:59.000Z

    Highlights: ? Ozone and persulfate reagent (O{sub 3}/S{sub 2}O{sub 8}{sup 2-}) was used to treat stabilized leachate. ? Central composite design (CCD) with response surface methodology (RSM) was applied. ? Operating variables including ozone and persulfate dosage, pH variance, and reaction time. ? Optimum removal of COD, color, and NH{sub 3}–N was 72%, 96%, and 76%, respectively. ? A good value of ozone consumption (OC) obtained with 0.60 (kg O{sub 3}/kg COD). - Abstract: The objective of this study was to investigate the performance of employing persulfate reagent in the advanced oxidation of ozone to treat stabilized landfill leachate in an ozone reactor. A central composite design (CCD) with response surface methodology (RSM) was applied to evaluate the relationships between operating variables, such as ozone and persulfate dosages, pH, and reaction time, to identify the optimum operating conditions. Quadratic models for the following four responses proved to be significant with very low probabilities (<0.0001): COD, color, NH{sub 3}–N, and ozone consumption (OC). The obtained optimum conditions included a reaction time of 210 min, 30 g/m{sup 3} ozone, 1 g/1 g COD{sub 0}/S{sub 2}O{sub 8}{sup 2-} ratio, and pH 10. The experimental results were corresponded well with predicted models (COD, color, and NH{sub 3}–N removal rates of 72%, 96%, and 76%, respectively, and 0.60 (kg O{sub 3}/kg COD OC). The results obtained in the stabilized leachate treatment were compared with those from other treatment processes, such as ozone only and persulfate S{sub 2}O{sub 8}{sup 2-} only, to evaluate its effectiveness. The combined method (i.e., O{sub 3}/S{sub 2}O{sub 8}{sup 2-}) achieved higher removal efficiencies for COD, color, and NH{sub 3}–N compared with other studied applications. Furthermore, the new method is more efficient than ozone/Fenton in advanced oxidation process in the treatment of the same studied leachate.

  10. A comparative simulation study of coupled THM processes and their effect on fractured rock permeability around nuclear waste repositories

    E-Print Network [OSTI]

    Rutqvist, Jonny

    2008-01-01T23:59:59.000Z

    hydrothermomechanical design of nuclear waste repositories.Associated with Nuclear Waste Repositories, Academic Press,rock permeability around nuclear waste repositories Jonny

  11. Multiple-code simulation study of the long-term EDZ evolution of geological nuclear waste repositories

    E-Print Network [OSTI]

    Rutqvist, J.

    2008-01-01T23:59:59.000Z

    Associated with Nuclear Waste Repositories, Academic Press,C (eds) Rock Mechanics of Nuclear Waste Repositories, Veil,EDZ Evolution of Geological Nuclear Waste Repositories Jonny

  12. Fukushima Daiichi Information Repository FY13 Status

    SciTech Connect (OSTI)

    Curtis Smith; Cherie Phelan; Dave Schwieder

    2013-09-01T23:59:59.000Z

    The accident at the Fukushima Daiichi nuclear power station in Japan is one of the most serious in commercial nuclear power plant operating history. Much will be learned that may be applicable to the U.S. reactor fleet, nuclear fuel cycle facilities, and supporting systems, and the international reactor fleet. For example, lessons from Fukushima Daiichi may be applied to emergency response planning, reactor operator training, accident scenario modeling, human factors engineering, radiation protection, and accident mitigation; as well as influence U.S. policies towards the nuclear fuel cycle including power generation, and spent fuel storage, reprocessing, and disposal. This document describes the database used to establish a centralized information repository to store and manage the Fukushima data that has been gathered. The data is stored in a secured (password protected and encrypted) repository that is searchable and available to researchers at diverse locations.

  13. The German quality system for waste repositories

    SciTech Connect (OSTI)

    Beckmerhagen, I.; Berg, H.P.; Brennecke, P. [Bundesamt fuer Strahlenschutz, Saltzgitter (Germany)

    1993-12-31T23:59:59.000Z

    The Bundesamt fuer Strahlenschutz (BfS)--Federal Office for Radiation protection--has to guarantee that the requirements resulting from different regulations concerning planning, design, construction, operation and decommissioning of a waste repository are fulfilled. In addition, the results of the safety assessments lead to nuclear-specific requirements on the design of the plant as well as to requirements on the radioactive waste packages intended to be disposed of. Therefore, the implementation of a quality assurance (QA) and quality control (QC) system is an essential task in order to ensure that the designed quality is achieved so that the necessary precaution against damage is taken. In this paper, a detailed description of QA and QC to be applied to the planned Konrad repository as well as the basic principles and the present status of the waste package QC are indicated and discussed.

  14. Salt repository project closeout status report

    SciTech Connect (OSTI)

    NONE

    1988-06-01T23:59:59.000Z

    This report provides an overview of the scope and status of the US Department of Energy (DOE`s) Salt Repository Project (SRP) at the time when the project was terminated by the Nuclear Waste Policy Amendments Act of 1987. The report reviews the 10-year program of siting a geologic repository for high-level nuclear waste in rock salt formations. Its purpose is to aid persons interested in the information developed during the course of this effort. Each area is briefly described and the major items of information are noted. This report, the three salt Environmental Assessments, and the Site Characterization Plan are the suggested starting points for any search of the literature and information developed by the program participants. Prior to termination, DOE was preparing to characterize three candidate sites for the first mined geologic repository for the permanent disposal of high-level nuclear waste. The sites were in Nevada, a site in volcanic tuff; Texas, a site in bedded salt (halite); and Washington, a site in basalt. These sites, identified by the screening process described in Chapter 3, were selected from the nine potentially acceptable sites shown on Figure I-1. These sites were identified in accordance with provisions of the Nuclear Waste Policy Act of 1982. 196 refs., 21 figs., 11 tabs.

  15. Applying insights from repository safety assessments.

    SciTech Connect (OSTI)

    Swift, Peter N.

    2010-03-01T23:59:59.000Z

    Despite decades of international consensus that deep geological disposal is the best option for permanent management of long-lived high-level radioactive wastes, no repositories for used nuclear fuel or high-level waste are in operation. Detailed long-term safety assessments have been completed worldwide for a wide range of repository designs and disposal concepts, however, and valuable insights from these assessments are available to inform future decisions about managing radioactive wastes. Qualitative comparisons among the existing safety assessments for disposal concepts in clay, granite, salt, and unsaturated volcanic tuff show how different geologic settings can be matched with appropriate engineered barrier systems to provide a high degree of confidence in the long-term safety of geologic disposal. Review of individual assessments provides insights regarding the release pathways and radionuclides that are most likely to contribute to estimated doses to humans in the far future for different disposal concepts, and can help focus research and development programs to improve management and disposal technologies. Lessons learned from existing safety assessments may be particularly relevant for informing decisions during the process of selecting potential repository sites.

  16. Collecting apparatus

    DOE Patents [OSTI]

    Duncan, Charles P. (Walnut Creek, CA)

    1983-01-01T23:59:59.000Z

    An improved collecting apparatus for small aquatic or airborne organisms such as plankton, larval fish, insects, etc. The improvement constitutes an apertured removal container within which is retained a collecting bag, and which is secured at the apex of a conical collecting net. Such collectors are towed behind a vessel or vehicle with the open end of the conical net facing forward for trapping the aquatic or airborne organisms within the collecting bag, while allowing the water or air to pass through the apertures in the container. The container is readily removable from the collecting net whereby the collecting bag can be quickly removed and replaced for further sample collection. The collecting bag is provided with means for preventing the bag from being pulled into the container by the water or air flowing therethrough.

  17. Leachate Chemistry of Field-Weathered Spent Mushroom Substrate Mingxin Guo, Jon Chorover,* Rex Rosario, and Richard H. Fox

    E-Print Network [OSTI]

    Chorover, Jon

    leaching an SMS­peat column with distilled water at leachate and effects of infiltration. Two SMS piles of protecting ground DOC, 0.7 kg of dissolved N, and 13.6 kg of inorganic salts. The 150- water resources of SMS are com- to the field at high rates, SMS may pollute ground water.posted straw, hay, peat, horse

  18. On-Site Pilot Study - Removal of Uranium, Radium-226 and Arsenic from Impacted Leachate by Reverse Osmosis - 13155

    SciTech Connect (OSTI)

    McMurray, Allan; Everest, Chris; Rilling, Ken [Conestoga-Rovers and Associates, 651 Colby Dr, Waterloo, ON (Canada)] [Conestoga-Rovers and Associates, 651 Colby Dr, Waterloo, ON (Canada); Vandergaast, Gary [Atomic Energy of Canada Ltd, 115 Toronto Road, Port Hope, ON (Canada)] [Atomic Energy of Canada Ltd, 115 Toronto Road, Port Hope, ON (Canada); LaMonica, David [RoChem Membrane Systems Inc., 430 30th Street, Hermosa Beach, CA (United States)] [RoChem Membrane Systems Inc., 430 30th Street, Hermosa Beach, CA (United States)

    2013-07-01T23:59:59.000Z

    Conestoga-Rovers and Associates (CRA-LTD) performed an on-site pilot study at the Welcome Waste Management Facility in Port Hope, Ontario, Canada, to evaluate the effectiveness of a unique leachate treatment process for the removal of radioactive contaminants from leachate impacted by low-level radioactive waste. Results from the study also provided the parameters needed for the design of the CRA-LTD full scale leachate treatment process design. The final effluent water quality discharged from the process to meet the local surface water discharge criteria. A statistical software package was utilized to obtain the analysis of variance (ANOVA) for the results from design of experiment applied to determine the effect of the evaluated factors on the measured responses. The factors considered in the study were: percent of reverse osmosis permeate water recovery, influent coagulant dosage, and influent total dissolved solids (TDS) dosage. The measured responses evaluated were: operating time, average specific flux, and rejection of radioactive contaminants along with other elements. The ANOVA for the design of experiment results revealed that the operating time is affected by the percent water recovery to be achieved and the flocculant dosage over the range studied. The average specific flux and rejection for the radioactive contaminants were not affected by the factors evaluated over the range studied. The 3 month long on-site pilot testing on the impacted leachate revealed that the CRA-LTD leachate treatment process was robust and produced an effluent water quality that met the surface water discharge criteria mandated by the Canadian Nuclear Safety Commission and the local municipality. (authors)

  19. Inheritance of chemical constituents in leachate from the seed coat of cotton (Gossypium hirsutum L.) and their interrelations with several seed characters

    E-Print Network [OSTI]

    Percy, Richard Greer

    1979-01-01T23:59:59.000Z

    on the basis of their performance in previous leachate in- vestigations. The OR-37-72 and SP37-16-70 strain. , were selected because of their high seed leachate ionic content. Lankart 57 was chosen be- cause of its consistently low seed leachate readings... in previous invest- igations. The pedigrees of these cultivars follow: l. OR-37-72 ? An okra leaf, frego bract selection from the OR family. The strain was developed in the following manner with accompanying ~i selection and selfing: [(Lankart goes. x...

  20. BUOYANCY FLOW IN FRACTURES INTERSECTING A NUCLEAR WASTE REPOSITORY

    E-Print Network [OSTI]

    Wang, J.S.Y.

    2010-01-01T23:59:59.000Z

    discharge •side. As the wastes heat up the rock formationLBL—11112 "Heat Transfer to Nuclear Waste Disposal", ASMEv INTRODUCTION Heat released from a nuclear waste repository

  1. Key Factors for Digital Collections August 7, 2007

    E-Print Network [OSTI]

    by Fondren's Digital Library Initiative We evaluate digital projects on a case by case basis. There is no oneKey Factors for Digital Collections August 7, 2007 Rice University Digital Repository Supported formula for this process and in fact welcome open discussion on potential digital projects

  2. MOBILIZATION AND CHARACTERIZATION OF COLLOIDS GENERATED FROM CEMENT LEACHATES MOVING THROUGH A SRS SANDY SEDIMENT

    SciTech Connect (OSTI)

    Li, D.; Roberts, K.; Kaplan, D.; Seaman, J.

    2011-09-20T23:59:59.000Z

    Naturally occurring mobile colloids are ubiquitous and are involved in many important processes in the subsurface zone. For example, colloid generation and subsequent mobilization represent a possible mechanism for the transport of contaminants including radionuclides in the subsurface environments. For colloid-facilitated transport to be significant, three criteria must be met: (1) colloids must be generated; (2) contaminants must associate with the colloids preferentially to the immobile solid phase (aquifer); and (3) colloids must be transported through the groundwater or in subsurface environments - once these colloids start moving they become 'mobile colloids'. Although some experimental investigations of particle release in natural porous media have been conducted, the detailed mechanisms of release and re-deposition of colloidal particles within natural porous media are poorly understood. Even though this vector of transport is known, the extent of its importance is not known yet. Colloid-facilitated transport of trace radionuclides has been observed in the field, thus demonstrating a possible radiological risk associated with the colloids. The objective of this study was to determine if cementitious leachate would promote the in situ mobilization of natural colloidal particles from a SRS sandy sediment. The intent was to determine whether cementitious surface or subsurface structure would create plumes that could produce conditions conducive to sediment dispersion and mobile colloid generation. Column studies were conducted and the cation chemistries of influents and effluents were analyzed by ICP-OES, while the mobilized colloids were characterized using XRD, SEM, EDX, PSD and Zeta potential. The mobilization mechanisms of colloids in a SRS sandy sediment by cement leachates were studied.

  3. Water-Steel Canister Interaction and H2 Gas Pressure Buildup in a Nuclear Waste Repository

    E-Print Network [OSTI]

    Xu, Tianfu; Senger, Rainer; Finstele, Stefan

    2008-01-01T23:59:59.000Z

    Nuclear Waste Repository T. Xu & S. Finsteiie Earth Sciencesdeep lying repositories for nuclear waste. Nagra Techni­ calthe system state in a nuclear waste re­ pository. 2 PROCESS

  4. Corrosion-induced gas generation in a nuclear waste repository: Reactive geochemistry and multiphase flow effect

    E-Print Network [OSTI]

    Xu, T.

    2009-01-01T23:59:59.000Z

    Lying Repositories for Nuclear Waste, NAGRA Technical Reporthost rock formation for nuclear waste storage. EngineeringGas Generation in a Nuclear Waste Repository: Reactive

  5. Cigeo, the French Geological Repository Project - 13022

    SciTech Connect (OSTI)

    Labalette, Thibaud; Harman, Alain; Dupuis, Marie-Claude; Ouzounian, Gerald [ANDRA, 1-7, rue Jean Monnet, 92298 Chatenay-Malabry Cedex (France)] [ANDRA, 1-7, rue Jean Monnet, 92298 Chatenay-Malabry Cedex (France)

    2013-07-01T23:59:59.000Z

    The Cigeo industrial-scale geological disposal centre is designed for the disposal of the most highly-radioactive French waste. It will be built in an argillite formation of the Callovo-Oxfordian dating back 160 million years. The Cigeo project is located near the Bure village in the Paris Basin. The argillite formation was studied since 1974, and from the Meuse/Haute-Marne underground research laboratory since end of 1999. Most of the waste to be disposed of in the Cigeo repository comes from nuclear power plants and from reprocessing of their spent fuel. (authors)

  6. Espinosa Glaze Polychrome Bowl New Mexico Cultural Assets Digital Repository

    E-Print Network [OSTI]

    Maccabe, Barney

    Espinosa Glaze Polychrome Bowl NM CADRe New Mexico Cultural Assets Digital Repository and e for Advanced Research Computing; thomas@phys.unm.edu) Led by the University of New Mexico Maxwell Museum of Anthropology (MMA), the New Mexico Cultural Assets Digital Repository and efacility is being established

  7. 11 A WYSIWYG Interface for User-Friendly Access to Geospatial Data Collections

    E-Print Network [OSTI]

    Jenny, Bernhard

    11 A WYSIWYG Interface for User-Friendly Access to Geospatial Data Collections Helen Jenny1 offer online access to their geospatial data repositories. Users can visually browse and some- times greatly from novice to GIS expert. Two types of user interfaces for geospatial data collections

  8. Hydro-mechanical behavior of Municipal Solid Waste subject to leachate recirculation in a large-scale compression reactor cell

    SciTech Connect (OSTI)

    Olivier, Franck [Environment, Energy and Waste Research Center (CREED), 291, avenue Dreyfous Ducas, 78520 Limay (France) and Laboratoire LIRIGM - Maison des Geosciences, 1381, rue de la piscine 38400 Saint-Martin d'Heres (France)]. E-mail: franck.olivier@ujf-grenoble.fr; Gourc, Jean-Pierre [Laboratoire LIRIGM - Maison des Geosciences, 1381, rue de la piscine 38400 Saint-Martin d'Heres (France)]. E-mail: gourc@ujf-grenoble.fr

    2007-07-01T23:59:59.000Z

    The paper presents the results of a laboratory experiment on Municipal Solid Waste (MSW) subjected to one-dimensional compression in a 1 m{sup 3} instrumented cell. The focus was on the hydro-mechanical behavior of the material under conditions of confinement and leachate percolation that replicate those found in real-scale landfills. The operation of the apparatus is detailed together with the testing methodology and the monitoring program. Two samples of waste were tested: the first extended over a period of 10 months ('Control Test') and the second for 22 months ('Enhanced Test' with leachate recirculation). Consolidation data is reported with regard to both short-term (stress-dependent) and long-term (time-dependent) settlements. A discussion follows based on the derived values of primary and secondary compression ratios. Correlations between compression parameters and the biodegradation process are presented. In particular, results clearly highlight the effect of leachate recirculation on waste settlement: 24% secondary deformation reached after slightly less than 2 years (equivalent to a 5-fold increase in compressibility) and 17.9% loss of dry matter. Comparisons are proposed considering the results derived from the few monitoring programs conducted on experimental bioreactors worldwide. Finally, the hydraulic characterization of waste is discussed with regard to the evaluation of effective porosity and permeability.

  9. Draft Area Recommendation Report for the Crystalline Repository Project: Overview. [Second repository

    SciTech Connect (OSTI)

    none,

    1986-01-01T23:59:59.000Z

    The draft Area Recommendation Report (ARR) for the Crystalline Repository Project identifies portions of crystalline rock bodies as proposed potentially acceptable sites for the Nation's second repository for deep geologic burial of high-level radioactive waste and spent nuclear fuel. This Overview provides a brief summary of that report. The US Department of Energy (DOE) evaluated available geologic and environmental data for 235 crystalline rock bodies in the North Central, Northeastern, and Southeastern Regions to identify preliminary candidate areas. The 12 proposed potentially acceptable sites are located in the States of Georgia (1), Maine (2), Minnesota (3), New Hampshire (1), North Carolina (2), Virginia (2), and Wisconsin (1). The data, analyses and rationale pertaining to the identification of the 12 proposed potentially acceptable sites are presented in the draft ARR. The analyses presented in the draft ARR demonstrate that the evidence available for each proposed potentially acceptable site supports (1) a finding that the site is not disqualified under Appendix III of the DOE Siting Guidelines and (2) a decision to proceed with the continued investigation of the site on the basis of the favorable and potentially adverse conditions identified to date. These potentially acceptable sites will be investigated and evaluated in more detail during the area phase of the siting process and considered along with other candidate sites in a progressive narrowing process to finally choose the site of the second repository in 1998.

  10. Repository Subsurface Preliminary Fire Hazard Analysis

    SciTech Connect (OSTI)

    Richard C. Logan

    2001-07-30T23:59:59.000Z

    This fire hazard analysis identifies preliminary design and operations features, fire, and explosion hazards, and provides a reasonable basis to establish the design requirements of fire protection systems during development and emplacement phases of the subsurface repository. This document follows the Technical Work Plan (TWP) (CRWMS M&O 2001c) which was prepared in accordance with AP-2.21Q, ''Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities''; Attachment 4 of AP-ESH-008, ''Hazards Analysis System''; and AP-3.11Q, ''Technical Reports''. The objective of this report is to establish the requirements that provide for facility nuclear safety and a proper level of personnel safety and property protection from the effects of fire and the adverse effects of fire-extinguishing agents.

  11. Repository surface design site layout analysis

    SciTech Connect (OSTI)

    Montalvo, H.R.

    1998-02-27T23:59:59.000Z

    The purpose of this analysis is to establish the arrangement of the Yucca Mountain Repository surface facilities and features near the North Portal. The analysis updates and expands the North Portal area site layout concept presented in the ACD, including changes to reflect the resizing of the Waste Handling Building (WHB), Waste Treatment Building (WTB), Carrier Preparation Building (CPB), and site parking areas; the addition of the Carrier Washdown Buildings (CWBs); the elimination of the Cask Maintenance Facility (CMF); and the development of a concept for site grading and flood control. The analysis also establishes the layout of the surface features (e.g., roads and utilities) that connect all the repository surface areas (North Portal Operations Area, South Portal Development Operations Area, Emplacement Shaft Surface Operations Area, and Development Shaft Surface Operations Area) and locates an area for a potential lag storage facility. Details of South Portal and shaft layouts will be covered in separate design analyses. The objective of this analysis is to provide a suitable level of design for the Viability Assessment (VA). The analysis was revised to incorporate additional material developed since the issuance of Revision 01. This material includes safeguards and security input, utility system input (size and location of fire water tanks and pump houses, potable water and sanitary sewage rates, size of wastewater evaporation pond, size and location of the utility building, size of the bulk fuel storage tank, and size and location of other exterior process equipment), main electrical substation information, redundancy of water supply and storage for the fire support system, and additional information on the storm water retention pond.

  12. Evaluating new waste form impacts on repository capacity from a total system perspective

    SciTech Connect (OSTI)

    Kim, D.K. [Office of Radioactive Waste Management, U.S. Dept. of Energy, S.W., Washington DC (United States); Nutt, W.M. [Golder Associates Inc., Las Vegas NV (United States); Dravo, A.N.; Seitz, M.G. [Booz Allen Hamilton, Washington DC (United States)

    2007-07-01T23:59:59.000Z

    This paper summarizes the steps that need to be taken to develop a long-term performance assessment of a repository and discusses the potential impacts on the existing performance assessment model that could result from a national decision to dispose of wastes from an advanced fuel cycle, such as that envisioned under the Global Nuclear Energy Partnership (GNEP). The objective is to establish a common understanding of what activities would potentially need to be conducted, and why, to support the disposal of high level wastes from an advanced nuclear fuel cycle. The long-term performance of the proposed repository at Yucca Mountain is currently evaluated using a methodology called Total System Performance Assessment (TSPA). The TSPA methodology can be applied to evaluate the safety of the disposal of nuclear wastes arising from GNEP technologies. The entire TSPA would need to be updated in accordance with U.S. Nuclear Regulatory Commission (NRC) requirements for a license to accommodate GNEP wastes. The revised TSPA would have to reflect the entire repository system as configured to dispose of these wastes. Major changes in the TSPA expected from introduction of GNEP wastes would be in two areas. First, the features, events and processes (FEPs) that might affect performance of the geologic system would have to be re-evaluated considering the GNEP wastes and any corresponding changes to the repository design. The modeling hierarchy used in the TSPA would then be modified to reflect any revised FEPs and scenarios. Secondly, the input and boundary conditions of some models used in the TSPA would have to be revised based on characteristics of the GNEP nuclear wastes and any associated change to the repository design. Some new models would likely have to be developed, for example due to new waste form types. These model revisions would likely require additional data such as characteristics of new waste forms. Post-closure performance assessment should be an integral part of the GNEP program with models developing in an iterative and integrated manner. Testing, analyses, and modeling of nuclear wastes supported by GNEP should strive to meet the requirements for data and processes established by NRC regulations and the U.S. Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM). This rigor will assure that a revision to the post-closure safety analysis is technically defensible in a regulatory environment. Qualifying data to describe changes introduced by GNEP wastes would have to undergo the same rigor and compliance with procedures as the data collection and modeling that supports the original license application. (authors)

  13. EM Gains Insight from Germany on Salt-Based Repositories

    Broader source: Energy.gov [DOE]

    KARLSRUHE and PEINE, Germany – EM officials recently took part in workshops in Germany to benefit from the exchange of research and experience operating salt-based repositories for radioactive waste.

  14. The DSpace Institutional Digital Repository System: Current Functionality

    E-Print Network [OSTI]

    Tansley, Robert

    2003-01-01T23:59:59.000Z

    In this paper we describe DSpaceâ?¢, an open source system that acts as a repository for digital research and educational material produced by an organization or institution. DSpace was developed during two years’ collaboration ...

  15. Automated Validation of Trusted Digital Repository Assessment Criteria

    E-Print Network [OSTI]

    Smith, MacKenzie

    The RLG/NARA trusted digital repository (TDR) certification checklist defines a set of assessment criteria for preservation environments. The criteria can be mapped into data management policies that define how a digital ...

  16. Establish and Operate a Geologic Core and Sample Repository in Midland, Texas

    SciTech Connect (OSTI)

    Tyler, Noel

    2000-08-14T23:59:59.000Z

    Shell Oil Company donated its proprietary core and sample repository to the Bureau of Economic Geology, The University of Texas at Austin, in 1994. This collection of geologic materials is composed of 325,000 boxes of rocks and samples housed in a 32,700-ft{sup 2} warehouse in Midland, Texas. The material includes cores from more than 3,000 wells (75,000 boxes) and cuttings from more than 90,000 wells (260,000 boxes). In addition to the warehouse space, the repository consists of layout rooms, a processing room, and office space. The U.S. Department of Energy provided $375,000 under Grant Number DE-FG22-94BC14854 for organizing the collection, staffing the facility, and making the material available to the public for the first 5 years of operation. Shell Oil Company provided an endowment of $1.3 million to cover the cost of operating the facility after the fifth year of operation.

  17. Multiple-code benchmark simulation study of coupled THMC processes in the excavation disturbed zone associated with geological nuclear waste repositories

    E-Print Network [OSTI]

    2006-01-01T23:59:59.000Z

    filled and open-drift nuclear waste repositories in Task DASSOCIATED WITH GEOLOGICAL NUCLEAR WASTE REPOSITORIES J.emplacement drifts of a nuclear waste repository. This BMT

  18. An analysis of repository waste-handling operations

    SciTech Connect (OSTI)

    Dennis, A.W.

    1990-09-01T23:59:59.000Z

    This report has been prepared to document the operational analysis of waste-handling facilities at a geologic repository for high-level nuclear waste. The site currently under investigation for the geologic repository is located at Yucca Mountain, Nye County, Nevada. The repository waste-handling operations have been identified and analyzed for the year 2011, a steady-state year during which the repository receives spent nuclear fuel containing the equivalent of 3000 metric tons of uranium (MTU) and defense high-level waste containing the equivalent of 400 MTU. As a result of this analysis, it has been determined that the waste-handling facilities are adequate to receive, prepare, store, and emplace the projected quantity of waste on an annual basis. In addition, several areas have been identified where additional work is required. The recommendations for future work have been divided into three categories: items that affect the total waste management system, operations within the repository boundary, and the methodology used to perform operational analyses for repository designs. 7 refs., 48 figs., 11 tabs.

  19. LIFE Materials: Fuel Cycle and Repository Volume 11

    SciTech Connect (OSTI)

    Shaw, H; Blink, J A

    2008-12-12T23:59:59.000Z

    The fusion-fission LIFE engine concept provides a path to a sustainable energy future based on safe, carbon-free nuclear power with minimal nuclear waste. The LIFE design ultimately offers many advantages over current and proposed nuclear energy technologies, and could well lead to a true worldwide nuclear energy renaissance. When compared with existing and other proposed future nuclear reactor designs, the LIFE engine exceeds alternatives in the most important measures of proliferation resistance and waste minimization. The engine needs no refueling during its lifetime. It requires no removal of fuel or fissile material generated in the LIFE engine. It leaves no weapons-attractive material at the end of life. Although there is certainly a need for additional work, all indications are that the 'back end' of the fuel cycle does not to raise any 'showstopper' issues for LIFE. Indeed, the LIFE concept has numerous benefits: (1) Per unit of electricity generated, LIFE engines would generate 20-30 times less waste (in terms of mass of heavy metal) requiring disposal in a HLW repository than does the current once-through fuel cycle. (2) Although there may be advanced fuel cycles that can compete with LIFE's low mass flow of heavy metal, all such systems require reprocessing, with attendant proliferation concerns; LIFE engines can do this without enrichment or reprocessing. Moreover, none of the advanced fuel cycles can match the low transuranic content of LIFE waste. (3) The specific thermal power of LIFE waste is initially higher than that of spent LWR fuel. Nevertheless, this higher thermal load can be managed using appropriate engineering features during an interim storage period, and could be accommodated in a Yucca-Mountain-like repository by appropriate 'staging' of the emplacement of waste packages during the operational period of the repository. The planned ventilation rates for Yucca Mountain would be sufficient for LIFE waste to meet the thermal constraints of the repository design. (4) A simple, but arguably conservative, estimate for the dose from a repository containing 63,000 MT of spent LIFE fuel would have similar performance to the currently planned Yucca Mountain Repository. This indicates that a properly designed 'LIFE Repository' would almost certainly meet the proposed Nuclear Regulatory Commission standards for dose to individuals, even though the waste in such a repository would have produced 20-30 times more generated electricity than the reference case for Yucca Mountain. The societal risk/benefit ratio for a LIFE repository would therefore be significantly better than for currently planned repositories for LWR fuel.

  20. Characteristics of potential repository wastes. Volume 2

    SciTech Connect (OSTI)

    Not Available

    1992-07-01T23:59:59.000Z

    The LWR spent fuels discussed in Volume 1 of this report comprise about 99% of all domestic non-reprocessed spent fuel. In this report we discuss other types of spent fuels which, although small in relative quantity, consist of a number of diverse types, sizes, and compositions. Many of these fuels are candidates for repository disposal. Some non-LWR spent fuels are currently reprocessed or are scheduled for reprocessing in DOE facilities at the Savannah River Site, Hanford Site, and the Idaho National Engineering Laboratory. It appears likely that the reprocessing of fuels that have been reprocessed in the past will continue and that the resulting high-level wastes will become part of defense HLW. However, it is not entirely clear in some cases whether a given fuel will be reprocessed, especially in cases where pretreatment may be needed before reprocessing, or where the enrichment is not high enough to make reprocessing attractive. Some fuels may be canistered, while others may require special means of disposal. The major categories covered in this chapter include HTGR spent fuel from the Fort St. Vrain and Peach Bottom-1 reactors, research and test reactor fuels, and miscellaneous fuels, and wastes generated from the decommissioning of facilities.

  1. Technical assistance to Ohio closure sites; Technologies to address leachate from the on-site disposal facility at Fernald Environmental Management Project, Ohio

    SciTech Connect (OSTI)

    Hazen, Terry

    2002-08-26T23:59:59.000Z

    On August 6-7, 2002, a Technical Assistance Team (''Team'') from the U.S. Department of Energy (DOE) Subsurface Contaminants Focus Area (SCFA) met with Fernald Environmental Management Project (FEMP) personnel in Ohio to assess approaches to remediating uranium-contaminated leachate from the On-Site Disposal Facility (OSDF). The Team was composed of technical experts from national labs, technology centers, and industry and was assembled in response to a request from the FEMP Aquifer Restoration Project. Dave Brettschneider of Fluor Fernald, Inc., requested that a Team of experts be convened to review technologies for the removal of uranium in both brine ion exchange regeneration solution from the Advanced Wastewater Treatment facility and in the leachate from the OSDF. The Team was asked to identify one or more technologies for bench-scale testing as a cost effective alternative to remove uranium so that the brine regeneration solution from the Advanced Waste Water Treatment facility and the leachate from the OSDF can be discharged without further treatment. The Team was also requested to prepare a recommended development and demonstration plan for the alternative technologies. Finally, the Team was asked to make recommendations on the optimal technical solution for field implementation. The Site's expected outcomes for this effort are schedule acceleration, cost reduction, and better long-term stewardship implementation. To facilitate consideration of the most appropriate technologies, the Team was divided into two groups to consider the brine and the leachate separately, since they represent different sources with different constraints on solutions, e.g., short-term versus very long-term and concentrated versus dilute contaminant matrices. This report focuses on the technologies that are most appropriate for the leachate from the OSDF. Upon arriving at FEMP, project personnel asked the Team to concentrate its efforts on evaluating potential technologies and strategies to reduce uranium concentration in the leachate.

  2. Results from an International Simulation Study on Coupled Thermal, Hydrological, and Mechanical (THM) Processes near Geological Nuclear Waste Repositories

    E-Print Network [OSTI]

    Rutqvist, J.

    2008-01-01T23:59:59.000Z

    safety of a hypothetical nuclear waste repository – BMT1 ofAssociated with Nuclear Waste Repositories, Academic Press,safety of a hypothetical nuclear waste repository – BMT1 of

  3. Integrating repositories with fuel cycles: The airport authority model

    SciTech Connect (OSTI)

    Forsberg, C. [Massachusetts Inst. of Technology, 77 Massachusetts Avenue, Cambridge, MA 02139-4307 (United States)

    2012-07-01T23:59:59.000Z

    The organization of the fuel cycle is a legacy of World War II and the cold war. Fuel cycle facilities were developed and deployed without consideration of the waste management implications. This led to the fuel cycle model of a geological repository site with a single owner, a single function (disposal), and no other facilities on site. Recent studies indicate large economic, safety, repository performance, nonproliferation, and institutional incentives to collocate and integrate all back-end facilities. Site functions could include geological disposal of spent nuclear fuel (SNF) with the option for future retrievability, disposal of other wastes, reprocessing with fuel fabrication, radioisotope production, other facilities that generate significant radioactive wastes, SNF inspection (navy and commercial), and related services such as SNF safeguards equipment testing and training. This implies a site with multiple facilities with different owners sharing some facilities and using common facilities - the repository and SNF receiving. This requires a different repository site institutional structure. We propose development of repository site authorities modeled after airport authorities. Airport authorities manage airports with government-owned runways, collocated or shared public and private airline terminals, commercial and federal military facilities, aircraft maintenance bases, and related operations - all enabled and benefiting the high-value runway asset and access to it via taxi ways. With a repository site authority the high value asset is the repository. The SNF and HLW receiving and storage facilities (equivalent to the airport terminal) serve the repository, any future reprocessing plants, and others with needs for access to SNF and other wastes. Non-public special-built roadways and on-site rail lines (equivalent to taxi ways) connect facilities. Airport authorities are typically chartered by state governments and managed by commissions with members appointed by the state governor, county governments, and city governments. This structure (1) enables state and local governments to work together to maximize job and tax benefits to local communities and the state, (2) provides a mechanism to address local concerns such as airport noise, and (3) creates an institutional structure with large incentives to maximize the value of the common asset, the runway. A repository site authority would have a similar structure and be the local interface to any national waste management authority. (authors)

  4. Monte Carlo simulations for generic granite repository studies

    SciTech Connect (OSTI)

    Chu, Shaoping [Los Alamos National Laboratory; Lee, Joon H [SNL; Wang, Yifeng [SNL

    2010-12-08T23:59:59.000Z

    In a collaborative study between Los Alamos National Laboratory (LANL) and Sandia National Laboratories (SNL) for the DOE-NE Office of Fuel Cycle Technologies Used Fuel Disposition (UFD) Campaign project, we have conducted preliminary system-level analyses to support the development of a long-term strategy for geologic disposal of high-level radioactive waste. A general modeling framework consisting of a near- and a far-field submodel for a granite GDSE was developed. A representative far-field transport model for a generic granite repository was merged with an integrated systems (GoldSim) near-field model. Integrated Monte Carlo model runs with the combined near- and farfield transport models were performed, and the parameter sensitivities were evaluated for the combined system. In addition, a sub-set of radionuclides that are potentially important to repository performance were identified and evaluated for a series of model runs. The analyses were conducted with different waste inventory scenarios. Analyses were also conducted for different repository radionuelide release scenarios. While the results to date are for a generic granite repository, the work establishes the method to be used in the future to provide guidance on the development of strategy for long-term disposal of high-level radioactive waste in a granite repository.

  5. Proceedings of the scientific visit on crystalline rock repository development.

    SciTech Connect (OSTI)

    Mariner, Paul E.; Hardin, Ernest L.; Miksova, Jitka [RAWRA, Czech Republic

    2013-02-01T23:59:59.000Z

    A scientific visit on Crystalline Rock Repository Development was held in the Czech Republic on September 24-27, 2012. The visit was hosted by the Czech Radioactive Waste Repository Authority (RAWRA), co-hosted by Sandia National Laboratories (SNL), and supported by the International Atomic Energy Agency (IAEA). The purpose of the visit was to promote technical information exchange between participants from countries engaged in the investigation and exploration of crystalline rock for the eventual construction of nuclear waste repositories. The visit was designed especially for participants of countries that have recently commenced (or recommenced) national repository programmes in crystalline host rock formations. Discussion topics included repository programme development, site screening and selection, site characterization, disposal concepts in crystalline host rock, regulatory frameworks, and safety assessment methodology. Interest was surveyed in establishing a %E2%80%9Cclub,%E2%80%9D the mission of which would be to identify and address the various technical challenges that confront the disposal of radioactive waste in crystalline rock environments. The idea of a second scientific visit to be held one year later in another host country received popular support. The visit concluded with a trip to the countryside south of Prague where participants were treated to a tour of the laboratory and underground facilities of the Josef Regional Underground Research Centre.

  6. DSpace : An Institutional Repository from the MIT Libraries and Hewlett Packard Laboratories

    E-Print Network [OSTI]

    Smith, MacKenzie

    2002-01-01T23:59:59.000Z

    The DSpaceâ?¢ project of the MIT Libraries and the Hewlett Packard Laboratories has built an institutional repository system for digital research material. This paper will describe the rationale for institutional repositories, ...

  7. Beyond institutional repositories *Laurent Romary, INRIA (Gemo research group) & Humboldt Universitt zu Berlin

    E-Print Network [OSTI]

    Boyer, Edmond

    Society (Max Planck Digital Library) armbruster@mpdl.mpg.de Invalidenstrasse 35, D-10115 Berlin - www the needs of the scholarly community, scientific communication and accompanied stakeholders in a sustainable repositories, institutional repositories, digital libraries, research infrastructure, deposit mandate

  8. U.S. Department of Energy Awards a Contract to USA Repository...

    Energy Savers [EERE]

    a Contract to USA Repository Services for Management and Operating Contractor Support for the Yucca Mountain Project U.S. Department of Energy Awards a Contract to USA Repository...

  9. Implementation of the Brazilian National Repository - RBMN Project - 13008

    SciTech Connect (OSTI)

    Cassia Oliveira de Tello, Cledola [CDTN - Center for Development of Nuclear Technology, Av. Presidente Antonio Carlos, 6.627 - Campus UFMG - Pampulha, CEP 31270-901 - Belo Horizonte - MG (Brazil)

    2013-07-01T23:59:59.000Z

    Ionizing radiation in Brazil is used in electricity generation, medicine, industry, agriculture and for research and development purposes. All these activities can generate radioactive waste. At this point, in Brazil, the use of nuclear energy and radioisotopes justifies the construction of a national repository for radioactive wastes of low and intermediate-level. According to Federal Law No. 10308, Brazilian National Commission for Nuclear Energy (CNEN) is responsible for designing and constructing the intermediate and final storages for radioactive wastes. Additionally, a restriction on the construction of Angra 3 is that the repository is under construction until its operation start, attaining some requirements of the Brazilian Environmental Regulator (IBAMA). Besides this NPP, in the National Energy Program is previewed the installation of four more plants, by 2030. In November 2008, CNEN launched the Project RBMN (Repository for Low and Intermediate-Level Radioactive Wastes), which aims at the implantation of a National Repository for disposal of low and intermediate-level of radiation wastes. This Project has some aspects that are unique in the Brazilian context, especially referring to the time between its construction and the end of its institutional period. This time is about 360 years, when the area will be released for unrestricted uses. It means that the Repository must be safe and secure for more than three hundred years, which is longer than half of the whole of Brazilian history. This aspect is very new for the Brazilian people, bringing a new dimension to public acceptance. Another point is this will be the first repository in South America, bringing a real challenge for the continent. The current status of the Project is summarized. (authors)

  10. The AutoMed Schema Integration Repository Michael Boyd, Peter M c . Brien and Nerissa Tong

    E-Print Network [OSTI]

    McBrien, Peter

    The AutoMed Schema Integration Repository Michael Boyd, Peter M c . Brien and Nerissa Tong {mboyd,pjm

  11. Nuclear waste repository transparency technology test bed demonstrations at WIPP

    SciTech Connect (OSTI)

    BETSILL,J. DAVID; ELKINS,NED Z.; WU,CHUAN-FU; MEWHINNEY,JAMES D.; AAMODT,PAUL

    2000-01-27T23:59:59.000Z

    Secretary of Energy, Bill Richardson, has stated that one of the nuclear waste legacy issues is ``The challenge of managing the fuel cycle's back end and assuring the safe use of nuclear power.'' Waste management (i.e., the back end) is a domestic and international issue that must be addressed. A key tool in gaining acceptance of nuclear waste repository technologies is transparency. Transparency provides information to outside parties for independent assessment of safety, security, and legitimate use of materials. Transparency is a combination of technologies and processes that apply to all elements of the development, operation, and closure of a repository system. A test bed for nuclear repository transparency technologies has been proposed to develop a broad-based set of concepts and strategies for transparency monitoring of nuclear materials at the back end of the fuel/weapons cycle. WIPP is the world's first complete geologic repository system for nuclear materials at the back end of the cycle. While it is understood that WIPP does not currently require this type of transparency, this repository has been proposed as realistic demonstration site to generate and test ideas, methods, and technologies about what transparency may entail at the back end of the nuclear materials cycle, and which could be applicable to other international repository developments. An integrated set of transparency demonstrations was developed and deployed during the summer, and fall of 1999 as a proof-of-concept of the repository transparency technology concept. These demonstrations also provided valuable experience and insight into the implementation of future transparency technology development and application. These demonstrations included: Container Monitoring Rocky Flats to WIPP; Underground Container Monitoring; Real-Time Radiation and Environmental Monitoring; Integrated level of confidence in the system and information provided. As the world's only operating deep geologic repository, the Waste Isolation Pilot Plant (WIPP) offers a unique opportunity to serve as an international cooperative test bed for developing and demonstrating technologies and processes in a fully operational repository system setting. To address the substantial national security implications for the US resulting from the lack of integrated, transparent management and disposition of nuclear materials at the back-end of the nuclear fuel and weapons cycles, it is proposed that WIPP be used as a test bed to develop and demonstrate technologies that will enable the transparent and proliferation-resistant geologic isolation of nuclear materials. The objectives of this initiative are to: (1) enhance public confidence in safe, secure geologic isolation of nuclear materials; (2) develop, test, and demonstrate transparency measures and technologies for the back-end of nuclear fuel cycle; and (3) foster international collaborations leading to workable, effective, globally-accepted standards for the transparent monitoring of geological repositories for nuclear materials. Test-bed activities include: development and testing of monitoring measures and technologies; international demonstration experiments; transparency workshops; visiting scientist exchanges; and educational outreach. These activities are proposed to be managed by the Department of Energy/Carlsbad Area Office (DOE/CAO) as part of The Center for Applied Repository and Underground Studies (CARUS).

  12. SHERPA Document SHERPA Document -Institutional Repositories: Staff and Skills Requirements

    E-Print Network [OSTI]

    Southampton, University of

    SHERPA Document SHERPA Document - Institutional Repositories: Staff and Skills Requirements Mary This document began in response to requests received by the core SHERPA team for examples of job descriptions and UKCORR members. This document will be revised annually (July/August) to reflect changing needs

  13. CSMRI DOCUMENT REPOSITORY INDEX Revised June 15, 2007

    E-Print Network [OSTI]

    Page 1 CSMRI DOCUMENT REPOSITORY INDEX Revised June 15, 2007 HARD COPY DOCUMENTS AVAILABLE 2002 - March 2003 3 New Horizons Project Records Capital Construction CSM 2002-2004 4 New Horizons - CSMRI Site Contaminated Material The S.M. Stoller Corporation April 1, 2005 7 Technical and Cost

  14. Effect of repository underground ventilation on emplacement drift temperature control

    SciTech Connect (OSTI)

    Yang, H.; Sun, Y.; McKenzie, D.G.; Bhattacharyya, K.K. [Morrison Knudson Corporation, Las Vegas, NV (United States)

    1996-02-01T23:59:59.000Z

    The repository advanced conceptual design (ACD) is being conducted by the Civilian Radioactive Waste Management System, Management & Operating Contractor. Underground ventilation analyses during ACD have resulted in preliminary ventilation concepts and design methodologies. This paper discusses one of the recent evaluations -- effects of ventilation on emplacement drift temperature management.

  15. Margaret A. Porter Collection

    E-Print Network [OSTI]

    Gonzalez, Gloria

    2012-01-01T23:59:59.000Z

    major clusters of Mazer collections related to West Coastinvisible histories visible collection notes from the NEH/project Margaret A. Porter Collection A s I processed the

  16. Nevada potential repository preliminary transportation strategy Study 2. Volume 1

    SciTech Connect (OSTI)

    NONE

    1996-02-01T23:59:59.000Z

    The objectives of this study were to build on the findings of the Nevada Potential Repository Preliminary Transportation Strategy Study 1 (CRWMS M&O 1995b), and to provide additional information for input to the repository environmental impact statement (EIS) process. In addition, this study supported the future selection of a preferred rail corridor and/or heavy haul route based on defensible data, methods, and analyses. Study research did not consider proposed legislation. Planning was conducted according to the Civilian Radioactive Waste Management Program Plan (DOE 1994a). The specific objectives of Study 2 were to: eliminate or reduce data gaps, inconsistencies, and uncertainties, and strengthen the analysis performed in Study 1; develop a preliminary list of rail route evaluation criteria that could be used to solicit input from stakeholders during scoping meetings. The evaluation criteria will be revised based on comments received during scoping; restrict and refine the width of the four rail corridors identified in Study 1 to five miles or less, based on land use constraints and engineering criteria identified and established in Study 2; evaluate national-level effects of routing spent nuclear fuel and high-level waste to the four identified branch lines, including the effects of routing through or avoiding Las Vegas; continue to gather published land use information and environmental data to support the repository EIS; continue to evaluate heavy haul truck transport over three existing routes as an alternative to rail and provide sufficient information to support the repository EIS process; and evaluate secondary uses for rail (passenger use, repository construction, shared use).

  17. Numerical study of the THM effects on the near-field safety of a hypothetical nuclear waste repository - BMT1 of the DECOVALEX III project. Part 3: Effects of THM coupling in sparsely fractured rocks

    E-Print Network [OSTI]

    2004-01-01T23:59:59.000Z

    Safety of a Hypothetical Nuclear Waste Repository – BMT1 ofsafety of a hypothetical nuclear waste repository – BMT1 ofsafety of a hypothetical nuclear waste repository – BMT1 of

  18. Repository-relevant testing applied to the Yucca Mountain Project

    SciTech Connect (OSTI)

    Bates, J.K.; Gerding, T.J.; Veleckis, E.

    1989-04-01T23:59:59.000Z

    A repository environment poses a challenge to developing a testing program because of the diverse nature of conditions that may exist at a given time during the life of the repository. A starting point is to identify whether any potential waste-water contact modes are particularly deleterious to the waste form performance, and whether any interactions between materials present in the waste package environment need to be accounted for during modeling the waste form reaction. The Unsaturated Test method in one approach that has been developed by the Yucca Mountain Project (YMP) to investigate the above issues, and a description of results that have been obtained during the testing of glass and unirradiated UO{sub 2} are the subject of this report. 10 refs., 7 figs., 4 tabs.

  19. Lithophysal Rock Mass Mechanical Properties of the Repository Host Horizon

    SciTech Connect (OSTI)

    D. Rigby

    2004-11-10T23:59:59.000Z

    The purpose of this calculation is to develop estimates of key mechanical properties for the lithophysal rock masses of the Topopah Spring Tuff (Tpt) within the repository host horizon, including their uncertainties and spatial variability. The mechanical properties to be characterized include an elastic parameter, Young's modulus, and a strength parameter, uniaxial compressive strength. Since lithophysal porosity is used as a surrogate property to develop the distributions of the mechanical properties, an estimate of the distribution of lithophysal porosity is also developed. The resulting characterizations of rock parameters are important for supporting the subsurface design, developing the preclosure safety analysis, and assessing the postclosure performance of the repository (e.g., drift degradation and modeling of rockfall impacts on engineered barrier system components).

  20. Repository relevant testing applied to the Yucca Mountain Project

    SciTech Connect (OSTI)

    Bates, J.K.; Woodland, A.B.; Wronkiewicz, D.J.; Cunnane, J.C.

    1990-10-01T23:59:59.000Z

    The tuff beds of Yucca Mountain, Nevada, are currently being investigated as a site for the disposal of high-level nuclear waste in an underground repository. If this site is found suitable, the repository would be located in the unsaturated zone above the water table, and a description of the site and the methodology of assessing the performance of the repository are described in the Site Characterization Plan (SCP). While many factors are accounted for during performance assessment, an important input parameter is the degradation behavior of the waste forms, which may be either spent fuel or reprocessed waste contained in a borosilicate glass matrix. To develop the necessary waste form degradation input, the waste package environment needs to be identified. This environment will change as the waste decays and also is a function of the repository design which has not yet been finalized. At the present time, an exact description of the waste package environment is not available. The SCP does provide an initial description of conditions that can be used to guide waste form evaluation. However, considerable uncertainty exists concerning the conditions under which waste form degradation and radionuclide release may occur after the waste package containment barriers are finally breached. The release conditions that are considered to be plausible include (1) a {open_quotes}bathtub{close_quotes} condition in which the waste becomes fully or partially submerged in water that enters the breached container and accumulates to fill the container up to the level of the breach opening, (2) a {open_quotes}wet drip{close_quotes} or {open_quotes}trickle through{close_quotes} condition in which the waste form is exposed to dripping water that enters through the top and exits the bottom of a container with multiple holes, and (3) a {open_quotes}dry{close_quotes} condition in which the waste form is exposed to a humid air environment.

  1. Thermal Conductivity of the Potential Repository Horizon Model Report

    SciTech Connect (OSTI)

    J. Ramsey

    2002-08-29T23:59:59.000Z

    The purpose of this report is to assess the spatial variability and uncertainty of thermal conductivity in the host horizon for the proposed repository at Yucca Mountain. More specifically, the lithostratigraphic units studied are located within the Topopah Spring Tuff (Tpt) and consist of the upper lithophysal zone (Tptpul), the middle nonlithophysal zone (Tptpmn), the lower lithophysal zone (Tptpll), and the lower nonlithophysal zone (Tptpln). The Tptpul is the layer directly above the repository host layers, which consist of the Tptpmn, Tptpll, and the Tptpln. Current design plans indicate that the largest portion of the repository will be excavated in the Tptpll (Board et al. 2002 [157756]). The main distinguishing characteristic among the lithophysal and nonlithophysal units is the percentage of large scale (cm-m) voids within the rock. The Tptpul and Tptpll, as their names suggest, have a higher percentage of lithophysae than the Tptpmn and the Tptpln. Understanding the influence of the lithophysae is of great importance to understanding bulk thermal conductivity and perhaps repository system performance as well. To assess the spatial variability and uncertainty of thermal conductivity, a model is proposed that is functionally dependent on the volume fraction of lithophysae and the thermal conductivity of the matrix portion of the rock. In this model, void space characterized as lithophysae is assumed to be air-saturated under all conditions, while void space characterized as matrix may be either water- or air-saturated. Lithophysae are assumed to be air-saturated under all conditions since the units being studied are all located above the water table in the region of interest, and the relatively strong capillary forces of the matrix will, under most conditions, preferentially retain any moisture present in the rock.

  2. HYDRIDE-RELATED DEGRADATION OF SNF CLADDING UNDER REPOSITORY CONDITIONS

    SciTech Connect (OSTI)

    K. McCoy

    2000-12-12T23:59:59.000Z

    The purpose and scope of this analysis/model report is to analyze the degradation of commercial spent nuclear fuel (CSNF) cladding under repository conditions by the hydride-related metallurgical processes, such as delayed hydride cracking (DHC), hydride reorientation and hydrogen embrittlement, thereby providing a better understanding of the degradation process and clarifying which aspects of the process are known and which need further evaluation and investigation. The intended use is as an input to a more general analysis of cladding degradation.

  3. Preliminary analyses of scenarios for potential human interference for repositories in three salt formations

    SciTech Connect (OSTI)

    Not Available

    1985-10-01T23:59:59.000Z

    Preliminary analyses of scenarios for human interference with the performance of a radioactive waste repository in a deep salt formation are presented. The following scenarios are analyzed: (1) the U-Tube Connection Scenario involving multiple connections between the repository and the overlying aquifer system; (2) the Single Borehole Intrusion Scenario involving penetration of the repository by an exploratory borehole that simultaneously connects the repository with overlying and underlying aquifers; and (3) the Pressure Release Scenario involving inflow of water to saturate any void space in the repository prior to creep closure with subsequent release under near lithostatic pressures following creep closure. The methodology to evaluate repository performance in these scenarios is described and this methodology is applied to reference systems in three candidate formations: bedded salt in the Palo Duro Basin, Texas; bedded salt in the Paradox Basin, Utah; and the Richton Salt Dome, Mississippi, of the Gulf Coast Salt Dome Basin.

  4. TNA Data Collection Tool

    Broader source: Energy.gov [DOE]

    The TNA Data Collection Tool Instructions provides guidance on how to complete the TNA Data Collection Tool. The TNA Data Collection Tool is an Excel spreadsheet that the organization's designating training POC will use to populate their organizations training needs.

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

    Broader source: Energy.gov [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...

  6. Comparison of potential radiological consequences from a spent-fuel repository and natural uranium deposits

    SciTech Connect (OSTI)

    Wick, O.J.; Cloninger, M.O.

    1980-09-01T23:59:59.000Z

    A general criterion has been suggested for deep geological repositories containing spent fuel - the repositories should impose no greater radiological risk than due to naturally occurring uranium deposits. The following analysis investigates the rationale of that suggestion and determines whether current expectations of spent-fuel repository performance are consistent with such a criterion. In this study, reference spent-fuel repositories were compared to natural uranium-ore deposits. Comparisons were based on intrinsic characteristics, such as radionuclide inventory, depth, proximity to aquifers, and regional distribution, and actual and potential radiological consequences that are now occurring from some ore deposits and that may eventually occur from repositories and other ore deposits. The comparison results show that the repositories are quite comparable to the natural ore deposits and, in some cases, present less radiological hazard than their natural counterparts. On the basis of the first comparison, placing spent fuel in a deep geologic repository apparently reduces the hazard from natural radioactive materials occurring in the earth's crust by locating the waste in impermeable strata without access to oxidizing conditions. On the basis of the second comparison, a repository constructed within reasonable constraints presents no greater hazard than a large ore deposit. It is recommended that if the naturally radioactive environment is to be used as a basis for a criterion regarding repositories, then this criterion should be carefully constructed. The criterion should be based on the radiological quality of the waters in the immediate region of a specific repository, and it should be in terms of an acceptable potential increase in the radiological content of those waters due to the existence of the repository.

  7. Development of an Integrated Natural Barrier Database System for Site Evaluation of a Deep Geologic Repository in Korea - 13527

    SciTech Connect (OSTI)

    Jung, Haeryong; Lee, Eunyong; Jeong, YiYeong; Lee, Jeong-Hwan [Korea Radioactive-waste Management Corportation - KRMC, 1045 Daedeokdaero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)] [Korea Radioactive-waste Management Corportation - KRMC, 1045 Daedeokdaero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)

    2013-07-01T23:59:59.000Z

    Korea Radioactive-waste Management Corporation (KRMC) established in 2009 has started a new project to collect information on long-term stability of deep geological environments on the Korean Peninsula. The information has been built up in the integrated natural barrier database system available on web (www.deepgeodisposal.kr). The database system also includes socially and economically important information, such as land use, mining area, natural conservation area, population density, and industrial complex, because some of this information is used as exclusionary criteria during the site selection process for a deep geological repository for safe and secure containment and isolation of spent nuclear fuel and other long-lived radioactive waste in Korea. Although the official site selection process has not been started yet in Korea, current integrated natural barrier database system and socio-economic database is believed that the database system will be effectively utilized to narrow down the number of sites where future investigation is most promising in the site selection process for a deep geological repository and to enhance public acceptance by providing readily-available relevant scientific information on deep geological environments in Korea. (authors)

  8. Thermally induced mechanical and permeability changes around a nuclear waste repository -- a far-field study based on equivalent properties determined by a discrete approach

    E-Print Network [OSTI]

    Min, Ki-Bok; Rutqvist, Jonny; Tsang, Chin-Fu; Jing, Lanru

    2004-01-01T23:59:59.000Z

    changes around a nuclear waste repository – a far-fieldmass containing a hypothetical nuclear waste repository. Thethe safe isolation of nuclear wastes from the biosphere,

  9. Bridging the Gap in the Chemical Thermodynamic Database for Nuclear Waste Repository: Studies of the Effect of Temperature on Actinide Complexation

    E-Print Network [OSTI]

    Rao, Linfeng

    2011-01-01T23:59:59.000Z

    Thermodynamic Database for Nuclear Waste Repository: Studiesthermodynamic database for nuclear waste repository wherethe safe management of nuclear wastes is to store the high-

  10. Building of multilevel stakeholder consensus in radioactive waste repository siting

    SciTech Connect (OSTI)

    Dreimanis, A. [Radiation Safety Centre, Riga LV (Latvia)

    2007-07-01T23:59:59.000Z

    This report considers the problem of multilevel consensus building for siting and construction of shared multinational/regional repositories for radioactive waste (RW) deep disposal. In the siting of a multinational repository there appears an essential innovative component of stakeholder consensus building, namely: to reach consent - political, social, economic, ecological - among international partners, in addition to solving the whole set of intra-national consensus building items. An entire partnering country is considered as a higher-level stakeholder - the national stakeholder, represented by the national government, being faced to simultaneous seeking an upward (international) and a downward (intra-national) consensus in a psychologically stressed environment, possibly being characterized by diverse political, economic and social interests. The following theses as a possible interdisciplinary approach towards building of shared understanding and stakeholder consensus on the international scale of RW disposal are forwarded and developed: a) building of international stakeholder consensus would be promoted by activating and diversifying on the international scale multilateral interactions between intra- and international stakeholders, including web-based networks of the RW disposal site investigations and decision-making, as well as networks for international cooperation among government authorities in nuclear safety, b) gradual progress in intergovernmental consensus and reaching multilateral agreements on shared deep repositories will be the result of democratic dialogue, via observing the whole set of various interests and common resolving of emerged controversies by using advanced synergetic approaches of conflict resolution, c) cross-cultural thinking and world perception, mental flexibility, creativity and knowledge are considered as basic prerogatives for gaining a higher level of mutual understanding and consensus for seeking further consensus, for advancing the preparedness to act together, and ultimately - for achieving desired shared goals. It is proposed that self-organized social learning will make it possible to promote adequate perception of risk and prevent, by diminishing uncertainties and unknown factors, social amplification of an imagined risk, as well as to increase the trust level and facilitate more adequate equity perception. The proposed approach to the multilevel stakeholder consensus building on international scale is extrapolated to the present-day activities of siting of such near-surface RW disposal facilities which supposedly could have non-negligible trans-boundary impact. A multilevel stakeholder interaction process is considered for the case of resolving of emerged problems in site selection for the planned near-surface RW repository in vicinity of the Lithuanian-Latvian border foreseen for disposal of short lived low- and intermediate level waste arising from the decommissioning of the Ignalina Nuclear Power Plant. (authors)

  11. MONITORED GEOLOGIC REPOSITORY LIFE CYCLE COST ESTIMATE ASSUMPTIONS DOCUMENT

    SciTech Connect (OSTI)

    R.E. Sweeney

    2001-02-08T23:59:59.000Z

    The purpose of this assumptions document is to provide general scope, strategy, technical basis, schedule and cost assumptions for the Monitored Geologic Repository (MGR) life cycle cost (LCC) estimate and schedule update incorporating information from the Viability Assessment (VA) , License Application Design Selection (LADS), 1999 Update to the Total System Life Cycle Cost (TSLCC) estimate and from other related and updated information. This document is intended to generally follow the assumptions outlined in the previous MGR cost estimates and as further prescribed by DOE guidance.

  12. Converting repository storage criteria into rules for materials conditioning

    SciTech Connect (OSTI)

    Becker, R.; Stegmaier, W. [Karlsruhe Nuclear Research Center (Germany)

    1993-12-31T23:59:59.000Z

    Productions of waste containers, waste forms and, consequently, waste packages are based on the regulations issued by the German Federal Ministry for the Environment and on the repository storage criteria of the Federal Office for Radiation Protection. Waste treatment facilities must install quality assurance systems and introduce detailed conditioning rules in order to verify these requirements. The conditioning rules incorporate descriptions of all conditioning steps as well as instructions to operators; they are laid down in conditioning manuals. By way of example, the procedure for evaporator concentrate cementation is outlined.

  13. Response to West Cumbria MRWS consultation: Why a deep nuclear waste repository should not be

    E-Print Network [OSTI]

    Response to West Cumbria MRWS consultation: Why a deep nuclear waste repository should not be sited geological nuclear waste repository. There a suspicion of predetermination because the only district that has. National and international guidance on how best to select potential sites for deep geological nuclear waste

  14. Common Metadata for Climate Modelling Digital Repositories CIM-enabled OASIS

    E-Print Network [OSTI]

    Common Metadata for Climate Modelling Digital Repositories CIM-enabled OASIS CERFACS Technical-1.2.1 Scientific Digital Repositories DOCUMENT Deliverable D5.7 Month 36 Deliverable Title CIM-enabled OASIS describes the adaption of the OASIS4 coupler so that it can use a CIM XML file for its configuration instead

  15. Mining Modern Repositories with Elasticsearch Oleksii Kononenko, Olga Baysal, Reid Holmes, and Michael W. Godfrey

    E-Print Network [OSTI]

    Godfrey, Michael W.

    Mining Modern Repositories with Elasticsearch Oleksii Kononenko, Olga Baysal, Reid Holmes and highlight its strengths and weaknesses for performing modern mining software repositories research. Categories and Subject Descriptors D.2.3 [Software Engineering]: Coding Tools and Tech- niques General Terms

  16. Towards Dynamic Data-Driven Management of the Ruby Gulch Waste Repository

    E-Print Network [OSTI]

    Parashar, Manish

    Towards Dynamic Data-Driven Management of the Ruby Gulch Waste Repository Manish Parashar1 Waste Repository. 1 Introduction The dynamic, data driven application systems (DDDAS) paradigm.versteeg@inl.gov Abstract. Previous work in the Instrumented Oil-Field DDDAS project has enabled a new generation of data

  17. Repository of NSF Funded Publications and Data Sets: "Back of Envelope" 15 year Cost Estimate

    E-Print Network [OSTI]

    Plale, Beth

    Repository of NSF Funded Publications and Data Sets: "Back of Envelope" 15 year Cost and variable costs of setting up and running a data repository (or database) to store and serve for rapid access, and tape for high reliability and cost efficient long-term storage. Data are ingested

  18. Benchmarking DAML+OIL Repositories Yuanbo Guo, Jeff Heflin, and Zhengxiang Pan

    E-Print Network [OSTI]

    Heflin, Jeff

    Benchmarking DAML+OIL Repositories Yuanbo Guo, Jeff Heflin, and Zhengxiang Pan Department, heflin, zhp2}@cse.lehigh.edu Abstract. We present a benchmark that facilitates the evaluation of DAML+OIL repositories in a standard and systematic way. This benchmark is intended to evaluate the performance of DAML+OIL

  19. Hydrogeologic effects of natural disruptive events on nuclear waste repositories

    SciTech Connect (OSTI)

    Davis, S.N.

    1980-06-01T23:59:59.000Z

    Some possible hydrogeologic effects of disruptive events that may affect repositories for nuclear wastte are described. A very large number of combinations of natural events can be imagined, but only those events which are judged to be most probable are covered. Waste-induced effects are not considered. The disruptive events discussed above are placed into four geologic settings. Although the geology is not specific to given repository sites that have been considered by other agencies, the geology has been generalized from actual field data and is, therefore, considered to be physically reasonable. The geologic settings considered are: (1) interior salt domes of the Gulf Coast, (2) bedded salt of southeastern New Mexico, (3) argillaceous rocks of southern Nevanda, and (4) granitic stocks of the Basin and Range Province. Log-normal distributions of permeabilities of rock units are given for each region. Chapters are devoted to: poresity and permeability of natural materials, regional flow patterns, disruptive events (faulting, dissolution of rock forming minerals, fracturing from various causes, rapid changes of hydraulic regimen); possible hydrologic effects of disruptive events; and hydraulic fracturing.

  20. Repository disposal requirements for commercial transuranic wastes (generated without reprocessing)

    SciTech Connect (OSTI)

    Daling, P.M.; Ludwick, J.D.; Mellinger, G.B.; McKee, R.W.

    1986-06-01T23:59:59.000Z

    This report forms a preliminary planning basis for disposal of commercial transuranic (TRU) wastes in a geologic repository. Because of the unlikely prospects for commercial spent nuclear fuel reprocessing in the near-term, this report focuses on TRU wastes generated in a once-through nuclear fuel cycle. The four main objectives of this study were to: develop estimates of the current inventories, projected generation rates, and characteristics of commercial TRU wastes; develop proposed acceptance requirements for TRU wastes forms and waste canisters that ensure a safe and effective disposal system; develop certification procedures and processing requirements that ensure that TRU wastes delivered to a repository for disposal meet all applicable waste acceptance requirements; and identify alternative conceptual strategies for treatment and certification of commercial TRU first objective was accomplished through a survey of commercial producers of TRU wastes. The TRU waste acceptance and certification requirements that were developed were based on regulatory requirements, information in the literature, and from similar requirements already established for disposal of defense TRU wastes in the Waste Isolation Pilot Plant (WIPP) which were adapted, where necessary, to disposal of commercial TRU wastes. The results of the TRU waste-producer survey indicated that there were a relatively large number of producers of small quantities of TRU wastes.

  1. Immersion studies on candidate container alloys for the Tuff Repository

    SciTech Connect (OSTI)

    Beavers, J.A.; Durr, C.L. [Cortest Columbus Technologies, OH (USA)

    1991-05-01T23:59:59.000Z

    Cortest Columbus Technologies (CC Technologies) is investigating the long-term performance of container materials used for high-level radioactive waste packages. This information is being developed for the Nuclear Regulatory Commission to aid in their assessment of the Department of Energy`s application to construct a geologic repository for disposal of high-level radioactive waste. This report summarizes the results of exposure studies performed on two copper-base and two Fe-Cr-Ni alloys in simulated Tuff Repository conditions. Testing was performed at 90{degrees}C in three environments; simulated J-13 well water, and two environments that simulated the chemical effects resulting from boiling and irradiation of the groundwater. Creviced specimens and U-bends were exposed to liquid, to vapor above the condensed phase, and to alternate immersion. A rod specimen was used to monitor corrosion at the vapor-liquid interface. The specimens were evaluated by electrochemical, gravimetric, and metallographic techniques following approximately 2000 hours of exposure. Results of the exposure tests indicated that all four alloys exhibited acceptable general corrosion rates in simulated J-13 well water. These rates decreased with time. Incipient pitting was observed under deposits on Alloy 825 and pitting was observed on both Alloy CDA 102 and Alloy CDA 715 in the simulated J-13 well water. No SCC was observed in U-bend specimens of any of the alloys in simulated J-13 well water. 33 refs., 48 figs., 23 tabs.

  2. Natural vegetation at the proposed Reference Repository Location in southeastern Washington

    SciTech Connect (OSTI)

    Rickard, W.H.

    1988-02-01T23:59:59.000Z

    The dominant shrubs were sagebrush and spiny hopsage; the herbs were dominated by cheatgrass and Sandberg bluegrass. Spiny hopsage appeared to be vulnerable to burning and also to damage by off-road vehicular traffic. It appears to have little or no ability to reproduce through seedlings; once the existing plants are killed they are not likely to be replaced, even if seed-producing plants are nearby. The only pure stand of spiny hopsage known to exist on the Hanford Site is on and near study plot 2H. Sagebrush, like spiny hopsage, is killed by burning and by heavy vehicles. Sagebrush is capable of reproducing via seeds, indicating that it is an inherently aggressive species with a capacity to reestablish itself if parent plants are in the vicinity to act as seed sources. Alien, annual plants, especially cheatgrass, were a major contributor to the herbaceous canopy cover in plots 3S, 4S, and 5S. However, native perennial grasses, especially Sandberg bluegrass, were a major contributor to the canopy cover in plots 1S and 2H. These differences are probably caused by differences in soil properties (e.g., water retention capacity), rather than to historical disturbances such as livestock grazing or wildfire. Specimens of Sandwort, Arenaria franklinii, growing near the Reference Repository Location were collected for examination by taxonomists to determine if the specimens are of the variety A. f. thompsonii, a taxon currently listed as threatened in the state of Washington. 16 refs., 7 figs., 3 tabs.

  3. Investigations on Repository Near-Field Thermal Modeling - Repository Science/Thermal Load Management & Design Concepts (M41UF033302)

    SciTech Connect (OSTI)

    Sutton, M; Blink, J A; Fratoni, M; Greenberg, H R; Ross, A D

    2011-07-15T23:59:59.000Z

    The various layers of material from the waste package (such as components of the engineered barrier system and the host rock surface) to a given distance within the rock wall at a given distance can be described as concentric circles with varying thermal properties (see Figure 5.1-1). The selected model approach examines the contributions of the waste package, axial waste package neighbors and lateral neighboring emplacement drifts (see Section 5.2.1 and Appendix H, Section 2). In clay and deep borehole media, the peak temperature is driven by the central waste package whereas, in granite and salt, the contribution to the temperature rise by adjacent (lateral) waste packages in drift or emplacement borehole lines is dominant at the time of the peak temperature. Mathematical models generated using Mathcad software provide insight into the effects of changing waste package spacing for six waste forms, namely UOX, MOX, co-extraction, new extraction, E-Chem ceramic and E-Chem metal in four different geologic media (granite, clay, salt and deep borehole). Each scenario includes thermal conductivity and diffusivity for each layer between the waste package and the host rock, dimensions of representative repository designs (such as waste package spacing, drift or emplacement borehole spacing, waste package dimensions and layer thickness), and decay heat curves generated from knowledge of the contents of a given waste form after 10, 50, 100 and 200 years of surface storage. Key results generated for each scenario include rock temperature at a given time calculated at a given radius from the central waste package (Section 5.2.1 and Appendix H, Section 3), the corresponding temperature at the interface of the waste package and EBS material, and at each EBS layer in between (Section 5.2.2 and Appendix H, Section 4). This information is vital to understand the implications of repository design (waste package capacity, surface storage time, waste package spacing, and emplacement drift or borehole spacing) by comparing the peak temperature to the thermal limits of the concentric layers surrounding the waste package; specifically 100 C for the bentonite buffer in granite and clay repositories, 100 C for rock wall in a clay repository and 200 C at the rock wall for a salt repository. These thermal limits are both preliminary and approximate, and serve as a means to evaluate design options rather than determining compliance for licensing situations. The thermal behavior of a salt repository is more difficult to model because it is not a concentric geometry and because the crushed salt backfill initially has a much higher thermal resistance than intact salt. Three models were investigated, namely a waste package in complete contact with crushed salt, secondly a waste package in contact with intact salt, and thirdly a waste package in contact with 75% intact and 25% crushed salt. The latter model best depicts emplacement of a waste package in the corner of an intact salt alcove and subsequently covered with crushed salt backfill to the angle of repose. The most conservative model (crushed salt) had temperatures much higher than the other models and although bounding, is too conservative to use. The most realistic model (75/25) had only a small temperature difference from the simplest (non-conservative, intact salt) model, and is the one chosen in this report (see Section 5.2.3). A trade-study investigating three key variables (surface storage time, waste package capacity and waste package spacing) is important to understand and design a repository. Waste package heat can be reduced by storing for longer periods prior to emplacement, or by reducing the number of assemblies or canisters within that waste package. Waste package spacing can be altered to optimize the thermal load without exceeding the thermal limits of the host rock or EBS components. By examining each of these variables, repository footprint (and therefore cost) can be optimized. For this report, the layout was fixed for each geologic medium based on prior published designs in

  4. THERMAL CONDUCTIVITY OF NON-REPOSITORY LITHOSTRATIGRAPHIC LAYERS

    SciTech Connect (OSTI)

    R. JONES

    2004-10-22T23:59:59.000Z

    This model report addresses activities described in ''Technical Work Plan for: Near-Field Environment and Transport Thermal Properties and Analysis Reports Integration'' (BSC 2004 [DIRS 171708]). The model develops values for thermal conductivity, and its uncertainty, for the nonrepository layers of Yucca Mountain; in addition, the model provides estimates for matrix porosity and dry bulk density for the nonrepository layers. The studied lithostratigraphic units, as identified in the ''Geologic Framework Model'' (GFM 2000) (BSC 2004 [DIRS 170029]), are the Timber Mountain Group, the Tiva Canyon Tuff, the Yucca Mountain Tuff, the Pah Canyon Tuff, the Topopah Spring Tuff (excluding the repository layers), the Calico Hills Formation, the Prow Pass Tuff, the Bullfrog Tuff, and the Tram Tuff. The deepest model units of the GFM (Tund and Paleozoic) are excluded from this study because no data suitable for model input are available. The parameter estimates developed in this report are used as input to various models and calculations that simulate heat transport through the rock mass. Specifically, analysis model reports that use product output from this report are: (1) Drift-scale coupled processes (DST and TH seepage) models; (2) Drift degradation analysis; (3) Multiscale thermohydrologic model; and (4) Ventilation model and analysis report. In keeping with the methodology of the thermal conductivity model for the repository layers in ''Thermal Conductivity of the Potential Repository Horizon'' (BSC 2004 [DIRS 169854]), the Hsu et al. (1995 [DIRS 158073]) three-dimensional (3-D) cubic model (referred to herein as ''the Hsu model'') was used to represent the matrix thermal conductivity as a function of the four parameters (matrix porosity, thermal conductivity of the saturating fluid, thermal conductivity of the solid, and geometric connectivity of the solid). The Hsu model requires input data from each test specimen to meet three specific conditions: (1) Known value for matrix porosity; (2) Known values for wet and dry thermal conductivity; and (3) The location of the measured specimen in relation to the model stratigraphic unit. The only matrix thermal conductivity values developed are limited to fully saturated and dry conditions. The model does not include the effects of convection and thermal radiation in voids. The model does not include temperature dependence of thermal conductivity, porosity, or bulk density.

  5. Mainstreaming Preservation through Slicing and Dicing of Digital Repositories: Investigating Alternative Service and Resource Options for ContextMiner Using Data Grid Technology

    E-Print Network [OSTI]

    Lee, Christopher; Marciano, Richard; Hou, Chien-Yi; Shah, Chirag

    2009-01-01T23:59:59.000Z

    efficiencies of resource use, (2) management of dependencies across entities, and (3) the repository business model

  6. Geotechnical support and topical studies for nuclear waste geologic repositories

    SciTech Connect (OSTI)

    Not Available

    1989-01-01T23:59:59.000Z

    The present report lists the technical reviews and comments made during the fiscal year 1988 and summarizes the technical progress of the topical studies. In the area of technical assistance, there were numerous activities detailed in the next section. These included 24 geotechnical support activities, including reviews of 6 Study Plans (SP) and participation in 6 SP Review Workshops, review of one whole document Site Characterization Plan (SCP) and participation in the Assembled Document SCP Review Workshops by 6 LBL reviewers; the hosting of a DOE program review, the rewriting of the project statement of work, 2 trips to technical and planning meetings; preparation of proposed work statements for two new topics for DOE, and 5 instances of technical assistance to DOE. These activities are described in a Table in the following section entitled Geoscience Technical Support for Nuclear Waste Geologic Repositories.''

  7. DOE Geothermal Data Repository - Tethering Data to Information: Preprint

    SciTech Connect (OSTI)

    Weers, J.; Anderson, A.

    2014-02-01T23:59:59.000Z

    Data are not inherently information. Without context, data are just numbers, figures, names, or points on a line. By assigning context to data, we can validate ideas, form opinions, and generate knowledge. This is an important distinction to information scientists, as we recognize that the context in which we keep our data plays a big part in generating its value. The mechanisms used to assign this context often include their own data, supplemental to the data being described and defining semantic relationships, commonly referred to as metadata. This paper provides the status of the DOE Geothermal Data Repository (DOE GDR), including recent efforts to tether data submissions to information, discusses the important distinction between data and information, outlines a path to generate useful knowledge from raw data, and details the steps taken in order to become a node on the National Geothermal Data System (NGDS).

  8. Generic repository design concepts and thermal analysis (FY11).

    SciTech Connect (OSTI)

    Howard, Robert (Oak Ridge National Laboratory, Oak Ridge, TN); Dupont, Mark (Savannah River Nuclear Solutions, Aiken, SC); Blink, James A. (Lawrence Livermore National Laboratory, Livermore, CA); Fratoni, Massimiliano (Lawrence Livermore National Laboratory, Livermore, CA); Greenberg, Harris (Lawrence Livermore National Laboratory, Livermore, CA); Carter, Joe (Savannah River Nuclear Solutions, Aiken, SC); Hardin, Ernest L.; Sutton, Mark A. (Lawrence Livermore National Laboratory, Livermore, CA)

    2011-08-01T23:59:59.000Z

    Reference concepts for geologic disposal of used nuclear fuel and high-level radioactive waste in the U.S. are developed, including geologic settings and engineered barriers. Repository thermal analysis is demonstrated for a range of waste types from projected future, advanced nuclear fuel cycles. The results show significant differences among geologic media considered (clay/shale, crystalline rock, salt), and also that waste package size and waste loading must be limited to meet targeted maximum temperature values. In this study, the UFD R&D Campaign has developed a set of reference geologic disposal concepts for a range of waste types that could potentially be generated in advanced nuclear FCs. A disposal concept consists of three components: waste inventory, geologic setting, and concept of operations. Mature repository concepts have been developed in other countries for disposal of spent LWR fuel and HLW from reprocessing UNF, and these serve as starting points for developing this set. Additional design details and EBS concepts will be considered as the reference disposal concepts evolve. The waste inventory considered in this study includes: (1) direct disposal of SNF from the LWR fleet, including Gen III+ advanced LWRs being developed through the Nuclear Power 2010 Program, operating in a once-through cycle; (2) waste generated from reprocessing of LWR UOX UNF to recover U and Pu, and subsequent direct disposal of used Pu-MOX fuel (also used in LWRs) in a modified-open cycle; and (3) waste generated by continuous recycling of metal fuel from fast reactors operating in a TRU burner configuration, with additional TRU material input supplied from reprocessing of LWR UOX fuel. The geologic setting provides the natural barriers, and establishes the boundary conditions for performance of engineered barriers. The composition and physical properties of the host medium dictate design and construction approaches, and determine hydrologic and thermal responses of the disposal system. Clay/shale, salt, and crystalline rock media are selected as the basis for reference mined geologic disposal concepts in this study, consistent with advanced international repository programs, and previous investigations in the U.S. The U.S. pursued deep geologic disposal programs in crystalline rock, shale, salt, and volcanic rock in the years leading up to the Nuclear Waste Policy Act, or NWPA (Rechard et al. 2011). The 1987 NWPA amendment act focused the U.S. program on unsaturated, volcanic rock at the Yucca Mountain site, culminating in the 2008 license application. Additional work on unsaturated, crystalline rock settings (e.g., volcanic tuff) is not required to support this generic study. Reference disposal concepts are selected for the media listed above and for deep borehole disposal, drawing from recent work in the U.S. and internationally. The main features of the repository concepts are discussed in Section 4.5 and summarized in Table ES-1. Temperature histories at the waste package surface and a specified distance into the host rock are calculated for combinations of waste types and reference disposal concepts, specifying waste package emplacement modes. Target maximum waste package surface temperatures are identified, enabling a sensitivity study to inform the tradeoff between the quantity of waste per disposal package, and decay storage duration, with respect to peak temperature at the waste package surface. For surface storage duration on the order of 100 years or less, waste package sizes for direct disposal of SNF are effectively limited to 4-PWR configurations (or equivalent size and output). Thermal results are summarized, along with recommendations for follow-on work including adding additional reference concepts, verification and uncertainty analysis for thermal calculations, developing descriptions of surface facilities and other system details, and cost estimation to support system-level evaluations.

  9. The Construction of the Konrad Repository - Status and Perspective - 13034

    SciTech Connect (OSTI)

    Kunze, V. [Bundesamt fuer Strahlenschutz - BfS, Postfach 10 01 49, 38201 Salzgitter (Germany)] [Bundesamt fuer Strahlenschutz - BfS, Postfach 10 01 49, 38201 Salzgitter (Germany)

    2013-07-01T23:59:59.000Z

    Due to the Atomic Energy Act of Germany the Federation is responsible for the construction and operation of installations for the safekeeping and disposal of radioactive waste. The Federal Office for Radiation Protection (Bundesamt fuer Strahlenschutz - BfS) is assigned with this duty. In 1982 the abandoned iron ore mine Konrad near Salzgitter (Federal State of Lower Saxony) was proposed as a repository for low and intermediate level radioactive waste with negligible heat generation. After 20 years of plan approval procedure the license was granted by the Ministry for Environment of Lower Saxony in May 2002. This decision was finally confirmed by the Federal Administrative Court in March 2007. The construction has started, but former assumptions about the beginning of waste emplacement tuned out to be too optimistic. In the course of the preparatory work and the implementation planning it turned out that many changes need to be done. As a matter of fact most of the documents and planning originate from the 1990's and need to be revised because from that time on until now no adaptation was appropriate. The necessity to apply the state-of-the-art technology and other legal implications give rise to further changes and new licensing procedures, especially building licenses. Furthermore, the license from 2002 also includes a lot of collateral clauses that need to be fulfilled before radioactive waste can be emplaced. With this in mind, the time frame for the construction of the Konrad repository was revised in 2010. As a result, the completion of the erection before 2019 does not seem to be realistic. (authors)

  10. Collective Phase Sensitivity

    E-Print Network [OSTI]

    Yoji Kawamura; Hiroya Nakao; Kensuke Arai; Hiroshi Kori; Yoshiki Kuramoto

    2008-07-08T23:59:59.000Z

    The collective phase response to a macroscopic external perturbation of a population of interacting nonlinear elements exhibiting collective oscillations is formulated for the case of globally-coupled oscillators. The macroscopic phase sensitivity is derived from the microscopic phase sensitivity of the constituent oscillators by a two-step phase reduction. We apply this result to quantify the stability of the macroscopic common-noise induced synchronization of two uncoupled populations of oscillators undergoing coherent collective oscillations.

  11. Utility Data Collection Service

    Broader source: Energy.gov [DOE]

    Presentation covers the utility data collection service and is given at the FUPWG 2006 Spring meeting, held on May 3-4, 2006 in Atlanta, Georgia.

  12. Proceedings of 3rd US/German Workshop on Salt Repository Research...

    Office of Environmental Management (EM)

    New Mexico on October 8-11, 2012. Approximately 60 salt research scientists from Germany and the United States met to discuss repository science state of the art. Workshop...

  13. REGIONAL THERMOHYDROLOGICAL EFFECTS OF AN UNDERGROUND REPOSITORY FOR NUCLEAR WASTES IN HARD ROCK

    E-Print Network [OSTI]

    Wang, J.S.Y.

    2014-01-01T23:59:59.000Z

    underground repository for nuclear waste in hard rock, LBL-and Vath, J.E. , Nuclear waste projections and source-termthe Scientific Basis for Nuclear Waste Management, Material

  14. Safety Assessment for VLLW Disposal at the National Radioactive Waste Repository Mochovce in Slovakia - 13508

    SciTech Connect (OSTI)

    Biurrun, E.; Haverkamp, B. [DBE TECHNOLOGY GmbH, Eschenstr. 55, D-31224 Peine (Germany)] [DBE TECHNOLOGY GmbH, Eschenstr. 55, D-31224 Peine (Germany); Lazaro, A.; Miralles, A. [Westinghouse Electric Spain SAR, Padilla 17, E-28006 Madrid (Spain)] [Westinghouse Electric Spain SAR, Padilla 17, E-28006 Madrid (Spain)

    2013-07-01T23:59:59.000Z

    Recent developments in the Slovak Republic have prompted the need to introduce the new category of very low level waste (VLLW) in the operation of the country's repository for low and intermediate level radioactive waste (LILW). By doing this, significant savings are expected to be achieved while disposing the waste resulting from early decommissioning of older, Soviet type reactors. To study the feasibility and the likely impact of such introduction, a project was launched and assigned in international competition to a German-Spanish consortium. The study confirmed by means of a safety assessment the feasibility of this waste category in the specific context of the Slovakian repository. Moreover, the advantages that such new waste category would render were stressed and the best option for enlargement of the repository, the construction of a module for LILW disposal within the limits of the existing repository, was identified. (authors)

  15. Thermo-Hydro-Mechanical Coupled Analysis in Low Permeability Media Under Nuclear Repository Conditions 

    E-Print Network [OSTI]

    Aponte Rivera, Fernando Luis

    2013-12-06T23:59:59.000Z

    The design of underground repositories to storage high level radioactive waste is based on the multi barrier concept that consists of placing natural and artificial barriers around the radioactive material for isolation. The artificial barrier...

  16. Design of a high-level waste repository system for the United States

    E-Print Network [OSTI]

    Driscoll, Michael J.

    1988-01-01T23:59:59.000Z

    This report presents a conceptual design for a High Level Waste disposal system for fuel discharged by U.S. commercial power reactors, using the Yucca Mountain repository site recently designated by federal legislation. ...

  17. Risk-informing decisions about high-level nuclear waste repositories

    E-Print Network [OSTI]

    Ghosh, Suchandra Tina, 1973-

    2004-01-01T23:59:59.000Z

    Performance assessments (PAs) are important sources of information for societal decisions in high-level radioactive waste (HLW) management, particularly in evaluating safety cases for proposed HLW repository development. ...

  18. The Adoption of Advanced Fuel Cycle Technology Under a Single Repository Policy

    SciTech Connect (OSTI)

    Paul Wilson

    2009-11-02T23:59:59.000Z

    Develops the tools to investiage the hypothesis that the savings in repository space associated with the implementation of advanced nuclear fuel cycles can result in sufficient cost savings to offset the higher costs of those fuel cycles.

  19. Collaborative Collecting: A Literature Review

    E-Print Network [OSTI]

    Abreu, Amelia

    2013-01-01T23:59:59.000Z

    and aesthetics in the Menil Collection. University of Texasstored within the individual collections of the contributingconstitutes the selected collections is directly entered,

  20. University Faculty Awareness and Attitudes towards Open Access Publishing and the Institutional Repository: A Case Study

    E-Print Network [OSTI]

    Yang, Zheng Ye; Li, Yu

    2015-05-06T23:59:59.000Z

    mentioned by faculty, such as OA publishing and repository services, copyright, data management, a seminar on how to most effectively make their research available to others, and a workshop on tools for data deposit for OA. Some faculty expressed...Journal of Librarianship and Scholarly Communication Volume 3 | Issue 1 eP1210 University Faculty Awareness and Attitudes towards Open Access Publishing and the Institutional Repository: A Case Study Zheng Y. Yang, Yu Li © 2015 by the author...

  1. Debt collection project report

    SciTech Connect (OSTI)

    Not Available

    1980-05-01T23:59:59.000Z

    In October 1979 the Office of Management and Budget initiated a review of debt collection within the Federal Government. A DOE Debt Collection Project Team was established, and seven activites were selected for review. These were Albuquerque Operations Office; Bonneville Power Administration; Chicago Operations and Regional Office; Naval Petroleum Reserves, California; Oak Ridge Operations Office; Washington Financial Services Division; and Western Area Power Administration. The team visited each of these activities to collect data on the size, age, and types of receivables managed and procedures for billing, aging, and handling overdue accounts. Various deficiencies were found to exist at several of the DOE entities that are not consistent with good management practices in the performance of their debt collection functions. Also, the Debt Collection Project Team identified a wide variation in the procedures followed by DOE activities in the management of accounts receivable, and a wide variation in the effectiveness of the debt management functions. 1 figure, 17 tables. (RWR)

  2. Development of an object-oriented simulation code for repository performance assessment

    SciTech Connect (OSTI)

    Tsujimoto, Keiichi; Ahn, J.

    1999-07-01T23:59:59.000Z

    As understanding for mechanisms of radioactivity confinement by a deep geologic repository improves at the individual process level, it has become imperative to evaluate consequences of individual processes to the performance of the whole repository system. For this goal, the authors have developed a model for radionuclide transport in, and release from, the repository region by incorporating multiple-member decay chains and multiple waste canisters. A computer code has been developed with C++, an object-oriented language. By utilizing the feature that a geologic repository consists of thousands of objects of the same kind, such as the waste canister, the repository region is divided into multiple compartments and objects for simulation of radionuclide transport. Massive computational tasks are distributed over, and executed by, multiple networked workstations, with the help of parallel virtual machine (PVM) technology. Temporal change of the mass distribution of 28 radionuclides in the repository region for the time period of 100 million yr has been successfully obtained by the code.

  3. Adapting Dry Cask Storage for Aging at a Geologic Repository

    SciTech Connect (OSTI)

    C. Sanders; D. Kimball

    2005-08-02T23:59:59.000Z

    A Spent Nuclear Fuel (SNF) Aging System is a crucial part of operations at the proposed Yucca Mountain repository in the United States. Incoming commercial SNF that does not meet thermal limits for emplacement will be aged on outdoor pads. U.S. Department of Energy SNF will also be managed using the Aging System. Proposed site-specific designs for the Aging System are closely based upon designs for existing dry cask storage (DCS) systems. This paper evaluates the applicability of existing DCS systems for use in the SNF Aging System at Yucca Mountain. The most important difference between existing DCS facilities and the Yucca Mountain facility is the required capacity. Existing DCS facilities typically have less than 50 casks. The current design for the aging pad at Yucca Mountain calls for a capacity of over 2,000 casks (20,000 MTHM) [1]. This unprecedented number of casks poses some unique problems. The response of DCS systems to off-normal and accident conditions needs to be re-evaluated for multiple storage casks. Dose calculations become more complicated, since doses from multiple or very long arrays of casks can dramatically increase the total boundary dose. For occupational doses, the geometry of the cask arrays and the order of loading casks must be carefully considered in order to meet ALARA goals during cask retrieval. Due to the large area of the aging pad, skyshine must also be included when calculating public and worker doses. The expected length of aging will also necessitate some design adjustments. Under 10 CFR 72.236, DCS systems are initially certified for a period of 20 years [2]. Although the Yucca Mountain facility is not intended to be a storage facility under 10 CFR 72, the operational life of the SNF Aging System is 50 years [1]. Any cask system selected for use in aging will have to be qualified to this design lifetime. These considerations are examined, and a summary is provided of the adaptations that must be made in order to use DCS technologies successfully at a geologic repository.

  4. Repository site data report for unsaturated tuff, Yucca Mountain, Nevada

    SciTech Connect (OSTI)

    Tien, P.L.; Updegraff, C.D.; Siegel, M.D.; Wahi, K.K.; Guzowski, R.V.

    1985-11-01T23:59:59.000Z

    The US Department of Energy is currently considering the thick sequences of unsaturated, fractured tuff at Yucca Mountain, on the southwestern boundary of the Nevada Test Site, as a possible candidate host rock for a nuclear-waste repository. Yucca Mountain is in one of the most arid areas in the United States. The site is within the south-central part of the Great Basin section of the Basin and Range physiographic province and is located near a number of silicic calderas of Tertiary age. Although localized zones of seismic activity are common throughout the province, and faults are present at Yucca Mountain, the site itself is basically aseismic. No data are available on the composition of ground water in the unsaturated zone at Yucca Mountain. It has been suggested that the composition is bounded by the compositions of water from wells USW-H3, UE25p-1, J-13, and snow or rain. There are relatively few data available from Yucca Mountain on the moisture content and saturation, hydraulic conductivity, and characteristic curves of the unsaturated zone. The available literature on thermomechanical properties of tuff does not always distinguish between data from the saturated zone and data from the unsaturated zone. Geochemical, hydrologic, and thermomechanical data available on the unsaturated tuffs of Yucca Mountain are tabulated in this report. Where the data are very sparse, they have been supplemented by data from the saturated zone or from areas other than Yucca Mountain. 316 refs., 58 figs., 37 tabs.

  5. Water, Vapor, and Salt Dynamics in a Hot Repository

    SciTech Connect (OSTI)

    Bahrami, Davood; Danko, George [Department of Mining Engineering, University of Nevada, Reno, 1664 N. Virginia St., Reno, NV, 89557 (United States); Walton, John [Department of Civil Engineering, University of Texas at El Paso, 500 W. University, El Paso, TX, 79968 (United States)

    2007-07-01T23:59:59.000Z

    The purpose of this paper is to report the results of a new model study examining the high temperature nuclear waste disposal concept at Yucca Mountain using MULTIFLUX, an integrated in-drift- and mountain-scale thermal-hydrologic model. The results show that a large amount of vapor flow into the drift is expected during the period of above-boiling temperatures. This phenomenon makes the emplacement drift a water/moisture attractor during the above-boiling temperature operation. The evaporation of the percolation water into the drift gives rise to salt accumulation in the rock wall, especially in the crown of the drift for about 1500 years in the example. The deposited salts over the drift footprint, almost entirely present in the fractures, may enter the drift either by rock fall or by water drippage. During the high temperature operation mode, the barometric pressure variation creates fluctuating relative humidity in the emplacement drift with a time period of approximately 10 days. Potentially wet and dry conditions and condensation on salt-laden drift wall sections may adversely affect the storage environment. Salt accumulations during the above-boiling temperature operation must be sufficiently addressed to fully understand the waste package environment during the thermal period. Until the questions are resolved, a below-boiling repository design is favored where the Alloy-22 will be less susceptible to localized corrosion. (authors)

  6. Mechanical interaction between rock, buffer and canister in repositories

    SciTech Connect (OSTI)

    Borgesson, L. [Clay Technology AB, Lund (Sweden)

    1993-12-31T23:59:59.000Z

    The bentonite clay buffer, which is used in the repository concept of Sweden as well as many other countries, has an important role for mechanical protection of the canister. Of special interest is the effect of a rock shear, i.e. displacement of the rock along a fracture intersecting the deposition hole, on the canister. The article shows the results of some FEM calculations of a rock shear when the new composite copper/steel canister, is used. The effect of the swelling pressure from the bentonite before shear and the effect of a symmetric as well as an asymmetric rock shear will be shown. The calculations have been preceded by extensive laboratory tests and verification calculations by which material models for the buffer and proper calculation techniques have been developed. The material model for the clay is an elastic plastic model in which porous elasticity, based on the effective stress theory, is combined with Drucker-Prager plasticity. The results indicate that the bentonite clay acts as a very good mechanical buffer against such rock displacements. Although plastic yielding may occur, mainly in the copper, the plastic strain is not more than a few percent just after the shear.

  7. UESC Data Collection Update

    Broader source: Energy.gov [DOE]

    Presentation—given at the April 2012 Federal Utility Partnership Working Group (FUPWG) meeting—provides an overview of utility energy service contract (UESC) data collection, including what is needed, how to submit data, and why it is important.

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    Boyer, Edmond

    and industrial appli- cations such as combustion devices [1], oil cracking [2], fluidized beds in coal stations simulations at the reactor scale for fluidized beds or combustion chambers require the implementation of macro beds Collision and lubrication models The direct numerical simulation of particle flows is investigated

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    in fixed beds of solid fuels. In light of a dimensional analysis, Debenest et al. [7] identified a set channel. (2013) In: Eighth Mediterranean Combustion Symposium - , 08 September 2013 - 13 September 2013 in "Eighth Mediterranean Combustion Symposium -, Izmir : Turkey (2013)" #12;DIRECT NUMERICAL SIMULATIONS

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    Mailhes, Corinne

    their niche (3). However, com- pared to lithium-ion batteries, very little work has been done to integrate ECs to bulk-sized batteries. Currently, advanced rechargeable mi- crobatteries that use thin-film technologies with using lithium (2). Even three-dimensional (3D) batteries (1), which are expected to overcome power

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    Packing fixed bed reactors with cylinders: influence of particle length distribution. (2012) In: 20th August 2012, Prague, Czech Republic Packing fixed bed reactors with cylinders: Influence of particle packing structure of fixed bed reactors made of cylindrical pellets packed in cylindrical tubes. Packing

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    , harvesting period and extraction process. Industrial lignins are mainly used for energy production during the polymer pro- cessing. The migration of low molecular weight com- pounds in an ethanol/water solution simulating fatty foodstuff was performed and the antioxidant activity of the extract was analysed

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    , is considered to be a promising raw material for the production of bioplastics. However, it needs intense

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    Cylinder Stokes-type force Hydrodynamic interactions Non-Newtonian fluids Stokes' paradox a b s t r a c t The present work deals with the numerical calculation of the Stokes-type drag undergone by a cylindrical, where the Stokes' paradox takes place. For unbounded medium, avoiding these traps, we show that the drag

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    of the flotation cell.The froth layer is skimmed and dewatered. The dewatered contaminant sludge is disposed processes [4,5]. Oil-based inks such as offset inks have hydrophobic properties,so they generally respond

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    Mailhes, Corinne

    and Tenailleau, Christophe and Alphonse, Pierre and Chabal, Y.J. (2010) Multilayered Al/CuO thermite formation-oatao@inp-toulouse.fr. #12;Multilayered Al/CuO thermite formation by reactive magnetron sputtering: Nano versus micro M, 800 W. Campbell Rd., RL 10 Richardson, Texas 75080, USA Multilayered Al/CuO thermite was deposited

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    Boyer, Edmond

    to this article : URL : http://dx.doi.org/10.1016/j.carbon.2006.10.011 To cite this version : Salvador, Malcolm L. H. and Sim, Robert B. ( 2007) Binding of pulmonary surfactant proteins to carbon nanotubes; potential for damage to lung immune defense mechanisms. Carbon, vol. 45 (n° 3). pp. 607-617. ISSN 0008

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    Mailhes, Corinne

    is anthropogenic CO2 sequestration through the biological carbon pump. Indeed diatoms, silica-shelled unicellular of the carbon cycle in natural waters (oceans and rivers). The source of silicate in aquatic media is mainly due

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    Mailhes, Corinne

    sources ­ associated to particles (mainly via carbonates and Fe/Mn oxides), were pre- dominantly to elevated health risks (Oliver, 1997). In the meantime, anthropogenic metals sequestrated in soils during

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    Paris-Sud XI, Université de

    at 90, 100, 120, 140, 150 and 160 C in air- ventiled ovens by Fourier transform infrared after a considerably shorter induction period but reaches a lower maximal rate than in additive free PE

  1. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

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    Boyer, Edmond

    rue Notre-Dame Ouest, Montreal QC, H3C 1K3, Canada 3 AgroParisTech, UMR 1145 Ingenierie Procede half time. The evolution of activation energies determined with Kissinger's equation suggests renewable resources allowing reducing dependency on fossil resources and being in most cases biodegradable

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    Boyer, Edmond

    and physical properties. - Solar Energy Materials & Solar Cells - Vol. 116, p.34-42. - 2013 Any correspondence,version1-3Jul2014 Author manuscript, published in "Solar Energy Materials & Solar Cells 116 (2013) 34 popular transparent conducting electrode used in thin-film photovoltaics, flat-panel display devices, due

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    columns used in distillation or in absorption processes, it is of high importance to be able to predict/or by achieving the most adequate design ofpacked columns. Such an optimum design is linked to the choice, Véronique and Raynal, Ludovic. Liquid dispersion in packed columns: experiments and numerical modelling

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    Boyer, Edmond

    of hydrostatic stress is presented. A flywheel was modified to carry out compression tests at high strain rates-dimensional stress states. A new experimental apparatus for the study of the foam behaviour under a state, and a hydrostatic chamber designed to obtain the variation of stress with volumetric strain, as a function

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    Paris-Sud XI, Université de

    on the initial collapse stress and the hardening modulus in the post-yield plateau region. A flywheel apparatus. The compressive stress­strain behaviour of these foams has been investigated over a wide range of engineering for the everyday use of an automotive crash-box, the foam used in this structure is stressed under quasi

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    Paris-Sud XI, Université de

    ) simulations and experimental measurements. The analysis is applied to a vertical, cold-wall reactor, where on the ability to determine optimal operating conditions in a well-designed reactor configuration. Transport on computational fluid dynamics (CFD) have been used successfully in recent years to design new MOCVD reactors

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    Boyer, Edmond

    were carried out under dry friction using a ring-on-ring tribometer at ambient temperature (Figure 1, Friction, Thermal behavior During friction, the materials in contact undergo a thermal field that can accelerate their deterioration or promote the creation of protective layers [1]. Silicon carbide/carbon dry

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    Mailhes, Corinne

    Evaluation of the real contact area in three-body dry friction by micro-thermal analysis. (2010) Tribology;Evaluation of the real contact area in three-body dry friction by micro- thermal analysis Philippe Stempfléa the real AFM maps. Keywords: Scanning thermal microscopy; Friction; Third body; Greenwood

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    Paris-Sud XI, Université de

    -containing aluminum alloys such as 2024 alloy are often used in aerospace applications; thus, there is sig- nificant interest in their corrosion behaviour in aerated solutions. These materials are high-strength alloys mechanical properties. In such alloys, copper is present in the matrix as well as in various fine

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    Paris-Sud XI, Université de

    Introduction Aerospace industry uses more and more widely titanium alloys, mostly Ti6Al4V for its high, Nantes, France Abstract : In aerospace applications, drilling is one of the most common operations and one batch of Ti6Al4V alloy. Keywords: Drilling, Local forces, Ti6Al4V, Edge-Material pair 1

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    and trends concerning cellulosic materials processed in scCO2 such as cellulose drying to obtain aerogels for cellulose esters and ether synthesis, and fibres and film fabrication. These materials are used in coatings

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    Paris-Sud XI, Université de

    and mechanical conditions generated in machining. Sulfur additives are well-known for their strong extreme conditions generated on the cutting tools. In some cases of severe machining, the fluid contributes to lubrication in a physicochemical way thanks to the additives it contains. This study aims to analyze

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    Paris-Sud XI, Université de

    , - study of Friction Stir Welding. This work outlines how discrete element model can be a useful tool

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    .girot@bordeaux.ensam.fr Résumé Le procédé FSW ou Friction Stir Welding qui peut se traduire en français par friction malaxage - Caractérisation d'un alliage 2024-T3 assemblé par friction-malaxage - 2010 Any correspondence concerning FRICTION-MALAXAGE Nejah Jemal(1), Jean-Eric Masse(1), Laurent Langlois (2), Serge Tcherniaeff (3), Franck

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    friction stir welds using X-Ray and neutron diffraction - 2009 Any correspondence concerning this service;RESIDUAL STRESS EVOLUTION ANALYSIS IN AZ31 FRICTION STIR WELDS USING X-RAY AND NEUTRON DIFFRACTION. Loreleï the efficiency of new joining techniques, as Friction Stir Welding is then required. During Friction Stir Welding

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    of wrought magnesium alloy friction stir welds - Materials Science and Engineering A - Vol. 551, p.288 changes and induced residual stresses on tensile properties of wrought magnesium alloy friction stir welds Provence, France Keywords: Friction stir welding Magnesium alloys Speckle interferometry Residual stress

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    CNRS 5503 ENSIACET INPT, 4 Allée Emile Monso, BP 84234, 31432 Toulouse Cedex 4, France Keywords related to the energy source involved in the utility production system (UPS), either fuel oil or natural contributes to energy consumption in process plants and consequently to the operating cost in a scenario

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    Mailhes, Corinne

    , 31432 Toulouse Cedex 4, France Keywords: Hydrodealkylation of toluene Multi-objective genetic algorithm production system (UPS), either fuel oil or natural gas, of the HDA process are carried out. In each case. 1. Introduction Utility production largely contributes to energy consumption in process plants

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    Boyer, Edmond

    improves the engine efficiency and decreases oil consumption. It was believed that there are close links performance [1-3]. It helps piston rings/cylinder liners assemblies to reduce friction, oil consumption, Rue Saint Dominique, BP 508, 51006 Châlons-en-Champagne, Cedex, France 2 RENAULT S.A.S., Direction de

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    Paris-Sud XI, Université de

    by honing technique, is an essential factor for a good engine performance (friction, oil consumption considerably influences functional performances (running-in, friction, oil consumption, wear...) of the ring Champagne, Cedex, France 2 Renault s.a.s, Direction de l'Ingénierie Mécanique, 67 rue des bons raisins

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    Paris-Sud XI, Université de

    aims at reducing metallic contact, also allows oil consumption [2] and greenhouse gas emissions Châlons-en-Champagne, France Supélec, Département Automatique, Plateau de Moulon, 3 rue Joliot-Curie, F 91192 Gif sur Yvette cedex, France * Corresponding author. Tel.: +33 326 699 176; fax: +33 326 699 197.E

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    inventories of 210Pb and artificial radionuclides. (2008) Atmospheric Environment, Vol. 42 (n° 7). pp. 1517;Aerosol deposition and origin in French mountains estimated with soil inventories of 210 Pb and artificial Abstract Radionuclide inventories were measured in soils from different French mountainous areas: Chai

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    Paris-Sud XI, Université de

    in the form of recommendations for the design step. This proposal will be illustrated by means of a wind turbine design. Keywords Ecodesign, design for X, life cycle assessment, end-of-life, wind turbine 1 assessment (LCA), even if some materials, constituents, processes or life stages are less known than others

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    aluminum alloys in some structural and mechanical parts. Indeed, magnesium alloy densities are 36% lower than aluminum alloys, leading to a high strength to weight ratio (180 kN m/kg, comparable with that achieved in aluminum alloys). Magnesium alloys are also attractive owing to their electromagnetic

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    to be confirmed. Keywords: A. Aluminium alloys; B. Polarization curves; C. Corrosion potential; C. Galvanic couple 1. Introduction Aluminium alloys are commonly used for heat exchangers in the automotive industry heat exchangers has been to replace mechanical assembly by brazing of aluminium alloys mainly

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    in nuclear reactor vessels [1]. Mean field approaches are often used in designing heterogeneous materials-ray diffraction (XRD) Dislocations Carbides Micromechanical Modeling a b s t r a c t In situ tensile tests were tests were complemented by macroscopic tensile and reversible tensile-compression tests to study

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    synthesized by thermal annealing of copper thin films deposited onto silicon substrate. The effects [2], anode electrodes for batteries [3], magnetic storage media [4], and high temperature) Synthesis of large- area and aligned copper oxide nanowires from copper thin film on silicon substrate

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    alloy is a promising material for the manufac- turing of helicopter turbine components submitted such as turbine blades and vanes from excessive oxidation. Al-containing coatings are mainly processed

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    Mailhes, Corinne

    part. In turbine application, these materials are submitted to a high temperature (up to around 1500 °C of the material is shown to contain a continuous oxide layer of MgAl2O4 at the periphery of metallic particles °C in flowing dry air). Introduction Abradable seal coatings are currently used in gas turbine

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    ) b. Laboratory for water and turbine machines, Univ. of Ljubljana, Askerceva 6, Ljubljana 1000 of a millimetric Venturi test section associated with a transportable hydraulic loop. Various configurations

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    Boyer, Edmond

    dimension of these devices, heat and mass transfer are remarkably intensified and the temperature within can is independent of UTP under the studied flow conditions. These results suggest that the amount of heat or mass,c , Joelle Aubin b,c,n a Institute of Chemical Process Fundamentals of the ASCR, v.v.i., Rozvojova 135, CZ

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    Boyer, Edmond

    paper by Mojtabi and Rees (2011 Int. J. Heat Mass Transfer 54 293­301) who considered a configuration plates, subjected to a constant heat flux. These plates have identical conductivity. Moreover numerous fundamental and industrial applications. Reviews of recent developments and publications

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    Mailhes, Corinne

    and Zenasni, Aziz and Caussat, Brigitte High quality graphene synthesized by atmospheric pressure CVD : http://dx.doi.org/10.1016/j.surfcoat.2013.06.050 #12;High quality graphene synthesized by atmospheric/CNRS/CEA LTM, 17 rue des Martyrs, 38054 Grenoble Cedex 9, France a b s t r a c t Keywords: Graphene CVD

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    Boyer, Edmond

    . Introduction The preparation of iron oxide thin films can lead to devices with attractive optical, magnetic, France Abstract Magnetic and semi-conducting nanocomposite iron oxide thin films have been prepared under. Keywords: Iron oxides; Magnetic coupling; Exchange bias; Sputtering; Nanocomposite; Magnetite; Wustite 1

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    Mailhes, Corinne

    lead to the same layers of spinel and monoxide, but pores at the metal/ FeyO interface cause loss of adhesion of the oxide film. 1. Introduction The Hall­Héroult process for primary aluminum production consists of the electrolysis of alumina using consumable carbon anodes, which leads to the emission

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    systems of gas turbine vanes is related to a multiobjective design problem. In this paper, it is addressed. This paper also proposes to enhance available knowledge in the literature of cooling systems of gas turbine operating costs, turbine designers must also increase their component lifetimes. However, high gas

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    this version : Eric DUCASSE - Modeling principles for time-domain simulations of wind instruments in playing Administrator : archiveouverte@ensam.eu #12;Ducasse, E. (2002). "Modeling principles for time-domain simulations). Page 1 / 5 MODELING PRINCIPLES FOR TIME-DOMAIN SIMULATIONS OF WIND INSTRUMENTS IN PLAYING SITUATIONS

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    Boyer, Edmond

    (batch approach) and (2) building predictive24 models that could be the basis of an online control to design or optimise processes, machines,47 tools and wood preparation.48 Cutting models have been first in the literature concerning wood cutting forces permit to build models or18 to simulate the main wood machining

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    Paris-Sud XI, Université de

    and shear stresses) for each strength class. Contact joints in timber structures are often loaded), (Smith and al., 1988), (Bleron, 2000), the load-deformation behaviour of contact joints is generally very. The first one is a test where a block of wood is loaded in uniform compression over the full surface

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    a greater than 1000-fold nutrient gradient. Dramatically slowed breakdown at both extremes of the gradient-system metabolism, and nutrient spiraling) for assessing ecosystem health. N utrient enrichment from organic inputs

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    as for transparent electronics; thin-film solar cells2 and flat panel displays3,4 are typical applica- tions of samples deposited at different pressures, which provides an insight into the defect surface properties. ZnO is an n-type semiconductor with a wide direct band gap energy of 3.37 eV at room

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    that a deep keyhole welding requires surface temperature over Tv. It is indicated also that, in normal gas this version : Koji HIRANO, Rémy FABBRO, Maryse MULLER - Experimental determination of temperature threshold;Experimental determination of temperature threshold for melt surface deformation during laser interaction

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    surface, m2 T temperature, K U voltage, V U0 welding speed, m.s-1 Vd droplet speed, m.s-1 Vw filler wire of hybrid Nd:Yag laser-MAG arc welding processes. - Optics & Laser Technology - Vol. 43, p.1155-1166 - 2011-MAG arc welding processes. E LE GUEN1 , R FABBRO1 , M CARIN2 , F COSTE1 and P LE MASSON2 E-mail: leguen

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    . Space­time temperature distributions in weld- ments are predicted from the beginning of welding element simulation of magnesium alloys laser beam welding - Journal of Materials Processing Technology.jmatprotec.2010.02.023 #12;Finite element simulation of magnesium alloys laser beam welding Asma Belhadja

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    BALMES - On the influence of geometry updating on modal correlation of brake components. - 2012 Any On the influence of geometry updating on modal correlation of brake components. B. França de Paulaa , G. Rejdycha degradation of the test/analysis correlation. An application to an industrial brake part is eventually

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    G-Si, the development of new processes allowing the production of cheaper SoG-Si is a main issue for the solar energy 99.99%. 1. Introduction Photovoltaic technology is a very important renewable source of electrical industry [3]. In the 1980's, silicon electrodeposition in molten salts has been considered as an attractive

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    Mailhes, Corinne

    the production of cheaper SoG-Si is a main issue for the solar energy industry [3]. In the 1980's, silicon technology is a very important renewable source of electrical energy production with the highest annual electrodeposition in molten salts has been considered as an attractive option for SoG-Si production [4]. However

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    to greater thickness. Introduction For about 10 years microbial fuel cells (MFCs) have been proposed@ensiacet.fr; Tel: +33 5 34 32 36 73 Broader context For about 10 years microbial fuel cells (MFCs) have been technologies, such as microbial electrolysis cell, microbial desalination cell, microbial electro- synthesis

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    : Bioanode Microbial anode Pulp mill effluent Microbial fuel cell a b s t r a c t Microbial bioanodes were the emergent technology of microbial fuel cells (MFCs) to the treatment of effluents. MFCs would offer and theoretical characterization of microbial bioanodes formed in pulp and paper mill effluent

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    Toulouse (IMFT), France 3 Ineos Technologies, Lavéra, France 4 Ineos Technologies, Naperville, USA Abstract. This study is a collaboration between the Institut de Mécanique des Fluides de Toulouse (IMFT), and Ineos

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    Chimique, Toulouse, France 2 Ineos ChlorVinyls, Mazingarbe, France On-line Monitoring of Vinyl Chloride

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    , Université de Toulouse, Laboratoire de Génie Chimique, Toulouse, France 2 Ineos ChlorVinyls, Mazingarbe

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    ) - Les turbines à axe vertical (VAWTs) . Fig. 1 VAWT Chinoise (F.H. KING [2004]) L'origine connue des

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    Boyer, Edmond

    for capacitive storage devices. We demonstrate the efficacy of these electrodes in a hybrid electrochemical cell pervasive, the use of electrochemical capaci- tors (ECs) as electrical energy storage devices is finding of Nanostructured Nb2O5 Electrodes. (2014) Journal of The Electrochemical Society (JES), vol. 161 (n° 5). pp. A718-A

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    spherical projectile. The targets are simply supported at the rear of the structure. Two potential choices, a strong coupling has been found between the front skin and the core. The impact tests indicate impact tests. These impacts are characterized by medium-velocities and high energies: 120 m/s and 1 k

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    Paris-Sud XI, Université de

    . Introduction The present management of spent nuclear fuel is based on di- rect disposal or single recycling for nuclear fuel treatment using molten chloride media. Due to the very demanding working conditions (higher of Nuclear Materials, vol. 430 . pp. 58-63. ISSN 0022-3115 hal-00831234,version1- #12;Electrochemistry

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    of spent nuclear fuel is based on di- rect disposal or single recycling of U and Pu, whereas a strategy material, as shown, e.g. during development of an electrorefining process for nuclear fuel treatment using of Nuclear Materials, vol. 430 . pp. 58-63. ISSN 0022-3115 #12;Electrochemistry of uranium in molten LiF­CaF2

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    on the vulnerability of advanced CMOS technologies to MGy dose environments. (2013) IEEE Transactions on Nuclear or future nuclear power plants considering various radiation en- vironments including normal and accidental operating conditions, high energy physics instruments, fusion experiments or deep space missions. Various

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    and methyl acrolein. Their formation was shown to obey two main reaction pathways, both involving methyne here as a realistic path leading to methyl acrolein. The relative proportions of the six main VOCs

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    with multiphase alloys. Electrochemical measurements confirmed the stability of the thin alloy films and revealed- proaches, for example, impedance spectroscopy, have been used.4,5 However, as indicated by Schmutz et al microscopy AFM , with in situ scratching and Volta potential mapping, to ex- amine localized corrosion

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    in an initially quiescent flammable mixture and propagates past solid obstacles, generating a strong pressure involved in flame acceleration and pressure increase generation. Effects of geometric features or fuel type, France ABSTRACT: In order to understand gas explosion phenomena in industrial buildings, a reduced

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    Paris-Sud XI, Université de

    in South- and East-Asia. The Japanese word Kansei, commonly translated as "feeling", includes a wide range ParisTech researchers and makes it freely available over the web where possible. This is an author results on product emotions etc. in the Kansei questionnaires. Thereafter we present a study on the wide

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    and Feuillebois, François and Simonin, Olivier Eulerian Simulation of Interacting PWR Sprays Including Droplet. 133-143" #12;KEYWORDS: containment, spray, collision EULERIAN SIMULATION OF INTERACTING PWR SPRAYS d Institut de Mécanique des Fluides de Toulouse, Toulouse, France A numerical simulation

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    -iso-propoxide as titanium and oxygen precursors and hydrazine as a nitrogen source. The films composition was monitored pressure CVD MOCVD TiOxNy Hard coatings Titanium oxynitride coatings were deposited on various substrates by an original atmospheric pressure metal organic chemical vapor deposition (MOCVD) process using titanium tetra

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    with Automation: Use of Cognitive Countermeasures. (2011) Human Factors: The Journal of the Human Factors with automation leads to the degradation of operators' performance by promoting excessive focusing on a single in the unmanned ground vehicle environment. Applications: The principle of cognitive counter- measures can

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    pressure and other sig- nals, aimed at characterizing the properties of a geologic porous medium and analyses of pressure signals, hydrogeologic characterization and evolution of Excavation Damaged Zone, published in " " #12;Statistical analyses of pressure signals, hydrogeologic characterization and evolution

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    . Supercapacitor devices, also known as electrical double-layer capacitors (EDLCs), store charge by adsorption. However, the charge is confined to the surface, so the energy den- sity of EDLCs is less than electrode material lead to EDLC-like electrochemical features but the redox pro- cesses lead to much greater

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    ;Optimization of the settings of multiphase induction heating system Majid Souley EDF Eco-Efficiency & Indust Toulouse France stephane.caux@laplac e.univ-tlse.fr Olivier Pateau EDF Eco-Efficiency & Indust.Process Dept, Université de Toulouse; INPT, UPS; CNRS, Laboratoire Plasma et Conversion d'Energie, ENSEEIHT, 2 rue Camichel

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    of multiphase induction heating system Majid Souley EDF Eco-Efficiency & Indust.Process Dept, Av. des stephane.caux@laplac e.univ-tlse.fr Olivier Pateau EDF Eco-Efficiency & Indust.Process Dept, Av. des Toulouse; INPT, UPS; CNRS, Laboratoire Plasma et Conversion d'Energie, ENSEEIHT, 2 rue Camichel, 31071

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    for Power Generation and Energy Conversion Applications (PowerMEMS 2012), 02 December 2012 - 05 December and Energy Conversion Applications (PowerMEMS 2012), Atlanta : États-Unis (2012)" #12;PROOF OF CONCEPT for long term, deploy and forget, WSN. Environmental energies such as mechanical vibrations, solar

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    via atmospheric deposition, urban runoff, wastewater, industrial efflu- ents and agricultural in metal dynamics and export in a small agricultural catchment. (2013) Journal of Hydrology, vol. 499 . pp;Significance of floods in metal dynamics and export in a small agricultural catchment Vincent Roussiez a

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    administrator: staff-oatao@inp-toulouse.fr #12;Testing Real-time Systems Using TINA Noureddine Adjir 1 , Pierre for model-based black-box conformance testing of real-time systems using the Time Petri Net Analyzer TINA.1007/978-3-642-05031-2_1 To cite this version: ADJIR, Noureddine , SAQUI-SANNES, Pierre De , RAHMOUNI, Kamel Mustapha. Testing real-time

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    of helical tip and root vortices in a wind turbine wake. (2013) Physics of Fluids, vol. 25 . pp. 1-16. ISSN vortices in a wind turbine wake Michael Sherry,1,a) Andr´as Nemes,1 David Lo Jacono,1,2 Hugh M. Blackburn,1 non-dimensional wake distance. I. INTRODUCTION Rotor systems such as wind turbines, airplane

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    and roughness was observed and discussed. 1. Introduction Photovoltaic technology is emerging as a major source of electri- cal energy [1], and the most common base material for photovoltaic cell is solar grade silicon, silicon metal is more reductive than hydrogen meaning that silicon electrodeposition has to be carried out

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    for Enhanced Structured Lipids for Foods. Journal of the American Oil Chemists' Society, vol. 88 (n° 2). pp,2,3-trioleoyl-sn-glycerol (OOO), for palm oil and cocoa butter. Then, addition to palm oil of Medium extensive enthalpy (kJ) p phase p n number of mols P pressure (bar) q Molecule size parameter R gas constant

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    for sustainability, c) end-of-life studies, and d) energy efficiency monitoring and studies. But it remains a lack SUSTAINABILITY ASSESSMENT: STEP FOR LCA - 2013 Any correspondence concerning this service should be sent, published in "6th International Conference on Life Cycle Management Sweden (2013)" #12;The 6th International

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    ) design-for-X principles and design for sustainability, c) end-of-life studies, and d) energy efficiency SUSTAINABILITY ASSESSMENT: STEP FOR LCA - 2013 Any correspondence concerning this service should be sent, published in "6th International Conference on Life Cycle Management, Sweden (2013)" #12;The 6th

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    - temperature heat recovery applications, since they allow better recovery efficiency for a simplified cycle, allowing efficiency improvements, reduction of the cycle size and production in modular units. Many studies than the liquid/vapor critical point pressure, have an even greater potential, since they allow better

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    processes of prototyping for manufacturing reconstituted wood products: 3D printing and Solid Freeform

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    Paris-Sud XI, Université de

    Titanium Aluminum a b s t r a c t Laser-induced reactive wetting and brazing of T40 titanium with A5754 with laser in welding­brazing regime whereas Ma et al. (2013) have carried out tungsten arc butt - Generation and characterization of T40/A5754 interfaces with lasersPatrice - Journal of Materials Processing

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    , 31062 Toulouse cedex 9, France Keywords: Nanowires; Conductive polymer composites; Aspect ratio of conductive filler and is observed for the first time in a conductive polymer composite. 1. Introduction Conductive polymer composites have attracted significant attention since the introduction of metal [1

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    a c t Keywords: Nanowires; PEKK; Composites; Conductivity; Mechanical properties High-performance conductive thermoplastic composites poly(ether ketone ketone) (PEKK)/silver nanowires were elaborated by melt obtained above the percolation threshold were among the highest measured for low-filled conductive polymer

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    ; Conductive polymer composites; Polyamide 11; Dynamic mechanical properties; Nanocomposites Highly conductive been devoted to the elaboration of polymer con- ductive composites. Electrical conductivity is a crucial property for aero- nautical composites polymer based. Conductive fillers are added to promote

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    conduction in carbon nanotubes-polymer composites is examined by the construction of master curves Conductivity of Carbon Nanotubes-Polyepoxy Composites. (2003) Macromolecules, vol. 36 (n° 14). pp. 5187, published in "" #12;DC and AC Conductivity of Carbon Nanotubes-Polyepoxy Composites Sophie Barrau, Philippe

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    , Colette Effect of Palmitic Acid on the Electrical Conductivity of Carbon Nanotubes-Epoxy Resin Composites applications, especially as fiber reinforced composites. For this application, some electri- cal conductivity is required to provide electrostatic discharge. To allow a conductive path inside the polymer matrix

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    , Ireland a b s t r a c t Keywords: Nanowires; Conductive polymer composites; Polyamide 11; Dynamic to the elaboration of polymer con- ductive composites. Electrical conductivity is a crucial property for aero- nautical composites polymer based. Conductive fillers are added to promote the increase of electrical

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    . On the other hand, titanium nitride has a good thermal and electrical conductivity and a high hardness. Ti coatings [2], electrically switchable windows [3], transparent IR window electrodes [4], effectiveOxNy Hard coatings Titanium oxynitride coatings were deposited on various substrates by an original

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    ON COMPOSITE MATERIALS, Seville, Spain, 22-26 June 2014 2 Figure 1. Environmental impacts due to the carbon MATERIALS, Seville, Spain, 22-26 June 2014 1 THE RECYCLING OF OMC'S CARBON REINFORCEMENT BY SOLVOLYSING: Composite recycling, carbon reinforcement recovery, epoxy matrix solvolysis, life cycle assessment (LCA

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    nanotube­Co­MgO composite powders and extraction of the nanotubes. (2000) Journal of Materials Chemistry #12;Synthesis of single-walled carbon nanotube±Co±MgO composite powders and extraction@iris.ups-tlse.fr A carbon nanotube±Co±MgO composite powder is prepared by reducing a Mg0.9Co0.1O solid solution in H2±CH4

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    endophyte of black spruce (Picea mariana) needles is also an aquatic hyphomycete. (2006) Molecular Ecology #12;Blackwell Publishing Ltd A fungal endophyte of black spruce (Picea mariana) needles is also spacer (ITS) sequence of this fungus and of a com- monly encountered foliar endophyte isolated from P

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    'optimisation ´energ´etique de la marche ont ´et´e effectu´ees pour cette structure et pour diff´erents rayons de`ere ´energ´etique est r´ealis´ee `a l'aide du Simplex. Les r´esultats montrent que des rayons ´elev´es au contact est une piste pour diminuer la consommation ´energ´etique. Abstract : The knee of biped robots has

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    by spark plasma sintering of oxide nanoparticles. Scripta Materialia, vol. 63 (n° 2). pp. 211-214. ISSN: staff-oatao@inp-toulouse.fr. #12;Optically transparent ceramics by spark plasma sintering of oxide densification rates characteristic of spark plasma sintering (SPS), the latter technique has been widely

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    by spark plasma sintering at 100 MPa, within the temperature range of 700­1500 C. Sintering at 700 C. Introduction Spark plasma sintering (SPS) has been used for rapid den- sification of different ceramic plasma sintering. Journal of the European Ceramic Society, vol. 31 (n° 6). pp. 1057-1066. ISSN 0955

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    -Fritsch, Sophie ( 2011) Microstructure of Ba1-xLaxTiO3- ceramics sintered by spark plasma sintering. Journal of Ba1-xLaxTiO3- ceramics sintered by Spark Plasma Sintering N. El Horra,, Z. Valdez-Navab,c, C, there has been a growing interest for Spark Plasma Sintering (SPS) technique. It offers, in comparison

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    of multi-walled carbon nanotube-yttria-stabilized ZrO2 composites prepared by spark plasma sintering. (2013. The specimens are densified by spark plasma sintering. Compared to ZrO2, there is a 3.8-fold decrease. Keywords: Spark plasma sintering; Carbon nanotubes; Zirconia; Friction Carbon-containing composites

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    of multi-walled carbon nanotube-yttria-stabilized ZrO2 composites prepared by spark plasma sintering. (2013 nanotube-yttria-stabilized ZrO2 composites prepared by spark plasma sintering A. Kasperski, A. Weibel, D plasma sintering. Compared to ZrO2, there is a 3.8-fold decrease of the friction coefficient against

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    by spark plasma sintering.Mechanics of Materials, vol. 42 (n° 5). pp. 548-558. ISSN 0167-6636 Any produced by spark plasma sintering Gabriella Bolzon a,*, Enzo J. Chiarullo a , Pedro Egizabal b , Claude composites Spark plasma sintering (SPS) Material characterization Instrumented indentation Drucker

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    ceramics obtained by Spark Plasma Sintering (SPS) contain cubic and tetragonal phases. Rather large oxygen

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    and Estournès, Claude ( 2010) Proto-TGO formation in TBC systems fabricated by spark plasma sintering. Surface-TGO formation in TBC systems fabricated by spark plasma sintering Mathieu Boidot a , Serge Selezneff a , Daniel coating Alumina Spark plasma sintering Thermal barrier coatings (TBC) are commonly used in modern gas

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    Made From Zinc Oxide Nanoparticles Through Low Temperature Spark Plasma Sintering. Advanced Functional of Varistors Made From Zinc Oxide Nanoparticles Through Low Temperature Spark Plasma Sintering By Le´na Saint sintering[9] and the initial nanoscale is lost in the final ceramics, so that no varistor ceramics

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    boundary-layer is then subject to a low frequency phenomenon known as 'flapping'. The influence Reynolds number for which the separated flow becomes unstable with respect to oscillatory perturbations

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    59046 Lille, France Abstract. Cr, CrN and CrAlN monolayers were synthesized by RF dual magnetron sputtering on AISI4140 steel and silicon substrates at 200°C. Multilayers coatings based on the three mono boundaries between the two phases. As a consequence, it is reported that CrAlN films exhibited excellent

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    variations are not always measured in most industrial robots. Therefore, in this study, an observer. INTRODUCTION A. Robot and control Current studies propose to replace some special machine- tools by industrial robots because of their effective cost and larger workspace compared with usual machine

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    the Accuracy of Industrial Robots by offline Compensation of Joints Errors - 2013 Any correspondence concerning), Greece (2012)" #12;Improving the Accuracy of Industrial Robots by offline Compensation of Joints Errors.damak@geomnia.eu Abstract--The use of industrial robots in many fields of industry like prototyping, pre-machining and end

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    with industrial six-axis robots 2 Abstract Nowadays, the adaptation of industrial robots to carry out high. This planning method is validated experimentally on an industrial robot. Key words Trajectory planning; Industrial Robots; Jerk; Vibration; Machining. hal-00992192,version1-16May2014 #12;Feedrate planning

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    -grinding significance for calcium carbonate­calcium phosphate mixed cement. Part I: effect of particle size and mixing-oatao@inp-toulouse.fr. #12;Co-grinding significance for calcium carbonate­calcium phosphate mixed cement. Part I: Effect Emile Monso, BP 44362, 31030 Toulouse Cedex 4, France Keywords: Bone cement Calcium carbonate Calcium

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    Decomposition has been constructed. The model has been extended to include the effect of control. The Reduced be sometimes intense. Applications of such flows arise in airframe fuel vents, landing gears, weapon bays

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    -based approach for reliability assessment. (2014) In: International Conference on Accelerated Life Testing-based approach for reliability assessment Hocine Dehmous1 , Moussa Karama2 and H´el`ene Welemane2 1 Universit of composite materials and structures. Based on the coupling of reliability methods and homogenization

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    their TRP. Solid oxide fuel cells SOFCs with a planar configura- tion are of great interest as efficient in SOFCs are often heterogeneous, the knowledge of their thermophysical properties is not straight- forward. In particular, the thermal radiative properties TRP of SOFCs ceramic are unknown and, in more general view

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    Ansart Abstract Solid Oxide Fuel Cells (SOFCs) operate at temper- atures above 1,100 K where radiation effects can be significant. Therefore, an accurate thermal model of an SOFC requires the inclusion used in the design of SOFCs must be known. However, little information can be found in the literature

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    power modules devices are paramount components in the aeronautical, automotive and military applications management (Fig .1). The dielectric ceramic substrate is double bonded with thick copper or aluminum such as AlSiC, copper or aluminum. The brazing is achieved using solder alloys considered as one

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    than aluminum alloys, whereas they exhibit the same mechanical characteristics. Their application increases in many economic sectors, in particular, in aeronautic and automotive industries. Nevertheless,2 Consequently, automotive industries became highly interested on the use of magnesium and its alloys in order

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    in the fields of aerospace, automotive and many other industries where weight reduction is a concern, because two-thirds of that of aluminum alloys and a quarter of that of steels. Despite the versatility aluminum alloys [1]. The most common treatments used to improve these properties are chemical surface

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    Mailhes, Corinne

    with a transition process of the cellulose, occurring at a temperature defined by the inflection point Tt with petrochemical plastic materials, which at the end of their useful life become litter (Scott 2000), and Derraik for petrochemical plastics, mainly B. Jallabert Á G. Vaca-Medina Á A. Rouilly (&) Laboratoire de Chimie Agro

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    Paris-Sud XI, Université de

    of delamination mechanisms during a laser drilling on a cobalt-base superalloy - Journal of Materials Processing a laser drilling on a cobalt-base superalloy J. Girardot , M. Schneider, L. Berthe, V. Favier Arts et-base superalloy Laser drilling Fast camera analysis Thermal barrier coating Haynes 188 a b s t r a c

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    Paris-Sud XI, Université de

    , simulation, CNEM. Abstract : This work presents a numerical alternative for the laser drilling simulation process of the laser drilling and the modeling equations are clarified. Then a comparison between, drilling, simulation, CNEM. 1 Introduction La simulation d'un procédé d'usinage tel que le perçage laser en

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    Paris-Sud XI, Université de

    , Nicole GENET - Evaluation of Lubricant Viscosity and Base Oil Effects by Form Tapping Test - - 2008 Any@ensam.eu #12;1 Evaluation of lubricant viscosity and base oil effects by form tapping test. A. Bierla La to correlate the effect of lubricant viscosity and base oil on the efficiency of a lubricant, we measure

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    Paris-Sud XI, Université de

    the lubrication of the piston slide and the tightness of the combustion chamber. Thus, oil con- sumption dynamic effects in continuous balanced contact with the workpiece have to be studied deeply. This paper highlights these effects on honed surface textures. The stone dynamic behav- ior was studied at conventional

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    Boyer, Edmond

    for stochastic Finite Element (FE) post-processing calculation of the iron losses in the stator of a synchronous - Stochastic post-processing calculation of iron losses ­ application to a PMSM - COMPEL: The International : archiveouverte@ensam.eu #12;STOCHASTIC POST-PROCESSING CALCULATION OF IRON LOSSES - APPLICATION TO A PMSM M

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    Boyer, Edmond

    @ensam.eu #12;Abstract-- Industrial processing (cutting, assembly...) of steel laminations can lead is not usually verified because of the tool wear or, more intrinsically, to the manufacturing process itself are more likely to be affected. In the present work, twenty eight (28) samples of slinky stator (SS

  1. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

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    Paris-Sud XI, Université de

    stochastic model of anhysteretic non-linear B(H) curve is proposed for the ferromagnetic yokes of the stator of these five parameters on the flux linkage of one phase of the stator winding depending on the excitation) and investigate where the characterization process of the B(H) curve should focus to improve the accuracy

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    Mailhes, Corinne

    reprocessing strategies are particularly ap- plicable to the reprocessing of sodium cooled fast reactor fuel. The

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    Paris-Sud XI, Université de

    systems, solar panels, textiles, and largely in medical devices. For computer assisted application de-temperature superposition property was used to predict the shape memory behavior of the acrylate polymer network. All-sebastian.arrieta-escobar@ensam.eu (Sebasti´an Arrieta) Accepted in Mechanics of Materials September 5, 2013 #12;well the material behavior

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    Paris-Sud XI, Université de

    for SMEs: Application to an equipment manufacturer - Int. J. of Product Lifecycle Management - Vol. 6, n°1. of Product Lifecycle Management 6, 1 (2012) 51 - 64" DOI : 10.1504/IJPLM.2012.046429 #12;International Journal of Product Lifecycle Management 1 Copyright © 200x Inderscience Enterprises Ltd. Generic PLM

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    Mailhes, Corinne

    and Cantarel, Arthur and Karama, Moussa Identification of the elastic properties in CFRP composites. (2014) In-Laetitia Pastor*, Hélène Welemane , Arthur Cantarel*, Moussa Karama Université de Toulouse, INP-ENIT, LGP, 47.perrin@iut-tarbes.fr, marie.laetitia.pastor@iut-tarbes.fr, arthur.cantarel@iut-tarbes.fr Keywords: Laminated composite

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    Paris-Sud XI, Université de

    and Cantarel, Arthur and Karama, Moussa Identification of the elastic properties in CFRP composites. (2014) In composites Victor Munoz , Marianne Perrin*, Marie-Laetitia Pastor*, Hélène Welemane , Arthur Cantarel 1624, 65016 Tarbes, France, marianne.perrin@iut-tarbes.fr, marie.laetitia.pastor@iut-tarbes.fr, arthur.cantarel

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    and Cantarel, Arthur and Karama, Moussa Utilisation de la thermographie infrarouge et de l'émission acoustique carbone-époxy Munoz Victor1, Perrin Marianne2, Pastor Marie-Laetitia2, Welemane Hélène1, Cantarel Arthur2.perrin@iut-tarbes.fr; marie- laetitia.pastor@iut-tarbes.fr; arthur.cantarel@iut-tarbes.fr Résumé : Le manque de connaissances

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    Paris-Sud XI, Université de

    and Cantarel, Arthur and Karama, Moussa Utilisation de la thermographie infrarouge et de l'émission acoustique, Perrin Marianne2, Pastor Marie-Laetitia2, Welemane Hélène1, Cantarel Arthur2, Karama Moussa1 1 PRES.pastor@iut-tarbes.fr; arthur.cantarel@iut-tarbes.fr Résumé : Le manque de connaissances dans le comportement des matériaux

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    , and then it rehardens when cooled. It is possible that between these two polymers a bond is formed by the diffusion of conditions such as a good behavior in the bonding of oriented PET films up to a temperature of -90 °C. Under, this phenomenon of diffusion gives rise to the formation of an interphase region. This interphase region

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    this version : Emilie LE GUEN, Muriel CARIN, Rémy FABBRO, Frédéric COSTE, Philippe LE MASSON - 3D heat transfer model of hybrid laser Nd : Yag-MAG welding of a S355 steel and experimental validation - International

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    . (2014) Oil & Gas Science and Technology Journal, vol. 69 (n° 1). pp. 83-105. ISSN 1294-4475 Any premie` re est le moteur atmosphe´ rique F7P, a` quatre soupapes par cylindre qui dispose d'une caracte

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    in novel ceramic matrix nanocomposites. (2000) Ceramics International, vol. 26 (n° 6). pp. 677-683. ISSN in novel ceramic matrix nanocomposites A. Peigney *, Ch. Laurent, E. Flahaut, A. Rousset Laboratoire de that produces ceramic±matrix composite powders that contain in situ grown nanotubes. The synthesis parameters

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    ´e Paul-Sabatier, 31062 Toulouse Cedex 9, France Abstract The densification by hot-pressing of ceramic­matrix for use in nanocomposite materials with a metal­matrix, polymer­matrix or ceramic­matrix.1 However, relatively few works have so far addressed such ceramic­matrix composites. The preparation methods

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    and Peigney, Alain Percolation of single-walled carbon nanotubes in ceramic matrix nanocomposites. (2004) Acta.actamat.2003.10.038 #12;Percolation of single-walled carbon nanotubes in ceramic matrix nanocomposites S. Rul into a metal-, ceramic- or, more commonly, polymer- matrix. The composites are generally prepared by mixing

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    Mailhes, Corinne

    in novel ceramic matrix nanocomposites. (2000) Ceramics International, vol. 26 (n° 6). pp. 677-683. ISSN: staff-oatao@listes-diff.inp-toulouse.fr #12;Carbon nanotubes in novel ceramic matrix nanocomposites A of carbon nanotubes, we describe an original catalytic method that produces ceramic±matrix composite powders

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    devices and their incorporation in polymer­ matrix, metal­matrix, or ceramic­matrix composites.2 The ob to carbon nanotube growth. Journal of the American Ceramic Society, vol. 93 (n° 11). pp. 3732-3739. ISSN difficulty to prepare a nanocomposite is to achieve a homogeneous dispersion of the CNTs in the matrix

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    -to-weightratios and impact energy absorption.Theyhave become increasingly employed in automotive and energy applica- tions to extreme external con- ditions such as impact or fatigue loadings. Since 1970, PP or PP copolymers (PPC of their low price, l

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    -grained polycristalline aluminium alloy (grain dimension in the millimeter range) under tensile test Corresponding author

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    this version : Mortatti, Jefferson and Meneghel de Moraes, Graziela and Probst, Jean-Luc Heavy metal@cena.usp.br) Variations in the aquatic environmental conditions can produce a release of heavy metals from the sediment, allowing a detailed study of heavy metals in association with the bioavailable and residual fractions

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    . Between the small drag limit, with the two families of marginal and non- dispersive shallow water waves, and the large drag limit, with the marginal and non- dispersive waves of the kinematic wave approximation frottement. Keywords: Convective instability, kinematic-wave approximation, roll-wave instability, Saint

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    Boyer, Edmond

    species. The presence of shredders sub- stantially increased the resuspension of fine sediments ([300, human use and modification of soils, for instance from agriculture, forestry and mining, can lead

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    vehicles' CO2 emissions are particularly interested in polymer-coated steels. For example, Smoosteel, manganese phosphate, and vinylphenol was applied on the HDG steel to obtain high corrosion resistance and high adherence of a polyester and melamine primer. The influence of the manganese phosphate

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    , Ph. ( 2010) CO2 sensing properties of semiconducting copper oxide and spinel ferrite nanocompositeHz). The results showed a high response of 50% (Rair/RCO2 = 1.9) at 250 C and 700 Hz for a CO2 concentration-type CuO has been developed by Herran et al. [9] to explain how AC electri- cal properties change with CO2

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    Boyer, Edmond

    . However, the main limitations of PLA as a packaging material are a high gas permeability (CO2, O2/PHBV Films with Improved Mechanical and Gas Barrier Properties - Macromolecular Materials and Engineering.201200285 #12;PLA/PHBV Films with Improved Mechanical and Gas Barrier Properties Majdi Boufarguine, Alain

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    Boyer, Edmond

    functionality, also makes them ideal as CO2 absorbents for post-combustion CO2 capture. Similarly, the tuneable. Austen Angellg Ionic liquids offer a unique suite of properties that make them important candidates with high electrochemical and thermal stability, as well as ionic conductivity, create the possibility

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    III ions at the octahedral sites, which were reduced to Co2? on producing CoO. For 0 \\ x B 1, the reduction that took into account either CoIII and Mn3? or Co2? , CoIII and Mn4? only, our thermal analysis study showed that Co2? /CoIII and Mn3? /Mn4? pairs occupy the octahedral sites. These results were used

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    efficiency thermodynamic cycles such as supercritical steam and carbon dioxide. First experimental results. The absorber is a 42.4 mm o.d. stainless steel tube. SiC was used because of its thermal properties

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    Boyer, Edmond

    of zeolite chemical surface properties on VOC elimination was also investigated. Three modified zeolite carbon is normally pre- ferred. However, activated carbons are not stable at high temperatures and could. Natural zeolites have been applied for sulfur dioxide and VOC removal (Kuleyin ; Allen et al

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    degradation. During this decomposition, the principal products are water and carbon dioxide [5, 11, 12, 14, 15 number of studies published on its properties is explained by important interests to optimize the natural influence have to be carefully considered [21]. According to Hatakeyama [20], physico-chemical properties

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    Boyer, Edmond

    opportunities for high efficiency thermodynamic cycles such as supercritical steam and carbon dioxide. First. The absorber is a 42.4 mm o.d. stainless steel tube. SiC was used because of its thermal properties

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    Boyer, Edmond

    and Biggs, Jeremy and Bressi, Nicolas and Grillas, Patrick and Hull, Andrew P. and Kalettka, Thomas Coccia · Arthur Compin ·Jeremy Biggs ·Nicolas Bressi ·Patrick Grillas· Andrew Hull· Thomas Kalettka. Roma 1, Rome, Italy C. Coccia CISC, Donana, Spain J. Biggs Pond Conservation: The Water Habitats Trust

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    this version : Boix, Dani and Biggs, Jeremy and Céréghino, Régis and Hull, Andrew P. and Kalettka, Thomas research and management in Europe: "Small is Beautiful" Dani Boix· Jeremy Biggs ·Régis Céréghino · Andrew P, 17071 Girona, Catalonia, Spain e-mail: dani.boix@udg.edu J. Biggs Pond Conservation, Oxford, UK R

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    particles, whereas FeAl2O4 grains formed during SPS are ben- eficial for higher cycle numbers. Keywords of the associated energy by elastic deformation. Alumina­ matrix nanocomposites and nano/micro hybrid compos- ites

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    , ranging from 15 to 44) adults with estimated average total biomass of 651 kg (386 ­ 1132) and biomass is the occurrence of high local density and biomass. For instance, large numbers of Pacific salmon aggregate predator (Wels catfish, Silurus glanis). This species is the world's third largest and Europe's largest

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    . The predominant anthropogenic Hg sources were coal burning and smelter Hg emissions. a b s t r a c t Keywords and after the In- dustrial Revolution were coal burning and smelter Hg emissions. Mercury accumulation rates

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    coal burning and smelter Hg emissions. a b s t r a c t Keywords: Atmospheric pollution Coal combustion were coal burning and smelter Hg emissions. Mercury accumulation rate

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    Boyer, Edmond

    high-temperature synthesis (SHS),2 reaction between gaseous glasses.1 Therefore, various synthetic methods have been considered for pollucite using self-propagating thus producing a highly dense waste form. Furthermore, the measured solubility of pollucite is lower

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    concerns the assessment of fire and explosion hazards and the development of inherently safer designs;Introduction The fire and explosion hazard of liquids is primarily characterized by their flash point.1 01 ­ France ABSTRACT Flash point is the most important variable used to characterize the fire

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    , electrochemistry or air contamination. The downsizing of the particle size of such material permits an improvement scale, is a powerful technique to study the chemical state of transition metal oxides in nano to their use in battery materials. In this paper the degree of crystallinity and the grain size distribution

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    % to 79%). Microemulsions are used as a "green solvent" and give a better contact be- tween the phases

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    anodic films on 1050 aluminium sub- strate were coloured by AC electrodeposition of nickel. Several by the electrodeposition of nickel [9­17] or more rarely cobalt [18, 19]. The deposition electrolyte is usually a sulphate) Electrical behaviour, characteristics and properties of anodic aluminium oxide films coloured by nickel

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    ­trifluoroethylene) [P(VDF-TrFE)] matrix. The nanowires were synthesized by electrodeposition using nanoporous anodic such as electrical conductivity [9] and magnetic susceptibility [10­12]. Nickel nanowires (Ni NWs) have a high

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    in a deteriorated heat transfer regime. Among the several past in-pile research programs on RIA, the experiments the work of Toulouse researchers and makes it freely available over the web where possible during a reactivity initiated accident (RIA). It has been demonstrated that under very fast transient

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    new, cleaner processes and through assembly optimization. On one hand, life cycle assessment (LCA) [1 to apply life cycle assessment to product industrialization, and specifically to assembly lines systems), and ISO:14040 and 14062 (for life cycle assessment and the eco-design approach) help

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    Gasification Syngas Plasma Polishing Raw syngas Heat recovery steam heat Syngas cleaning Separation shredding Buffer storage Ash melting Hot polished syngas Commercial syngas heat Low t° syngas ELECTRICITY RESIDUAL Inert molten slag 1200°C Valuable fuel 1. WASTE TO FUEL Gasification Syngas Plasma Polishing Raw syngas

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    and design for sustainability [16-25]; c) end-of-life studies [26-31]; and d) energy efficiency monitoring for Manufacturing Sustainability Assessment. In : Re-engineering Manufacturing for Sustainability, Springer - 2013 Sustainability Assessment Yaoyao Fiona Zhao 1 , Nicolas Perry 2 , Hery Andriankaja 3 1 Department of Mechanical

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    of polarization (DoP) is a fundamental quantity characterizing a par- tially polarized electromagnetic field Member, IEEE Abstract--Monitoring and detection of ships and oil spills using synthetic aperture radar coverage and day and night all-weather capabilities of SAR systems. Among different polarimetric SAR modes

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    and subjective evaluation of a human­robot object hand-over task. (2011) Applied Ergonomics, vol. 42 (n° 6). pp administrator: staff-oatao@listes-diff.inp-toulouse.fr #12;Physiological and subjective evaluation are not enough. It is necessary to guarantee ergonomic robot motions. Therefore, we have developed Human Aware

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    6 aluminium alloy. Surface and Interface Analysis, vol. 42 (n° 4). pp.185-188. ISSN 0142-2421 Any-oatao@inp-toulouse.fr. #12;Corrosion behaviour of mechanically polished AA7075-T6 aluminium alloy Y. Liu,a A. Laurino,b T behaviour of AA7075 aluminium alloy are investigated. It was found that a nano-grained, near

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    . Influence of anodizing process on fatigue life of a machined aluminium alloy. Procedia Engineering, 2010 of Anodizing Process on Fatigue Life of Machined Aluminium Alloy M. Shahzad * - M. Chaussumier - R. Chieragatti. Being subjected to different environmental conditions, aluminium alloys often undergo different surface

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    Aluminium alloy The aim of this study was to investigate the Coefficient of Thermal Expansion (CTE) of anodic films on 7175 T7351 aluminium alloy and to evaluate the influence of the film characteristics are processed on light alloys to obtain specific superficial characteristics. Actually, the growth of oxide

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    that decrease of the fatigue life of aluminium alloys treated with anodization can be explained; pits; fatigue; aluminium alloy; short crack; long crack 1. Introduction Aluminum alloys 2xxx and 7xxx conditions, aluminium alloys are often anodized by electrolytic process that produces controlled columnar

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    Black inorganic anodized aluminium alloys are used for managing passive thermal control on spacecraft thermal cycling on 2XXX and 7XXX aluminium alloys. This phenomenon could generate particulate been studied for a 7175 T7351 aluminium alloy. The chemical heterogeneity of the coating has been

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    and creep on intergranular fatigue crack path in 2XXX aluminium alloys. (2010) Engineering Fracture crack path in 2XXX aluminium alloys Gilbert Hénaff *, Frédéric Menan 1 , Grégory Odemer 2 Institut Aluminium alloy Corrosion­fatigue Creep­fatigue Hydrogen embrittlement Cavitation a b s t r a c

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    E-Print Network [OSTI]

    interest in using magnesium alloys to replace aluminium alloys in some structural and mechanical parts embedded thermocouples were previously performed for aluminium alloys [4­7]. They did not observe any tem31 magnesium alloy rolled sheets: Influence of processing parameters - Acta Materialia - Vol. 57, n°2

  16. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

    E-Print Network [OSTI]

    Boyer, Edmond

    was wrought aluminium 2024-O in the form of 5 mm sheets. The second was a cast aluminium-silicon alloy AlSi7Cu compared to the uniaxial condition. However, in terms of the cast aluminium alloy, it has been demonstrated determined at 2 · 106 cycles and at various R-ratios using a staircase procedure. For the aluminium 2024

  17. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    : staff-oatao@listes-diff.inp-toulouse.fr #12;Recovery of actinides from actinide­aluminium alloys A chlorination route is being investigated for recovery of actinides from actinide­aluminium alloys, which experimentally tested using U­Pu­Al alloy prepared by electrodeposition of U and Pu on solid aluminium plate

  18. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    inhibition of 2024 aluminium alloy by sodium decanoate. Electrochimica Acta, vol. 55 (n° 21). pp. 6182 administrator: staff-oatao@inp-toulouse.fr. #12;Corrosion inhibition of 2024 aluminium alloy by sodium decanoate, 118 route de Narbonne, 31077 Toulouse Cedex 04, France Keywords: Aluminium alloy Carboxylates

  19. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Boyer, Edmond

    of actinides from actinide­aluminium alloys by chlorination: Part II P. Soucek a, , L. Cassayre b , R. Eloirdi actinide­aluminium alloys, which originate from pyrochemical recovery of actinides from spent metallic on solid aluminium plate electrodes by electrorefining of U­Pu­Zr alloy in the molten salt. All the most

  20. Open Archive Toulouse Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Boyer, Edmond

    ) Galvanic corrosion of aluminium­copper model alloys. Electrochimica Acta, vol. 52 (n° 27). pp. 7626 of aluminium­copper model alloys Jonathan Idraca, Georges Mankowskia, George Thompsonb, Peter Skeldonb, Yolande; Sulphate 1. Introduction In commercial aluminium­copper alloys, the various alloy- ing elements result

  1. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    ( 2011) Molecular mobility in piezoelectric hybrid nanocomposites with 0-3 connectivity: Particles size-oatao@inp-toulouse.fr. #12;Molecular mobility in piezoelectric hybrid nanocomposites with 0-3 connectivity: Particles size t Keywords: Dynamic dielectric spectroscopy; Thermostimulated currents; Hybrid nanocomposites; Molecular

  2. Open Archive Toulouse Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    activity of a hybrid ferroelectric nanocomposite, i.e. polyamide 11/barium titanate (BT), has been influence of BaTiO3 particles on piezoelectric behaviour of PA 11/BaTiO3 nanocomposites. Journal of Non particles on piezoelectric behaviour of PA 11/BaTiO3 nanocomposites Jean-Fabien Capsal a , Eric Dantras a

  3. Open Archive Toulouse Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    house effect, alternative fuels for diesel engines have been widely studied during the last decades. Biodiesel, as a renewable alternative diesel fuel, can be derived from vegetable oils, animal fats

  4. Open Archive Toulouse Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    and surface analyses) are discussed. Keywords: Polyimide; CVD; Flux vector; Thin films 1. Introduction with manufac- turing technology, and many others [1]. In the last several years, polymer thin film deposition to deposit materials in various forms, including: monocrystalline, polycrystalline, amorphous, and epitaxial

  5. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    is required. Moreover, a concept of movable factory, from one solar farm site to another one, is also with similar nature. The target project is to produce and install a 500,000 m² solar farm (i.e. 50,000 re/Process Simultaneous Design for Implementing a Fresnel Thermodynamic Solar Plant - 2013 Any correspondence concerning

  6. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

    E-Print Network [OSTI]

    Boyer, Edmond

    speeds. Keywords: Friction; tribology; cutting fluid; straight oil; heat partition coefficient #12;2 1 in order to eliminate problems associated with the cutting fluid management: waste generation, machining operations till uses cutting fluid since manufacturing procedure and machines cannot be modified easily

  7. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

    E-Print Network [OSTI]

    are difficult to perform and the manufacturing process that is most commonly used is gas tungsten arc welding for joining magnesium alloys as it presents a low and pre- cise heat input, high welding speed and a small BARRALLIER - Texture evolution in Nd:YAG-laser welds of AZ31 magnesium alloy hot rolled sheets and its

  8. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    on VAWTs like Savonius or Darrieus rotors ([7], [10]...) but few works were hal-00915125,version1-6Dec2013

  9. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    instationnaire d'un rotor éolien de Savonius : mise en évidence de l'influence de la portance - - 2013 Any´erodynamique instationnaire d'un rotor ´eolien de Savonius : mise en ´evidence de l'influence de la portance Pauline BUTAUDa'´eolienne Savonius, notamment en comparant les r´esultats statiques instationnaires (´eolienne immobile) et

  10. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    , and biomass gasi- fication. Since few years, the development of computational ability and Computational Fluid Dynamic (CFD) allows 3-dimensional realistic simulations of industrial configura- tions by using eulerian multi-fluid approach. In the application of CFD models, careful validation with experimental

  11. Open Archive Toulouse Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    O2; Supported photocatalyst; Visible photocatalysis 1. Introduction Titanium dioxide (TiO2) is an efficient and well studied semiconductor for various photodriven applications, as in photocatalysis [1

  12. Open Archive Toulouse Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    functional properties and microstructure of the films are discussed. Keywords: MOCVD; TiO2; Photocatalysis; Wettability 1. Introduction Water and air purification is the most promising application of photocatalysis

  13. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    of the classic von K´arm´an vortex street, regardless of the details of the body which forms the street structure, different from the classic von K´arm´an street, can be achieved depending on the amplitude oscillation of the cylinder at the vortex shedding frequency of the unperturbed cylinder is reported. Recent

  14. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    -Gaubert), galoroux@usp.br (G.C. LeRoux), cdfcdf2@yahoo.com, charles.jesus@bioetanol.org.br (C.D.F. de Jesus), ajgcruz

  15. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    for modelling pesticide fluvial transport: Application to an agricultural catchment in south-western France into pesticide partition coefficient Kd for modelling pesticide fluvial transport: Application to an agricultural, EcoLab, 31326 Castanet Tolosan Cedex, France h i g h l i g h t s Water managers need to assess

  16. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Boyer, Edmond

    to biological wastewater treatment [1]. Thanks to their dense structure, aerobic granules have very good to withstand high-strength wastewater and results in the biological reactor having a smaller volume than con- phate removal efficiency was observed in both systems; enhanced biological P removal being greater

  17. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    -epa.2010.0180 #12;Mono inverter Multi parallel PMSM - Structure and Control strategy Damien Bidarta , Maria a new and original Mono inverter Multi parallel Permanent Magnet Synchronous Motor (PMSM) system. Experimental results are given for a system with 2 PMSM plugged in parallel. The proposed solution can however

  18. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    -Tolerant Operation of an Open-End Winding Five-Phase PMSM Drive with Inverter Faults - - 2013 Any correspondence-Tolerant Operation of an Open-End Winding Five-Phase PMSM Drive with Inverter Faults Fabien Meinguet, Ngac-Ky Nguyen, Control reconfiguration, Fault tolerance, Multi-phase machines, Open-end winding, PMSM, Reliability. I

  19. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    fuel cells (PEMFCs) are one of the most promising solutions as an alternative to combustion engine) and performance modelling (PM): the PNM/PM approach. PNM allows simulating the decrease of through-plane gas simulating performance loss of PEMFC as a function of gas diffusion decay. This coupling shows that the loss

  20. Science Arts & Mtiers (SAM) is an open access repository that collects the work of Arts et Mtiers ParisTech

    E-Print Network [OSTI]

    voie à un gain de masse, à des réductions de coût en production et en maintenance, essentiellement'influence des différents paramètres du procédé de soudage TIG (Tungsten Inert Gas) appliqué à l'alliage d, cost savings in production and maintenance, mainly due to an improvement in corrosion resistance

  1. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    this version : Nouvel, Laurent- Xavier and Sirand-Pugnet, Pascal and Marenda, Marc and Sagné, Eveline and Barbe-events that are shaping mycoplasma diversity Laurent X Nouvel1,2 , Pascal Sirand-Pugnet3,4 , Marc S Marenda1,2,8 , Eveline

  2. Open Archive Toulouse Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    and mechanical testing of glass fiber entangled sandwich beams: A comparison with honeycomb and foam sandwich and mechanical testing of glass fiber entangled sandwich beams: A comparison with honeycomb and foam sandwich or glass-phe- nolic. The other most commonly used core materials are expanded foams, which are often

  3. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    ´rida, Venezuela b Laboratoire National des Champs Magne´tiques Intenses (LNCMI) ­ CNRS UPR 3228, Universite´ de g Centro de Estudios de Semiconductores, Universidad de los Andes, Me´rida 5201, Venezuela A B S T R

  4. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    , microwave reac- tors, reactive distillation, static mixers and microstructured reactors. Furthermore

  5. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    - tors, reactive distillation, static mixers and microstructured reactors. Furthermore, continuous flow

  6. Open Archive TOULOUSE Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    a two-step process including an initial emul- sification of two immiscible fluids in static mixers emulsification in static mixers are then investigated. The hydrodynamic of the Deanhex reactor used is also process, the emulsion droplets obtained at the static mixer outlet are encapsulated firstly in the Deanhex

  7. Open Archive Toulouse Archive Ouverte (OATAO) OATAO is an open access repository that collects the work of Toulouse researchers and

    E-Print Network [OSTI]

    Mailhes, Corinne

    with the simulated robot torques during the motion. 2 Humanoid motion generation and human movement analysis with the generation of human-like whole-body movements on anthropomorphic systems. We propose a general framework to generate robot movements from the definition of ordered stack of tasks and a global resolution scheme

  8. NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

    SciTech Connect (OSTI)

    none,

    1982-07-01T23:59:59.000Z

    This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.

  9. Numerical study of the thm effects on the near-field safety of a hypothetical nuclear waste repository - bmt1 of the decovalex iii project. part 1: conceptualization and characterization of the problems and summary of results

    E-Print Network [OSTI]

    2004-01-01T23:59:59.000Z

    T-H-M Processes for Nuclear Waste Repositories. Executivesafety of a hypothetical nuclear waste repository – BMT1 ofof a hypothetical nuclear waste repository at the near-fiel

  10. Repository Surface Design Engineering Files Report Rev 00 ICN 1

    SciTech Connect (OSTI)

    DOE

    2001-05-08T23:59:59.000Z

    The objective of the Repository Surface Design Engineering Files Report Supplement [herein known as the Engineering Files (EF)] is to provide the surface design data needed by the Environmental Impact Statement (EIS) contractor to prepare the EIS and evaluate options and alternatives. This document is based on the Repository Surface Design Engineering Files Report, Revision 03 (CRWMS M and O 1999f) (EF Rev 03). Where facility and system designs have been changed for the Site Recommendation (SR) effort they are described in this report. EIS information provided in this report includes the following: (1) Description of program phases; there are no changes that impact this report. (2) A description of the major design requirements and assumptions that drive the surface facilities reference design is provided herein (Section 2.2), including the surface design resulting from recommendations regarding Enhanced Design Alternative (EDA) II, as discussed in the License Application Design Section Report (CRWMS M and O 1999d), and changes to the waste stream. See Section 2, Table 2-2, for the SR waste stream. (3) The major design requirements and assumptions that drive the surface facilities reference design are by reference to EF Rev 03; there are no changes that impact this report. (4) Description of the reference design concept and existing site conditions is by reference to EF Rev 03 (including Table 4-1, which is not included in this supplement); there are no changes that impact this report. (5) Description of alternative design cases is by reference to EF Rev 03; there are no changes that impact this report. (6) Description of optional inventory modules is by reference to EF Rev 03; there are no changes that impact this report. (7) Tabular summary level engineering values (i.e., staffing, wastes, emissions, resources, and land use) for the reference design and the alternative design cases that address construction, emplacement operations, caretaker operations, and closure; changes, if any, are indicated on appropriate tables. (8) A description of a design concept for the complete retrieval and storage of waste packages, and summary-level engineering quantities for the construction and operation of this concept, is included as Attachment I; there are no changes that impact this report. (9) The concept for a 10,000 metric tons heavy metal (MTHM) Waste Staging Facility (Attachment II) has been deleted. The addition of four spent fuel assembly (SFA) staging pools in the Waste Handling Building (WHB) is described herein. (10) Description of a design concept for an on-site Cask Maintenance Facility to provide for shipping cask repair and recertification (Attachment III) is by reference to EF Rev 03; there are no changes that impact this report. (11) Figures that have changed for the SR effort are included in Attachment IV. Unchanged figures are referenced from EF Rev 03. (12) A preliminary design concept for dry vault inventory of commercial spent nuclear fuel to support thermal blending of spent fuel assemblies in waste packages has been added as Attachment V for this supplement.

  11. Aspects of igneous activity significant to a repository at Yucca Mountain, Nevada

    SciTech Connect (OSTI)

    Krier, D. J. (Donathan J.); Perry, F. V. (Frank V.)

    2004-01-01T23:59:59.000Z

    Location, timing, volume, and eruptive style of post-Miocene volcanoes have defined the volcanic hazard significant to a proposed high-level radioactive waste (HLW) and spent nuclear fuel (SNF) repository at Yucca Mountain, Nevada, as a low-probability, high-consequence event. Examination of eruptive centers in the region that may be analogueues to possible future volcanic activity at Yucca Mountain have aided in defining and evaluating the consequence scenarios for intrusion into and eruption above a repository. The probability of a future event intersecting a repository at Yucca Mountain has a mean value of 1.7 x 10{sup -8} per year. This probability comes from the Probabilistic Volcanic Hazard Assessment (PVHA) completed in 1996 and updated to reflect change in repository layout. Since that time, magnetic anomalies representing potential buried volcanic centers have been identified fiom magnetic surveys; however these potential buried centers only slightly increase the probability of an event intersecting the repository. The proposed repository will be located in its central portion of Yucca Mountain at approximately 300m depth. The process for assessing performance of a repository at Yucca Mountain has identified two scenarios for igneous activity that, although having a very low probability of occurrence, could have a significant consequence should an igneous event occur. Either a dike swarm intersecting repository drifts containing waste packages, or a volcanic eruption through the repository could result in release of radioactive material to the accessible environment. Ongoing investigations are assessing the mechanisms and significance of the consequence scenarios. Lathrop Wells Cone ({approx}80,000 yrs), a key analogue for estimating potential future volcanic activity, is the youngest surface expression of apparent waning basaltic volcanism in the region. Cone internal structure, lavas, and ash-fall tephra have been examined to estimate eruptive volume, eruption type, and subsurface disturbance accompanying conduit growth and eruption. The Lathrop Wells volcanic complex has a total volume estimate of approximately 0.1 km{sup 3}. The eruptive products indicate a sequence of initial magmatic fissure fountaining, early Strombolian activity, and a brief hydrovolcanic phase, and violent Strombolian phase(s). Lava flows adjacent to the Lathrop Wells Cone probably were emplaced during the mid-eruptive sequence. Ongoing investigations continue to address the potential hazards of a volcanic event at Yucca Mountain.

  12. Nevada potential repository preliminary transportation strategy: Study 1

    SciTech Connect (OSTI)

    None,

    1995-04-01T23:59:59.000Z

    Limited feasible options exist when considering the shipment of spent nuclear fuel and high-level radioactive waste. These options are rail or truck; because of the weight associated with transportation casks (68.0 to 113.4 tonnes/75 to 125 tons), heavy-haul trucks are also considered. Yucca Mountain currently lacks rail service or an existing right-of-way for rail; it also lacks a dedicated highway suitable for heavy-haul trucks. Approximately 11,230 shipments by rail are planned from waste producer sites to Nevada, with an additional 1,041 shipments by legal-weight truck from four reactor sites not capable of upgrading for rail shipment. This study identifies the reasonable alternatives for waste transport to the potential repository site, describes the evaluation process performed to identify those alternatives, and discusses the reasons for elimination of transportation routes deemed to be not reasonable. The study concluded that heavy haul truck transportation is feasible-cost is very favorable when compared to rail-but route restrictions must be further evaluated. In addition to restrictions due to seasonal weather conditions, specific routes have additional restrictions, including no travel on holidays or weekends, and travel during daylight hours only. Further restrictions will be imposed by the U.S. Department of Transportation based on routing of radioactive materials by highway. Operation and maintenance costs for heavy-haul over a 24-year period, based on preliminary information, were calculated on an estimated operational cost of $15,000 per trip, with an estimated 468 trips per year average (11,230 total trips), for an estimated cost of $171 million to $173 million, depending on the route used. Because the initial costs and the total system life cycle costs of heavy-haul are approximately 50 percent lower than the lowest rail cost, this option will continue to be evaluated.

  13. Dibaryons from Exceptional Collections

    E-Print Network [OSTI]

    Christopher P. Herzog; Johannes Walcher

    2003-07-17T23:59:59.000Z

    We discuss aspects of the dictionary between brane configurations in del Pezzo geometries and dibaryons in the dual superconformal quiver gauge theories. The basis of fractional branes defining the quiver theory at the singularity has a K-theoretic dual exceptional collection of bundles which can be used to read off the spectrum of dibaryons in the weakly curved dual geometry. Our prescription identifies the R-charge R and all baryonic U(1) charges Q_I with divisors in the del Pezzo surface without any Weyl group ambiguity. As one application of the correspondence, we identify the cubic anomaly tr R Q_I Q_J as an intersection product for dibaryon charges in large-N superconformal gauge theories. Examples can be given for all del Pezzo surfaces using three- and four-block exceptional collections. Markov-type equations enforce consistency among anomaly equations for three-block collections.

  14. Nye County, Nevada 1992 nuclear waste repository program: Program overview. Final report

    SciTech Connect (OSTI)

    NONE

    1998-07-01T23:59:59.000Z

    The purpose of this document is to provide an overview of the Nye County FY92 Nuclear Waste Repository Program (Program). Funds to pay for Program costs will come from the Federal Nuclear Waste Fund, which was established under the Nuclear Waste Policy Act of 1982 (NWPA). In early 1983, the Yucca Mountain was identified as a potentially suitable site for the nation`s first geologic repository for spent reactor fuel and high-level radioactive waste. Later that year, the Nye County Board of County Commissioners (Board) established the capability to monitor the Federal effort to implement the NWPA and evaluate the potential impacts of repository-related activities on Nye County. Over the last eight years, the County`s program has grown in complexity and cost in order to address DOE`s evolving site characterization studies, and prepare for the potential for facility construction and operation. Changes were necessary as well, in response to Congress`s redirection of the repository program specified in the amendments, to the NWPA approved in 1987. In early FY 1991, the County formally established a project office to plan and implement its program of work. The Repository Project Office`s (RPO) mission and functions are provided in Section 2.0. The RPO organization structure is described in Section 3.0.

  15. Uranium, thorium and trace elements in geologic occurrences as analogues of nuclear waste repository conditions

    SciTech Connect (OSTI)

    Wollenberg, H.A.; Brookins, D.G.; Cohen, L.H.; Flexser, S.; Abashian, M.; Murphy, M.; Williams, A.E.

    1984-05-01T23:59:59.000Z

    Contact zones between intrusive rocks and tuff, basalt, salt and granitic rock were investigated as possible analogues of nuclear waste repository conditions. Results of detailed studies of contacts between quartz monzonite of Laramide age, intrusive into Precambrian gneiss, and a Tertiary monzonite-tuff contact zone indicate that uranium, thorium and other trace elements have not migrated significantly from the more radioactive instrusives into the country rock. Similar observations resulted from preliminary investigations of a rhyodacite dike cutting basalt of the Columbia River plateau and a kimberlitic dike cutting bedded salt of the Salina basin. This lack of radionuclide migration occurred in hydrologic and thermal conditions comparable to, or more severe than those expected in nuclear waste repository environments and over time periods of the order of concern for waste repositories. Attention is now directed to investigation of active hydrothermal systems in candidate repository rock types, and in this regard a preliminary set of samples has been obtained from a core hole intersecting basalt underlying the Newberry caldera, Oregon, where temperatures presently range from 100 to 265{sup 0}C. Results of mineralogical and geochemical investigations of this core should indicate the alteration mineralogy and behavior of radioelements in conditions analogous to those in the near field of a repository in basalt.

  16. Evaluation of Five Sedimentary Rocks Other Than Salt for Geologic Repository Siting Purposes

    SciTech Connect (OSTI)

    Croff, A.G.; Lomenick, T.F.; Lowrie, R.S.; Stow, S.H.

    2003-11-15T23:59:59.000Z

    The US Department of Energy (DOE), in order to increase the diversity of rock types under consideration by the geologic disposal program, initiated the Sedimary ROck Program (SERP), whose immediate objectiv eis to evaluate five types of secimdnary rock - sandstone, chalk, carbonate rocks (limestone and dolostone), anhydrock, and shale - to determine the potential for siting a geologic repository. The evaluation of these five rock types, together with the ongoing salt studies, effectively results in the consideration of all types of relatively impermeable sedimentary rock for repository purposes. The results of this evaluation are expressed in terms of a ranking of the five rock types with respect to their potential to serve as a geologic repository host rock. This comparative evaluation was conducted on a non-site-specific basis, by use of generic information together with rock evaluation criteria (RECs) derived from the DOE siting guidelines for geologic repositories (CFR 1984). An information base relevant to rock evaluation using these RECs was developed in hydrology, geochemistry, rock characteristics (rock occurrences, thermal response, rock mechanics), natural resources, and rock dissolution. Evaluation against postclosure and preclosure RECs yielded a ranking of the five subject rocks with respect to their potential as repository host rocks. Shale was determined to be the most preferred of the five rock types, with sandstone a distant second, the carbonate rocks and anhydrock a more distant third, and chalk a relatively close fourth.

  17. Summary of four release consequence analyses for hypothetical nuclear waste repositories in salt and granite

    SciTech Connect (OSTI)

    Cole, C.R.; Bond, F.W.

    1980-12-01T23:59:59.000Z

    Release consequence methology developed under the Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) program has now been applied to four hypothetical repository sites. This paper summarizes the results of these four studies in order to demonstrate that the far-field methodology developed under the AEGIS program offers a practical approach to the post-closure safety assessment of nuclear waste repositories sited in deep continental geologic formations. The four studies are briefly described and compared according to the following general categories: physical description of the repository (size, inventory, emplacement depth); geologic and hydrologic description of the site and the conceptual hydrologic model for the site; description of release scenario; hydrologic model implementation and results; engineered barriers and leach rate modeling; transport model implementation and results; and dose model implementation and results. These studies indicate the following: numerical modeling is a practical approach to post-closure safety assessment analysis for nuclear waste repositories; near-field modeling capability needs improvement to permit assessment of the consequences of human intrusion and pumping well scenarios; engineered barrier systems can be useful in mitigating consequences for postulated release scenarios that short-circuit the geohydrologic system; geohydrologic systems separating a repository from the natural biosphere discharge sites act to mitigate the consequences of postulated breaches in containment; and engineered barriers of types other than the containment or absorptive type may be useful.

  18. Portable data collection device

    DOE Patents [OSTI]

    French, Patrick D. (Aurora, CO)

    1996-01-01T23:59:59.000Z

    The present invention provides a portable data collection device that has a variety of sensors that are interchangeable with a variety of input ports in the device. The various sensors include a data identification feature that provides information to the device regarding the type of physical data produced by each sensor and therefore the type of sensor itself. The data identification feature enables the device to locate the input port where the sensor is connected and self adjust when a sensor is removed or replaced. The device is able to collect physical data, whether or not a function of a time.

  19. Sebastian Collected Issue 1

    E-Print Network [OSTI]

    Sebastian

    2002-01-01T23:59:59.000Z

    .1 F r r r r SEBASTIAN r COLLECTED r 1 r r r [ r r r DOG-HOUSE r PRESS r r r r r V0> P [PI ipi SEBASTIAN COLLECTED 1 DEDICATION As always, to friends past, present and future - with fond memories of blue carbons... exactly how it all started, you know, I'd probably swear blind I waswearing a blue shirt and you'd say it was a green one, that kind of thing. As for how those bloody worry beads come into it, well, thasswayout of my orbit, mate." He was grinning...

  20. Information Collection Management Program

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2006-10-11T23:59:59.000Z

    This Order sets forth DOE requirements and responsibilities for implementing the information collection management provisions of the Paperwork Reduction Act of 1995 and the Office of Management and Budgets implementing regulation Controlling Paperwork Burdens on the Public, as contained in 5 CFR 1320. No cancellation.

  1. Sustainability Bulletin Clothing Collection

    E-Print Network [OSTI]

    Kidd, William S. F.

    Sustainability Bulletin April 2014 #12;Upcoming Clothing Collection March 3-April 14 Hunter Lovins on Wednesday, April 23rd from 11am-2pm brought to you by EAP and the Office of Environmental Sustainability will be in the Campus Center Ballroom to highlight other aspects of well-being such as health, nutrition, sustainability

  2. ROTCH LIBRARY COLLECTIONS

    E-Print Network [OSTI]

    ROTCH LIBRARY QUIET STUDY STUDY CARREL STUDY CARREL FOLIOS QUIET STUDY A-H 6 PAMPHLETS J-NA4999 ARE HERE *RESTROOMS ARE LOCATED OUTSIDE OF LIBRARY 2 QUIET STUDY MICROFICHE/ MICROFILM STUDY CARREL STUDY/Microfilm Pamphlets Public Computers Quiet Study Reference Collection Restrooms - outside of library Rotch Visual

  3. ROTCH LIBRARY COLLECTIONS

    E-Print Network [OSTI]

    ROTCH LIBRARY QUIET STUDY STUDY CARREL STUDY CARREL FOLIOS QUIET STUDY A-H 6 PAMPHLETS J-NA4999 ARE HERE *RESTROOMS ARE LOCATED OUTSIDE OF LIBRARY 2 QUIET STUDY MICROFICHE/ MICROFILM STUDY CARREL STUDY/Microfilm Pamphlets Public Computers Quiet Study Reference Collection Restrooms - outside of library Scanner, Copier

  4. Conceptual model for regional radionuclide transport from a salt dome repository: a technical memorandum

    SciTech Connect (OSTI)

    Kier, R.S.; Showalter, P.A.; Dettinger, M.D.

    1980-05-30T23:59:59.000Z

    Disposal of high-level radioactive wastes is a major environmental problem influencing further development of nuclear energy in this country. Salt domes in the Gulf Coast Basin are being investigated as repository sites. A major concern is geologic and hydrologic stability of candidate domes and potential transport of radionuclides by groundwater to the biosphere prior to their degradation to harmless levels of activity. This report conceptualizes a regional geohydrologic model for transport of radionuclides from a salt dome repository. The model considers transport pathways and the physical and chemical changes that would occur through time prior to the radionuclides reaching the biosphere. Necessary, but unknown inputs to the regional model involve entry and movement of fluids through the repository dome and across the dome-country rock interface and the effect on the dome and surrounding strata of heat generated by the radioactive wastes.

  5. Monitoring the Long-Term Safety Performance of a Repository for Used Nuclear Fuel - 12294

    SciTech Connect (OSTI)

    Villagran, J.E. [Nuclear Waste Management Organization, Toronto (Canada)

    2012-07-01T23:59:59.000Z

    The nuclear waste management programs of several nations include plans for the design, construction and operation of deep geological repositories. Some of these programs have initiated the licensing process for their repository designs. Monitoring strategies and systems are at different levels of development in each program and there is common ground with respect to the ultimate goal of the monitoring function. In this context, the primary functions of a monitoring system are considered to be the verification of safety performance and making available information that may be required for implementation of future decisions such as the timing of repository decommissioning and closure or the possible retrieval of waste containers. This study examines some of the relevant issues and outlines a conceptual monitoring system for further study and development during implementation of Adaptive Phased Management, the method selected by the Government of Canada for long-term management of used nuclear fuel. (author)

  6. Workshop on development of radionuclide getters for the Yucca Mountain waste repository: proceedings.

    SciTech Connect (OSTI)

    Moore, Robert Charles; Lukens, Wayne W. (Lawrence Berkeley National Laboratory)

    2006-03-01T23:59:59.000Z

    The proposed Yucca Mountain repository, located in southern Nevada, is to be the first facility for permanent disposal of spent reactor fuel and high-level radioactive waste in the United States. Total Systems Performance Assessment (TSPA) analysis has indicated that among the major radionuclides contributing to dose are technetium, iodine, and neptunium, all of which are highly mobile in the environment. Containment of these radionuclides within the repository is a priority for the Yucca Mountain Project (YMP). These proceedings review current research and technology efforts for sequestration of the radionuclides with a focus on technetium, iodine, and neptunium. This workshop also covered issues concerning the Yucca Mountain environment and getter characteristics required for potential placement into the repository.

  7. Burnett Collection / Frank Burnett (collector)

    E-Print Network [OSTI]

    Handy, Todd C.

    Burnett Collection / Frank Burnett (collector) Last revised September 2010 University of British;Collection Description Burnett Collection / Frank Burnett (collector). ­ 1927-1944. 6.5 cm of textual records

  8. A postmortem assessment of environmental compliance of a high-level radioactive waste repository, Hanford Site, Washington 

    E-Print Network [OSTI]

    Petrini, Rudolf Harald Wilhelm

    1988-01-01T23:59:59.000Z

    . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Pertinent legislation . Radionuclide concentrations at the accessible environment 74 79 81 84 97 111 111 115 CONCLUSIONS 142 REFERENCES 147 APPENDIX 150 Development of expressions for regulatory Rf and Krt: generic repository . Development... of expressions for regulatory Rf and Ku in presence of matrix diffusion: generic repository . . . . . . . . . . . Development of expressions for regulatory Rf and Kri: Cohasset flow top. . . . . . . . . . . . . . . . . Development of expressions...

  9. Methods of calculating the post-closure performance of high-level waste repositories

    SciTech Connect (OSTI)

    Ross, B. (ed.)

    1989-02-01T23:59:59.000Z

    This report is intended as an overview of post-closure performance assessment methods for high-level radioactive waste repositories and is designed to give the reader a broad sense of the state of the art of this technology. As described here, ''the state of the art'' includes only what has been reported in report, journal, and conference proceedings literature through August 1987. There is a very large literature on the performance of high-level waste repositories. In order to make a review of this breadth manageable, its scope must be carefully defined. The essential principle followed is that only methods of calculating the long-term performance of waste repositories are described. The report is organized to reflect, in a generalized way, the logical order to steps that would be taken in a typical performance assessment. Chapter 2 describes ways of identifying scenarios and estimating their probabilities. Chapter 3 presents models used to determine the physical and chemical environment of a repository, including models of heat transfer, radiation, geochemistry, rock mechanics, brine migration, radiation effects on chemistry, and coupled processes. The next two chapters address the performance of specific barriers to release of radioactivity. Chapter 4 treats engineered barriers, including containers, waste forms, backfills around waste packages, shaft and borehole seals, and repository design features. Chapter 5 discusses natural barriers, including ground water systems and stability of salt formations. The final chapters address optics of general applicability to performance assessment models. Methods of sensitivity and uncertainty analysis are described in Chapter 6, and natural analogues of repositories are treated in Chapter 7. 473 refs., 19 figs., 2 tabs.

  10. Inequality, Coalitions and Collective Action

    E-Print Network [OSTI]

    Bardhan, Pranab; Singh, Nirvikar

    2004-01-01T23:59:59.000Z

    Inequality, Coalitions and Collective Action Pranab K.coalitions) and underlying inequality in the distribution ofO10, P0 Key Words: inequality, self-enforcing, collective

  11. Review of geochemical measurement techniques for a nuclear waste repository in bedded salt

    SciTech Connect (OSTI)

    Knauss, K.G.; Steinborn, T.L.

    1980-05-22T23:59:59.000Z

    A broad, general review is presented of geochemical measurement techniques that can provide data necessary for site selection and repository effectiveness assessment for a radioactive waste repository in bedded salt. The available measurement techniques are organized according to the parameter measured. The list of geochemical parameters include all those measurable geochemical properties of a sample whole values determine the geochemical characteristics or behavior of the system. For each technique, remarks are made pertaining to the operating principles of the measurement instrument and the purpose for which the technique is used. Attention is drawn to areas where further research and development are needed.

  12. Modelling and Numerical Simulation of Gas Migration in a Nuclear Waste Repository

    E-Print Network [OSTI]

    Bourgeat, Alain; Smai, Farid

    2010-01-01T23:59:59.000Z

    We present a compositional compressible two-phase, liquid and gas, flow model for numerical simulations of hydrogen migration in deep geological radioactive waste repository. This model includes capillary effects and the gas diffusivity. The choice of the main variables in this model, Total or Dissolved Hydrogen Mass Concentration and Liquid Pressure, leads to a unique and consistent formulation of the gas phase appearance and disappearance. After introducing this model, we show computational evidences of its adequacy to simulate gas phase appearance and disappearance in different situations typical of underground radioactive waste repository.

  13. Transportation cask decontamination and maintenance at the potential Yucca Mountain repository; Yucca Mountain Site characterization project

    SciTech Connect (OSTI)

    Hartman, D.J.; Miller, D.D. [Bechtel National, Inc., San Francisco, CA (United States); Hill, R.R. [Sandia National Labs., Albuquerque, NM (United States)

    1992-04-01T23:59:59.000Z

    This study investigates spent fuel cask handling experience at existing nuclear facilities to determine appropriate cask decontamination and maintenance operations at the potential Yucca Mountain repository. These operations are categorized as either routine or nonroutine. Routine cask decontamination and maintenance tasks are performed in the cask preparation area at the repository. Casks are taken offline to a separate cask maintenance area for major nonroutine tasks. The study develops conceptual designs of the cask preparation area and cask maintenance area. The functions, layouts, and major features of these areas are also described.

  14. Alternative configurations for the waste-handling building at the Yucca Mountain Repository

    SciTech Connect (OSTI)

    NONE

    1990-08-01T23:59:59.000Z

    Two alternative configurations of the waste-handling building have been developed for the proposed nuclear waste repository in tuff at Yucca Mountain, Nevada. One configuration is based on criteria and assumptions used in Case 2 (no monitored retrievable storage facility, no consolidation), and the other configuration is based on criteria and assumptions used in Case 5 (consolidation at the monitored retrievable storage facility) of the Monitored Retrievable Storage System Study for the Repository. Desirable waste-handling design concepts have been selected and are included in these configurations. For each configuration, general arrangement drawings, plot plans, block flow diagrams, and timeline diagrams are prepared.

  15. HepSim: a repository with predictions for high-energy physics experiments

    E-Print Network [OSTI]

    S. V. Chekanov

    2015-02-06T23:59:59.000Z

    A file repository for calculations of cross sections and kinematic distributions using Monte Carlo generators for high-energy collisions is discussed. The repository is used to facilitate effective preservation and archiving of data from theoretical calculations, as well as for comparisons with experimental data. The HepSim data library is publicly accessible and includes a number of Monte Carlo event samples with Standard Model predictions for current and future experiments. The HepSim project includes a software package to automate the process of downloading and viewing online Monte Carlo event samples. A data streaming over a network for end-user analysis is discussed.

  16. Oil Shale Development from the Perspective of NETL's Unconventional Oil Resource Repository

    SciTech Connect (OSTI)

    Smith, M.W. (REM Engineering Services, Morgantown, WV); Shadle, L.J.; Hill, D. (REM Engineering Services, Morgantown, WV)

    2007-01-01T23:59:59.000Z

    The history of oil shale development was examined by gathering relevant research literature for an Unconventional Oil Resource Repository. This repository contains over 17,000 entries from over 1,000 different sources. The development of oil shale has been hindered by a number of factors. These technical, political, and economic factors have brought about R&D boom-bust cycles. It is not surprising that these cycles are strongly correlated to market crude oil prices. However, it may be possible to influence some of the other factors through a sustained, yet measured, approach to R&D in both the public and private sectors.

  17. HepSim: A Repository with Predictions for High-Energy Physics Experiments

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Chekanov, S. V.

    2015-01-01T23:59:59.000Z

    A file repository for calculations of cross sections and kinematic distributions using Monte Carlo generators for high-energy collisions is discussed. The repository is used to facilitate effective preservation and archiving of data from theoretical calculations and for comparisons with experimental data. The HepSim data library is publicly accessible and includes a number of Monte Carlo event samples with Standard Model predictions for current and future experiments. The HepSim project includes a software package to automate the process of downloading and viewing online Monte Carlo event samples. Data streaming over a network for end-user analysis is discussed.

  18. Collection Description Ephemera Collection 1. Ray Mander personal

    E-Print Network [OSTI]

    Bristol, University of

    info Ephemera Collection 1. Apollo Society 2. Gallery 1st Nighters 3. Unions 4. TMA Ephemera Collection. Apollo 1906 Ephemera Collection 1. Apollo 1907-24 2. Apollo 1925-37 3. Apollo 1938-55 4. Apollo 1956-87 #12;5. Apollo 1988 Ephemera Collection 1. Apollo Victoria & Astoria 2. Arts 1941 3. Arts 1942-51 4

  19. Collective stimulated Brillouin scatter

    E-Print Network [OSTI]

    Alexander O. Korotkevich; Pavel M. Lushnikov; Harvey A. Rose

    2011-05-11T23:59:59.000Z

    We develop a statistical theory of stimulated Brillouin backscatter (BSBS) of a spatially and temporally partially incoherent laser beam for laser fusion relevant plasma. We find a new collective regime of BSBS which has a much larger threshold than the classical threshold of a coherent beam in long-scale-length laser fusion plasma. We identify two contributions to BSBS convective instability increment. The first is collective with intensity threshold independent of the laser correlation time and controlled by diffraction. The second is independent of diffraction, it grows with increase of the correlation time and does not have an intensity threshold. The instability threshold is inside the typical parameter region of National Ignition Facility (NIF). We also find that the bandwidth of KrF-laser-based fusion systems would be large enough to allow additional suppression of BSBS.

  20. Collective network routing

    DOE Patents [OSTI]

    Hoenicke, Dirk

    2014-12-02T23:59:59.000Z

    Disclosed are a unified method and apparatus to classify, route, and process injected data packets into a network so as to belong to a plurality of logical networks, each implementing a specific flow of data on top of a common physical network. The method allows to locally identify collectives of packets for local processing, such as the computation of the sum, difference, maximum, minimum, or other logical operations among the identified packet collective. Packets are injected together with a class-attribute and an opcode attribute. Network routers, employing the described method, use the packet attributes to look-up the class-specific route information from a local route table, which contains the local incoming and outgoing directions as part of the specifically implemented global data flow of the particular virtual network.

  1. Collective Dynamics at RHIC

    E-Print Network [OSTI]

    Aihong Tang

    2007-01-23T23:59:59.000Z

    The property of the ``perfect liquid'' created at RHIC is probed with anisotropic flow measurements. Different initial conditions and their consequences on flow measurements are discussed. The collectivity is shown to be achieved fast and early. The thermalization is investigated with the ratio of $v_4/v_2^2$. Measurements from three sectors of soft physics (HBT, flow and strangeness) are shown to have a simple, linear, length scaling. Directed flow is found to be independent of system size.

  2. Binghamton University Libraries Special Collections

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    Binghamton University Libraries Special Collections The George E. Green Letter Collection, 1900-1916 Finding Aid created 2010 Macarry Pobanz, Student Assistant, Special Collections #12;The George E. Green Letter Collection Biographical note George E. Green was a prominent politician and businessman

  3. Portable liquid collection electrostatic precipitator

    DOE Patents [OSTI]

    Carlson, Duane C.; DeGange, John J.; Halverson, Justin E.

    2005-10-18T23:59:59.000Z

    A portable liquid collection electrostatic collection precipitator for analyzing air is provided which is a relatively small, self-contained device. The device has a tubular collection electrode, a reservoir for a liquid, and a pump. The pump pumps the liquid into the collection electrode such that the liquid flows down the exterior of the collection electrode and is recirculated to the reservoir. An air intake is provided such that air to be analyzed flows through an ionization section to ionize analytes in the air, and then flows near the collection electrode where ionized analytes are collected. A portable power source is connected to the air intake and the collection electrode. Ionizable constituents in the air are ionized, attracted to the collection electrode, and precipitated in the liquid. The precipitator may also have an analyzer for the liquid and may have a transceiver allowing remote operation and data collection.

  4. Rethinking Preservation Validation with the Preserved Object and Repository Risks Ontology (PORRO)

    E-Print Network [OSTI]

    Lalmas, Mounia

    for knowledge manage- ment approaches exhibited by the preservation community in other applications. 2. PORRO information facets to support fully warranted preservation management decisions and conclusions. It makesRethinking Preservation Validation with the Preserved Object and Repository Risks Ontology (PORRO

  5. Limits on the thermal energy release from radioactive wastes in a mined geologic repository

    SciTech Connect (OSTI)

    Scott, J.A.

    1983-03-01T23:59:59.000Z

    The theraml energy release of nuclear wastes is a major factor in the design of geologic repositories. Thermal limits need to be placed on various aspets of the geologic waste disposal system to avoid or retard the degradation of repository performance because of increased temperatures. The thermal limits in current use today are summarized in this report. These limits are placed in a hierarchial structure of thermal criteria consistent with the failure mechanism they are trying to prevent. The thermal criteria hierarchy is used to evaluate the thermal performance of a sample repository design. The design consists of disassembled BWR spent fuel, aged 10 years, close packed in a carbon steel canister with 15 cm of crushed salt backfill. The medium is bedded salt. The most-restrictive temperature for this design is the spent-fuel centerline temperature limit of 300/sup 0/C. A sensitivity study on the effects of additional cooling prior to disposal on repository thermal limits and design is performed.

  6. Numerical methods for the simulation of a corrosion model in a nuclear waste deep repository $

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Numerical methods for the simulation of a corrosion model in a nuclear waste deep repository $ C of the French nuclear waste management agency ANDRA, investigations are conducted to optimize and finalize by the Nuclear Waste Management Agency ANDRA Corresponding author. Phone: +49 30 20372 560, Fax: +49 30 2044975

  7. Mapping A Common Geoscienti c Object Model to Heterogeneous Spatial Data Repositories

    E-Print Network [OSTI]

    Nittel, Silvia

    stored using domain-speci c le format libraries, maps and raster data stored in le-based GIS systemsMapping A Common Geoscienti c Object Model to Heterogeneous Spatial Data Repositories Silvia Nittel Department University of California, Los Angeles University of California, Los Angeles University

  8. The Analytical Repository Source-Term (AREST) model: Description and documentation

    SciTech Connect (OSTI)

    Liebetrau, A.M.; Apted, M.J.; Engel, D.W.; Altenhofen, M.K.; Strachan, D.M.; Reid, C.R.; Windisch, C.F.; Erikson, R.L.; Johnson, K.I.

    1987-10-01T23:59:59.000Z

    The geologic repository system consists of several components, one of which is the engineered barrier system. The engineered barrier system interfaces with natural barriers that constitute the setting of the repository. A model that simulates the releases from the engineered barrier system into the natural barriers of the geosphere, called a source-term model, is an important component of any model for assessing the overall performance of the geologic repository system. The Analytical Repository Source-Term (AREST) model being developed is one such model. This report describes the current state of development of the AREST model and the code in which the model is implemented. The AREST model consists of three component models and five process models that describe the post-emplacement environment of a waste package. All of these components are combined within a probabilistic framework. The component models are a waste package containment (WPC) model that simulates the corrosion and degradation processes which eventually result in waste package containment failure; a waste package release (WPR) model that calculates the rates of radionuclide release from the failed waste package; and an engineered system release (ESR) model that controls the flow of information among all AREST components and process models and combines release output from the WPR model with failure times from the WPC model to produce estimates of total release. 167 refs., 40 figs., 12 tabs.

  9. Knowledge Network: An Information Repository with Services for Managing Concurrent Engineering Design

    E-Print Network [OSTI]

    Fox, Mark S.

    Knowledge Network: An Information Repository with Services for Managing Concurrent Engineering design engineers. The KAD system centers on a knowledge network that stores design knowledge and provides are constructing a Knowledge Aided Design (KAD) system for supporting concurrent engineering design and enhancing

  10. Designing a Secure Storage Repository for Sharing Scientific Datasets using Public Clouds

    E-Print Network [OSTI]

    Prasanna, Viktor K.

    later, or revoking this permission alto- gether. An electricity consumer with a smart power grid utility concern about the associated loss of control over private data hosted in the Cloud. In this paper, we, motivated by the smart power grid domain. Our repository model allows users to securely store and share

  11. Decommissioning and Closure of the Morsleben Deep Geological Repository - The Final Step

    SciTech Connect (OSTI)

    Ripkens, M.; Biurrun, E.

    2002-02-26T23:59:59.000Z

    In Germany, a deep geologic repository for low and intermediate-level waste has been in operation since 1971. This repository, which is located in the territory of former Eastern Germany, became a Federal Facility in the wake of German reunification in 1990. Since then, waste from all of Germany was disposed of until a stop ordered by BfS in 1998. The site is now in the process of being decommissioned and later closed down. This process includes updating the concept for guaranteeing appropriate waste isolation for as long as the waste remains a hazard. During the licensing procedure being currently conducted, in line with German requirements for repository sites, the site operator must provide convincing proof of the facility's long-term safety. Thereafter, implementation of the decommissioning and closure concept will follow. It is estimated that the licensing procedure will take until the year 2006. The decommissioning and closure process itself will require about 10 years. Reliable costs estimates are not yet available. This paper briefly covers the history of the Morsleben radioactive waste repository and provides a draft update on the status of the licensing procedure.

  12. Preconceptual systems and equipment for plugging of man-made accesses to a repository in basalt

    SciTech Connect (OSTI)

    Taylor, C.L.; O'Rourke, J.E.; Allirot, D.; O'Connor, K.

    1980-09-01T23:59:59.000Z

    This report presents results of a study leading to preconceptual designs for plugging boreholes, shafts, and tunnels to a nuclear waste repository in basalt. Beginning design criteria include a list of preferred plug materials and plugging machines that were selected to suit the environmental conditions, and depths, diameters, and orientations of the accesses to a nuclear waste repository in the Columbia River basalts located in eastern Washington State. The environmental conditions are described. The fiscal year 1979-1980 Task II work is presented in two parts: preliminary testing of materials for plugging of man-made accesses to a repository in basalt (described in a separate report); and preconceptual systems and equipment for plugging of man-made accesses to a repository in basalt (described in this report). To fulfill the scope of the Task II work, Woodward-Clyde Consultants (WCC) was requested to: provide preconceptual systems for plugging boreholes, tunnels, and shafts in basalt; describe preconceptual borehole plugging equipment for placing the selected materials in man-made accesses; utilize the quality assurance program, program plan and schedule, and work plans previously developed for Task II; and prepare a preliminary report.

  13. MDA-based Approach for Embedded Software Generation from a UML/MOF Repository

    E-Print Network [OSTI]

    Wagner, Flávio Rech

    MDA-based Approach for Embedded Software Generation from a UML/MOF Repository 1 Francisco A. M. do, following the MDA approach, which is oriented to the design space exploration of embedded systems, based, Languages Keywords Embedded systems design, Design space exploration, UML, MDA. 1. INTRODUCTION Approaches

  14. Ontological Semantics of Standards and PLM Repositories in the Product Development Phase

    E-Print Network [OSTI]

    Schröder, Lutz

    Ontological Semantics of Standards and PLM Repositories in the Product Development Phase Marco the large amounts of engineering information stored in contemporary PLM systems, the concept of knowledge based engineering (KBE) can be considered from a PLM perspective. By eventually combining product

  15. Sequential Thermo-Hydraulic Modeling of Variably Saturated Flow in High-Level Radioactive Waste Repository

    E-Print Network [OSTI]

    Boyer, Edmond

    Sequential Thermo-Hydraulic Modeling of Variably Saturated Flow in High-Level Radioactive Waste-Malabry, France Key words: waste repository, geological disposal, thermo- hydraulic modeling Introduction The most long-lived radioactive wastes must be managed in a safe way for human health and for the environment

  16. Aerosol particle transport modeling for preclosure safety studies of nuclear waste repositories

    SciTech Connect (OSTI)

    Gelbard, F. [Sandia National Labs., Albuquerque, NM (USA)

    1989-01-01T23:59:59.000Z

    An important concern for preclosure safety analysis of a nuclear waste repository is the potential release to the environment of respirable aerosol particles. Such particles, less than 10 {mu}m in aerodynamic diameter, may have significant adverse health effects if inhaled. To assess the potential health effects of these particles, it is not sufficient to determine the mass fraction of respirable aerosol. The chemical composition of the particles is also of importance since different radionuclides may pose vastly different health hazards. Thus, models are needed to determine under normal and accident conditions the particle size and the chemical composition distributions of aerosol particles as a function of time and of position in the repository. In this work a multicomponent sectional aerosol model is used to determine the aerosol particle size and composition distributions in the repository. A range of aerosol mass releases with varying mean particle sizes and chemical compositions is used to demonstrate the sensitivities and uncertainties of the model. Decontamination factors for some locations in the repository are presented. 8 refs., 1 tab.

  17. Meyers DR-1 GSA Data Repository Item for: "Resolving Milankovitchian Controversies

    E-Print Network [OSTI]

    Meyers, Stephen R.

    Meyers DR-1 GSA Data Repository Item for: "Resolving Milankovitchian Controversies: The Triassic Latemar Limestone and the Eocene Green River Formation" Stephen R. Meyers Department of Geological" (Meyers, 2008). Topics addressed here include: (1) an introduction to the ASM methodology, (2) specific

  18. Kraith Collected Issue 1

    E-Print Network [OSTI]

    Lichtenberg, Jacqueline; Multiple Contributors

    1974-01-01T23:59:59.000Z

    very much you have wanted Kraith tc be collected. Now, we may all thank our editors, publishers, and devoted Kraith Creators for making this volume avail~ble. , However, due to the size of the Kraith Series, and due to the fact that the Series isn...'t think that was too cutie-cute . Ruth liked the idea and the convention was establ ished. However, as I fini shed MISSION, L began to realize that it wasn It possible to say izia few words enough to tie down my whole concept of what VUlcans~ .. 1...

  19. Kraith Collected Issue 4

    E-Print Network [OSTI]

    Lichtenberg, Jacqueline; Clark, Beverly

    1974-01-01T23:59:59.000Z

    before I actively began the typing of Volume Three of Kraith Collected, I received notification from Jacqueline that she and Joan Winston were collaborating on a story. Jacqueline said that she had written a story some months llefore, but, on having... co.uld he have ever her if she decided en her o.wn to. co.me?" "Miss Grayso.n, Sarek is a Vulcan." He said it as if it explained everything with to.tal finality. She to.o.k it as if it meant merely that Vulcan integrity was net to. be impugned...

  20. Assessment of Effectiveness of Geologic Isolation Systems: REFERENCE SITE INITIAL ASSESSMENT FOR A SALT DOME REPOSITORY

    SciTech Connect (OSTI)

    Harwell,, M. A.; Brandstetter,, A.; Benson,, G. L.; Bradley,, D. J.; Serne,, R. J.; Soldat, J. K; Cole,, C. R.; Deutsch,, W. J.; Gupta,, S. K.; Harwell,, C. C.; Napier,, B. A.; Reisenauer,, A. E.; Prater,, L. S.; Simmons,, C. S.; Strenge,, D. L.; Washburn,, J. F.; Zellmer,, J. T.

    1982-06-01T23:59:59.000Z

    As a methodology demonstration for the Office of Nuclear Waste Isolation (ONWI), the Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program conducted an initial reference site analysis of the long-term effectiveness of a salt dome repository. The Hainesville Salt Dome in Texas was chosen to be representative of the Gulf Coast interior salt domes; however, the Hainesville Site has been eliminated as a possible nuclear waste repository site. The data used for this exercise are not adequate for an actual assessment, nor have all the parametric analyses been made that would adequately characterize the response of the geosystem surrounding the repository. Additionally, because this was the first exercise of the complete AEGIS and WASTE Rock Interaction Technology (WRIT) methodology, this report provides the initial opportunity for the methodology, specifically applied to a site, to be reviewed by the community outside the AEGIS. The scenario evaluation, as a part of the methodology demonstration, involved consideration of a large variety of potentially disruptive phenomena, which alone or in concert could lead to a breach in a salt dome repository and to a subsequent transport of the radionuclides to the environment. Without waste- and repository-induced effects, no plausible natural geologic events or processes which would compromise the repository integrity could be envisioned over the one-million-year time frame after closure. Near-field (waste- and repository-induced) effects were excluded from consideration in this analysis, but they can be added in future analyses when that methodology development is more complete. The potential for consequential human intrusion into salt domes within a million-year time frame led to the consideration of a solution mining intrusion scenario. The AEGIS staff developed a specific human intrusion scenario at 100 years and 1000 years post-closure, which is one of a whole suite of possible scenarios. This scenario resulted in the delivery of radionuclidecontaminated brine to the surface, where a portion was diverted to culinary salt for direct ingestion by the existing population. Consequence analyses indicated calculated human doses that would be highly deleterious. Additional analyses indicated that doses well above background would occur from such a scenario t even if it occurred a million years into the future. The way to preclude such an intrusion is for continued control over the repository sitet either through direct institutional control or through the effective passive transfer of information. A secondary aspect of the specific human intrusion scenario involved a breach through the side of the salt dome t through which radionuclides migrated via the ground-water system to the accessible environment. This provided a demonstration of the geotransport methodology that AEGIS can use in actual site evaluations, as well as the WRIT program's capabilities with respect to defining the source term and retardation rates of the radionuclides in the repository. This reference site analysis was initially published as a Working Document in December 1979. That version was distributed for a formal peer review by individuals and organizations not involved in its development. The present report represents a revisiont based in part on the responses received from the external reviewers. Summaries of the comments from the reviewers and responses to these comments by the AEGIS staff are presented. The exercise of the AEGIS methodology was successful in demonstrating the methodologyt and thus t in providing a basis for substantive peer review, in terms of further development of the AEGIS site-applications capability and in terms of providing insight into the potential for consequential human intrusion into a salt dome repository.

  1. Assessment of Effectiveness of Geologic Isolation Systems: REFERENCE SITE INITIAL ASSESSMENT FOR A SALT DOME REPOSITORY

    SciTech Connect (OSTI)

    Harwell,, M. A.; Brandstetter,, A.; Benson,, G. L.; Raymond,, J. R.; Brandley,, D. J.; Serne,, R. J.; Soldat,, J. K.; Cole,, C. R.; Deutsch,, W. J.; Gupta,, S. K.; Harwell,, C. C.; Napier,, B. A.; Reisenauer,, A. E.; Prater,, L. S.; Simmons,, C. S.; Strenge,, D. L.; Washburn,, J. F.; Zellmer,, J. T.

    1982-06-01T23:59:59.000Z

    As a methodology demonstration for the Office of Nuclear Waste Isolation (ONWI), the Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program conducted an initial reference site analysis of the long-term effectiveness of a salt dome repository. The Hainesville Salt Dome in Texas was chosen to be representative of the Gulf Coast interior salt domes; however, the Hainesville Site has been eliminated as a possible nuclear waste repository site. The data used for this exercise are not adequate for an actual assessment, nor have all the parametric analyses been made that would adequately characterize the response of the geosystem surrounding the repository. Additionally, because this was the first exercise of the complete AEGIS and WASTE Rock Interaction Technology (WRIT) methodology, this report provides the initial opportunity for the methodology, specifically applied to a site, to be reviewed by the community outside the AEGIS. The scenario evaluation, as a part of the methodology demonstration, involved consideration of a large variety of potentially disruptive phenomena, which alone or in concert could lead to a breach in a salt dome repository and to a subsequent transport of the radionuclides to the environment. Without waste- and repository-induced effects, no plausible natural geologic events or processes which would compromise the repository integrity could be envisioned over the one-million-year time frame after closure. Near-field (waste- and repository-induced) effects were excluded from consideration in this analysis, but they can be added in future analyses when that methodology development is more complete. The potential for consequential human intrusion into salt domes within a million-year time frame led to the consideration of a solution mining intrusion scenario. The AEGIS staff developed a specific human intrusion scenario at 100 years and 1000 years post-closure, which is one of a whole suite of possible scenarios. This scenario resulted in the delivery of radionuclidecontaminated brine to the surface, where a portion was diverted to culinary salt for direct ingestion by the existing population. Consequence analyses indicated calculated human doses that would be highly deleterious. Additional analyses indicated that doses well above background would occur from such a scenario t even if it occurred a million years into the future. The way to preclude such an intrusion is for continued control over the repository sitet either through direct institutional control or through the effective passive transfer of information. A secondary aspect of the specific human intrusion scenario involved a breach through the side of the salt dome t through which radionuclides migrated via the ground-water system to the accessible environment. This provided a demonstration of the geotransport methodology that AEGIS can use in actual site evaluations, as well as the WRIT program's capabilities with respect to defining the source term and retardation rates of the radionuclides in the repository. This reference site analysis was initially published as a Working Document in December 1979. That version was distributed for a formal peer review by individuals and organizations not involved in its development. The present report represents a revisiont based in part on the responses received from the external reviewers. Summaries of the comments from the reviewers and responses to these comments by the AEGIS staff are presented. The exercise of the AEGIS methodology was sUGcessful in demonstrating the methodologyt and thus t in providing a basis for substantive peer review, in terms of further development of the AEGIS site-applications capability and in terms of providing insight into the potential for consequential human intrusion into a salt dome repository.

  2. Projected environmental impacts of radioactive material transportation to the first US repository site

    SciTech Connect (OSTI)

    Neuhauser, K.S.; Cashwell, J.W.; Reardon, P.C.; Ostmeyer, R.M.; McNair, G.W.

    1986-12-31T23:59:59.000Z

    This paper discusses the relative national environmental impacts of transporting nuclear wastes to each of the nine candidate repository sites in the United States. Several of the potential sites are closely clustered and, for the purpose of distance and routing calculations, are treated as a single location. These are: Cypress Creek Dome and Richton Dome in Mississippi (Gulf Interior Region), Deaf Smith County and Swisher County sites in Texas (Permian Basin), and Davis Canyon and Lavender Canyon site in Utah (Paradox Basin). The remaining sites are: Vacherie Dome, Louisiana; Yucca Mountain, Nevada; and Hanford Reservation, Washington. For compatibility with both the repository system authorized by the NWPA and with the MRS option, two separate scenarios were analyzed. In belief, they are (1) shipment of spent fuel and high-level wastes (HLW) directly from waste generators to a repository (Reference Case) and (2) shipment of spent fuel to a Monitored Retrievable Storage (MRS) facility and then to a repository. Between 17 and 38 truck accident fatalities, between 1.4 and 7.7 rail accident fatalities, and between 0.22 and 12 radiological health effects can be expected to occur as a result of radioactive material transportation during the 26-year operating period of the first repository. During the same period in the United States, about 65,000 total deaths from truck accidents and about 32,000 total deaths from rail accidents would occur; also an estimated 58,300 cancer fatalities are predicted to occur in the United States during a 26-year period from exposure to background radiation alone (not including medical and other manmade sources). The risks reported here are upper limits and are small by comparison with the "natural background" of risks of the same type. 3 refs., 6 tabs.

  3. COLLECTIONS Community History Collection/Anacostia Community Museum

    E-Print Network [OSTI]

    Mathis, Wayne N.

    , and other items. Most photographs have positive identification; all have extensive contextual information-Patterson Collection to the museum's permanent collection. The collection of neighborhood and family history materials is comprised of two binders containing approximately 100 photographs, 50 ephemeral materials, letters

  4. Hazard Lewis Farms Collection Binghamton University Libraries

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    Hazard Lewis Farms Collection Binghamton University Libraries Special Collections Hazard Lewis Farms Collection Finding Aid created 2012 Jean Green, Head of Special Collections, Preservation

  5. Funding collection programs

    SciTech Connect (OSTI)

    Walsh, P.; Pferdehirt, W.; O'Leary, P. (Univ. of Wisconsin, Madison, WI (United States). Solid and Hazardous Waste Education Center)

    1993-10-01T23:59:59.000Z

    In principle, paying for waste management services should be easy. Each person should be responsible for paying for his or her share of waste management costs. The price paid should be based on the most equitable, most environmentally sound, and most efficient management method. Everyone knows that life is not that simple. In the real world, decisions about how to pay for waste management services are based upon a variety of factors, including cost, equity, administrative ease, legal restrictions, legislative policies and mandates, historic precedent, and politics. Communities and service providers need to carefully consider these and other factors in developing and implementing a funding approach. This chapter will describe the issues that communities and service providers must address in developing the best strategy for funding waste and recyclable collection programs.

  6. Collective systems for creative expression

    E-Print Network [OSTI]

    Ar?kan, Harun Burak

    2006-01-01T23:59:59.000Z

    This thesis defines collective systems as a unique category of creative expression through the procedures of micro and macro cycles that address the transition from connectivity to collectivity. This thesis discusses the ...

  7. Houghton Library Collection Development Guidelines

    E-Print Network [OSTI]

    Liu, X. Shirley

    astronomy Maps and travel books Donald & Mary Hyde Collection of Dr. Samuel Johnson and Early Modern Books and Manuscripts (1600-1800) The Donald & Mary Hyde Collection of Dr. Samuel Johnson and Early Modern Books fiction Music Samuel Johnson and his circle Houghton collected authors, such as Cervantes, Donne

  8. Collection Management Policy Executive Summary

    E-Print Network [OSTI]

    Levi, Ran

    Collection Development Budget Allocation 1.4 Responsibility for Collection Development within the Library 2 Management 3.1 Locations and Availability of Material 3.1.1 Heavy Demand 3.1.2 Closed access and remote - Collection Maintenance and Evaluation 4.1 De-Selection of Materials #12;4.1.1 Criteria for Retention

  9. Binghamton University Libraries Special Collections

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    Binghamton University Libraries Special Collections The Josiah T. Newcomb Collection Finding Aid begun 1985, Richard Gannon Completed 2011, Jean L. Green, Head of Special Collections and Elizabeth A Science in 1937 at Colorado State College of Education and the Bachelor of Science in Library Science

  10. The Initial Environmental Assessments for the Nuclear Waste Repository under Section 112 of the Nuclear Waste Policy Act

    E-Print Network [OSTI]

    Montange, Charles H.

    1985-01-01T23:59:59.000Z

    NWPA. See note 139 supra. NUCLEAR WASTE ASSESSMENTS cess orof the program. If the Nuclear Waste Policy Act is to work,potentially acceptable for nuclear waste repositories was

  11. Symmetries in collective neutrino oscillations

    E-Print Network [OSTI]

    Huaiyu Duan; George M. Fuller; Yong-Zhong Qian

    2009-07-31T23:59:59.000Z

    We discuss the relationship between a symmetry in the neutrino flavour evolution equations and neutrino flavour oscillations in the collective precession mode. This collective precession mode can give rise to spectral swaps (splits) when conditions can be approximated as homogeneous and isotropic. Multi-angle numerical simulations of supernova neutrino flavour transformation show that when this approximation breaks down, non-collective neutrino oscillation modes decohere kinematically, but the collective precession mode still is expected to stand out. We provide a criterion for significant flavour transformation to occur if neutrinos participate in a collective precession mode. This criterion can be used to understand the suppression of collective neutrino oscillations in anisotropic environments in the presence of a high matter density. This criterion is also useful in understanding the breakdown of the collective precession mode when neutrino densities are small.

  12. Summary report of first and foreign high-level waste repository concepts; Technical report, working draft 001

    SciTech Connect (OSTI)

    Hanke, P.M.

    1987-11-04T23:59:59.000Z

    Reference repository concepts designs adopted by domestic and foreign waste disposal programs are reviewed. Designs fall into three basic categories: deep borehole from the surface; disposal in boreholes drilled from underground excavations; and disposal in horizontal tunnels or drifts. The repository concepts developed in Sweden, Switzerland, Finland, Canada, France, Japan, United Kingdom, Belgium, Italy, Holland, Denmark, West Germany and the United States are described. 140 refs., 315 figs., 19 tabs.

  13. MRS/IS facility co-located with a repository: preconceptual design and life-cycle cost estimates

    SciTech Connect (OSTI)

    Smith, R.I.; Nesbitt, J.F.

    1982-11-01T23:59:59.000Z

    A program is described to examine the various alternatives for monitored retrievable storage (MRS) and interim storage (IS) of spent nuclear fuel, solidified high-level waste (HLW), and transuranic (TRU) waste until appropriate geologic repository/repositories are available. The objectives of this study are: (1) to develop a preconceptual design for an MRS/IS facility that would become the principal surface facility for a deep geologic repository when the repository is opened, (2) to examine various issues such as transportation of wastes, licensing of the facility, and environmental concerns associated with operation of such a facility, and (3) to estimate the life cycle costs of the facility when operated in response to a set of scenarios which define the quantities and types of waste requiring storage in specific time periods, which generally span the years from 1990 until 2016. The life cycle costs estimated in this study include: the capital expenditures for structures, casks and/or drywells, storage areas and pads, and transfer equipment; the cost of staff labor, supplies, and services; and the incremental cost of transporting the waste materials from the site of origin to the MRS/IS facility. Three scenarios are examined to develop estimates of life cycle costs of the MRS/IS facility. In the first scenario, HLW canisters are stored, starting in 1990, until the co-located repository is opened in the year 1998. Additional reprocessing plants and repositories are placed in service at various intervals. In the second scenario, spent fuel is stored, starting in 1990, because the reprocessing plants are delayed in starting operations by 10 years, but no HLW is stored because the repositories open on schedule. In the third scenario, HLW is stored, starting in 1990, because the repositories are delayed 10 years, but the reprocessing plants open on schedule.

  14. Chemistry of Water Collected From an Unventilated Drift, Yucca Mountain, Nevada

    SciTech Connect (OSTI)

    Marshall, Brian D.; Peterman, Zell E. [WRD/YMPB, U.S. Geological Survey, WRD MS 963, Denver Federal Center, Denver, CO, 80225-0046 (United States); Oliver, Thomas A. [WRD/YMPB, S.M. Stoller Corp., c/o U.S. Geological Survey, WRD MS 963, Denver Federal Center, Denver, CO, 80225-0046 (United States)

    2007-07-01T23:59:59.000Z

    Water samples (referred to as puddle water samples) were collected from the surfaces of a conveyor belt and plastic sheeting in the unventilated portion of the Enhanced Characterization of the Repository Block (ECRB) Cross Drift in 2003 and 2005 at Yucca Mountain, Nevada. The chemistry of these puddle water samples is very different than that of pore water samples from borehole cores in the same region of the Cross Drift or than seepage water samples collected from the Exploratory Studies Facility tunnel in 2005. The origin of the puddle water is condensation on surfaces of introduced materials and its chemistry is dominated by components of the introduced materials. Large CO{sub 2} concentrations may be indicative of localized chemical conditions induced by biologic activity. (authors)

  15. Selection and durability of seal materials for a bedded salt repository: preliminary studies

    SciTech Connect (OSTI)

    Roy, D.M.; Grutzeck, M.W.; Wakeley, L.D.

    1983-11-01T23:59:59.000Z

    This report details preliminary results of both experimental and theoretical studies of cementitious seal materials for use in a proposed nuclear waste repository in bedded salt. Effects of changes in bulk composition and environment upon phase stability and physical/mechanical properties have been evaluated for more than 25 formulations. Bonding and interfacial characteristics of the region between host rock and seal material or concrete aggregate and cementitious matrix for selected formulations have been studied. Compatibilities of clays and zeolites in brines typical of the SE New Mexico region have been investigated, and their stabilities reviewed. Results of these studies have led to the conclusion that cementitious materials can be formulated which are compatible with the major rock types in a bedded salt repository environment. Strengths are more than adequate, permeabilities are consistently very low, and elastic moduli generally increase only very slightly with time. Seal formulation guidelines and recommendations for present and future work are presented. 73 references, 25 figures, 61 tables.

  16. RECON: a computer program for analyzing repository economics. Documentation and user's manual

    SciTech Connect (OSTI)

    Clark, L.L.; Cole, B.M.; McNair, G.W.; Schutz, M.E.

    1983-05-01T23:59:59.000Z

    From 1981 through 1983 the Pacific Northwest Laboratory has been developing a computer model named RECON to calculate repository costs from parametric data input. The objective of the program has been to develop the capability to evalute the effect on costs of changes in repository design parameters and operating scenario assumptions. This report documents the development of the model through March of 1983. Included in the report are: (1) descriptions of model development and the underlying equations, assumptions and definitions; (2) descriptions of data input either using card images or an interactive data input program; and (3) detailed listings of the program and definitions of program variables. Cost estimates generated using the model have been verified against independent estimates and good agreement has been obtained.

  17. MRS system study for the repository: Yucca Mountain Site Characterization Project; Volume 2

    SciTech Connect (OSTI)

    Sinagra, T.A. [Bechtel National, Inc., San Francisco, CA (USA); Harig, R. [Parsons, Brinckerhoff, Quade and Douglas, Inc., San Francisco, CA (USA)

    1990-12-01T23:59:59.000Z

    The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM), has initiated a waste management system study to identify the impacts of the presence or absence of a monitored retrievable storage facility (hereinafter referred to as ``MRS``) on system costs and program schedules. To support this study, life-cycle cost estimates and construction schedules have been prepared for the surface and underground facilities and operations geologic nuclear waste repository at Yucca Mountain, Nye County, Nevada. Nine different operating scenarios (cases) have been identified by OCRWM for inclusion in this study. For each case, the following items are determined: the repository design and construction costs, operating costs, closure and decommissioning costs, required staffing, construction schedules, uncertainties associated with the costs and schedules, and shipping cask and disposal container throughputs. This document contains A-D.

  18. Standard guide for characterization of spent nuclear fuel in support of geologic repository disposal

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2009-01-01T23:59:59.000Z

    1.1 This guide provides guidance for the types and extent of testing that would be involved in characterizing the physical and chemical nature of spent nuclear fuel (SNF) in support of its interim storage, transport, and disposal in a geologic repository. This guide applies primarily to commercial light water reactor (LWR) spent fuel and spent fuel from weapons production, although the individual tests/analyses may be used as applicable to other spent fuels such as those from research and test reactors. The testing is designed to provide information that supports the design, safety analysis, and performance assessment of a geologic repository for the ultimate disposal of the SNF. 1.2 The testing described includes characterization of such physical attributes as physical appearance, weight, density, shape/geometry, degree, and type of SNF cladding damage. The testing described also includes the measurement/examination of such chemical attributes as radionuclide content, microstructure, and corrosion product c...

  19. Thermomechanical repository and shaft response analyses using the CAVS (Cracking And Void Strain) jointed rock model: Draft final report

    SciTech Connect (OSTI)

    Dial, B.W.; Maxwell, D.E.

    1986-12-01T23:59:59.000Z

    Numerical studies of the far-field repository and near-field shaft response for a nuclear waste repository in bedded salt have been performed with the STEALTH computer code using the CAVS model for jointed rock. CAVS is a constitutive model that can simulate the slip and dilatancy of fracture planes in a jointed rock mass. The initiation and/or propagation of fractures can also be modeled when stress intensity criteria are met. The CAVS models are based on the joint models proposed with appropriate modifications for numerical simulations. The STEALTH/CAVS model has been previously used to model (1) explosive fracturing of a wellbore, (2) earthquake effects on tunnels in a generic nuclear waste repository, (3) horizontal emplacement for a nuclear waste repository in jointed granite, and (4) tunnel response in jointed rock. The use of CAVS to model far-field repository and near-field shaft response was different from previous approaches because it represented a spatially oriented approach to rock response and failure, rather than the traditional stress invariant formulation for yielding. In addition, CAVS tracked the response of the joint apertures to the time-dependent stress changes in the far-field repository and near-field shaft regions. 28 refs., 21 figs., 11 tabs.

  20. System description of the Repository-Only System for the FY 1990 systems integration program studies. [CONTAINS GLOSSARY

    SciTech Connect (OSTI)

    McKee, R.W.; Young, J.R.; Konzek, G.J.

    1991-07-01T23:59:59.000Z

    This document provides both functional and physical descriptions of a conceptual high-level waste management system defined as a Repository-Only System. Its purpose is to provide a basis for required system computer modeling and system studies initiated in FY 1990 under the Systems Integration Program of the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The Repository-Only System is designed to accept 3000 MTU per year of spent fuel and 400 equivalent MTU per year of high-level wastes disposal in the geologic repository. This document contains both functional descriptions of the processes in the waste management system and physical descriptions of the equipment and facilities necessary for performance of those processes. These descriptions contain the level of detail needed for the projected systems analysis studies. The Repository-Only System contains all system components, from the waste storage facilities of the waste generators to the underground facilities for final disposal of the wastes. The major facilities in the system are the waste generator waste storage facilities, a repository facility that packages the wastes and than emplaces them in the geologic repository, and the transportation equipment and facilities for transporting the wastes between these major facilities. 18 refs., 39 figs.

  1. Concurrent Garbage Collection of Persistent Heaps

    E-Print Network [OSTI]

    Concurrent Garbage Collection of Persistent Heaps Scott Nettles James O'Toole y David Gifford y.S. Government. #12; Keywords: persistence, transaction processing, garbage collection, copying garbage collection, concurrent garbage collection, replication copying garbage collection #12; Abstract We describe

  2. Engineered barrier development for a nuclear waste repository in basalt: an integration of current knowledge

    SciTech Connect (OSTI)

    Smith, M.J.

    1980-05-01T23:59:59.000Z

    This document represents a compilation of data and interpretive studies conducted as part of the engineered barriers program of the Basalt Waste Isolation Project. The overall objective of these studies is to provide information on barrier system designs, emplacement and isolation techniques, and chemical reactions expected in a nuclear waste repository located in the basalts underlying the Hanford Site within the state of Washington. Backfills, waste-basalt interactions, sorption, borehole plugging, etc., are among the topics discussed.

  3. Reyes et al., p. 1 DATA REPOSITORY ITEM FOR: Expansion of alpine glaciers in Pacific North

    E-Print Network [OSTI]

    Barclay, David J.

    Reyes et al., p. 1 DATA REPOSITORY ITEM FOR: Expansion of alpine glaciers in Pacific North America in the first millennium A.D. Site Latitude Longitude (ºN) (ºW) Lillooet Glacier 50º45' 123º46' Bridge Glacier 50º49' 123º29' Miserable Glacier 51°04' 123°52' Tiedemann Glacier 51º21' 124º56' Frank Mackie Glacier

  4. Building Component Library: An Online Repository to Facilitate Building Energy Model Creation; Preprint

    SciTech Connect (OSTI)

    Fleming, K.; Long, N.; Swindler, A.

    2012-05-01T23:59:59.000Z

    This paper describes the Building Component Library (BCL), the U.S. Department of Energy's (DOE) online repository of building components that can be directly used to create energy models. This comprehensive, searchable library consists of components and measures as well as the metadata which describes them. The library is also designed to allow contributors to easily add new components, providing a continuously growing, standardized list of components for users to draw upon.

  5. Expected environments in high-level nuclear waste and spent fuel repositories in salt

    SciTech Connect (OSTI)

    Claiborne, H.C.; Rickertsen, L.D., Graham, R.F.

    1980-08-01T23:59:59.000Z

    The purpose of this report is to describe the expected environments associated with high-level waste (HLW) and spent fuel (SF) repositories in salt formations. These environments include the thermal, fluid, pressure, brine chemistry, and radiation fields predicted for the repository conceptual designs. In this study, it is assumed that the repository will be a room and pillar mine in a rock-salt formation, with the disposal horizon located approx. 2000 ft (610 m) below the surface of the earth. Canistered waste packages containing HLW in a solid matrix or SF elements are emplaced in vertical holes in the floor of the rooms. The emplacement holes are backfilled with crushed salt or other material and sealed at some later time. Sensitivity studies are presented to show the effect of changing the areal heat load, the canister heat load, the barrier material and thickness, ventilation of the storage room, and adding a second row to the emplacement configuration. The calculated thermal environment is used as input for brine migration calculations. The vapor and gas pressure will gradually attain the lithostatic pressure in a sealed repository. In the unlikely event that an emplacement hole will become sealed in relatively early years, the vapor space pressure was calculated for three scenarios (i.e., no hole closure - no backfill, no hole closure - backfill, and hole closure - no backfill). It was assumed that the gas in the system consisted of air and water vapor in equilibrium with brine. A computer code (REPRESS) was developed assuming that these changes occur slowly (equilibrium conditions). The brine chemical environment is outlined in terms of brine chemistry, corrosion, and compositions. The nuclear radiation environment emphasized in this report is the stored energy that can be released as a result of radiation damage or crystal dislocations within crystal lattices.

  6. A Spanish reference concept for a repository in granite -- The role of the barrier system

    SciTech Connect (OSTI)

    Nilsson, L.B.; Sellin, P. [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Huertas, F. [Empresa Nacional de Residuos Radiactivos, S.A., Madrid (Spain); Pusch, R. [Clay Technology, Lund (Sweden)

    1993-12-31T23:59:59.000Z

    ENRESA, the organization responsible for radioactive waste management in Spain, is considering clay, salt and granite as optional host rocks for spent fuel disposal. The main features of a reference repository concept developed for the granite alternative is presented as well as a preliminary assessment of its long-term performance. Comments are given on issues, which should be studied more in depth in the continued R and D program.

  7. Options for treating high-temperature gas-cooled reactor fuel for repository disposal

    SciTech Connect (OSTI)

    Lotts, A.L.; Bond, W.D.; Forsberg, C.W.; Glass, R.W.; Harrington, F.E.; Micheals, G.E.; Notz, K.J.; Wymer, R.G.

    1992-02-01T23:59:59.000Z

    This report describes the options that can reasonably be considered for disposal of high-temperature gas-cooled reactor (HTGR) fuel in a repository. The options include whole-block disposal, disposal with removal of graphite (either mechanically or by burning), and reprocessing of spent fuel to separate the fuel and fission products. The report summarizes what is known about the options without extensively projecting or analyzing actual performance of waste forms in a repository. The report also summarizes the processes involved in convert spent HTGR fuel into the various waste forms and projects relative schedules and costs for deployment of the various options. Fort St. Vrain Reactor fuel, which utilizes highly-enriched {sup 235}U (plus thorium) and is contained in a prismatic graphite block geometry, was used as the baseline for evaluation, but the major conclusions would not be significantly different for low- or medium-enriched {sup 235}U (without thorium) or for the German pebble-bed fuel. Future US HTGRs will be based on the Fort St. Vrain (FSV) fuel form. The whole block appears to be a satisfactory waste form for disposal in a repository and may perform better than light-water reactor (LWR) spent fuel. From the standpoint of process cost and schedule (not considering repository cost or value of fuel that might be recycled), the options are ranked as follows in order of increased cost and longer schedule to perform the option: (1) whole block, (2a) physical separation, (2b) chemical separation, and (3) complete chemical processing.

  8. Quadrupole collective states within the Bohr collective Hamiltonian

    E-Print Network [OSTI]

    L. Prochniak; S. G. Rohozinski

    2009-11-02T23:59:59.000Z

    The article reviews the general version of the Bohr collective model for the description of quadrupole collective states, including a detailed study the model's kinematics. The general form of the classical and quantum Bohr Hamiltonian is presented together with a discussion of the tensor structure of the collective wave functions and with a short review of various methods of solving the Bohr Hamiltonian eigenvalue equation.The methods of derivation of the classical and quantum Bohr Hamiltonian from the microscopic many-body theory are recalled and the microscopic approach to the Bohr Hamiltonian is applied to interpret collective properties of 12 heavy even-even nuclei in the Hf-Hg region.

  9. Region-to-area screening methodology for the Crystalline Repository Project

    SciTech Connect (OSTI)

    none,

    1985-04-01T23:59:59.000Z

    The purpose of this document is to describe the Crystalline Repository Project's (CRP) process for region-to-area screening of exposed and near-surface crystalline rock bodies in the three regions of the conterminous United States where crystalline rock is being evaluated as a potential host for the second nuclear waste repository (i.e., in the North Central, Northeastern, and Southeastern Regions). This document indicates how the US Department of Energy's (DOE) General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories (10 CFR 960) were used to select and apply factors and variables for the region-to-area screening, explains how these factors and variable are to be applied in the region-to-area screening, and indicates how this methodology relates to the decision process leading to the selection of candidate areas. A brief general discussion of the screening process from the national survey through area screening and site recommendation is presented. This discussion sets the scene for detailed discussions which follow concerning the region-to-area screening process, the guidance provided by the DOE Siting Guidelines for establishing disqualifying factors and variables for screening, and application of the disqualifying factors and variables in the screening process. This document is complementary to the regional geologic and environmental characterization reports to be issued in the summer of 1985 as final documents. These reports will contain the geologic and environmental data base that will be used in conjunction with the methodology to conduct region-to-area screening.

  10. Proceedings of a workshop on uses of depleted uranium in storage, transportation and repository facilities

    SciTech Connect (OSTI)

    NONE

    1997-12-31T23:59:59.000Z

    A workshop on the potential uses of depleted uranium (DU) in the repository was organized to coordinate the planning of future activities. The attendees, the original workshop objective and the agenda are provided in Appendices A, B and C. After some opening remarks and discussions, the objectives of the workshop were revised to: (1) exchange information and views on the status of the Department of Energy (DOE) activities related to repository design and planning; (2) exchange information on DU management and planning; (3) identify potential uses of DU in the storage, transportation, and disposal of high-level waste and spent fuel; and (4) define the future activities that would be needed if potential uses were to be further evaluated and developed. This summary of the workshop is intended to be an integrated resource for planning of any future work related to DU use in the repository. The synopsis of the first day`s presentations is provided in Appendix D. Copies of slides from each presenter are presented in Appendix E.

  11. TEMP: A finite line heat transfer code for geologic repositories for nuclear waste

    SciTech Connect (OSTI)

    Wurm, K.J.; Bloom, S.G.; Atterbury, W.G.; Hetteberg, J.R.

    1987-10-01T23:59:59.000Z

    TEMP is a FORTRAN computer code for calculating temperatures in a geologic repository for nuclear waste. It will calculate the incremental temperature contributed by a single heat source, by an infinite array of heat sources, or by heat sources geometrically arranged in a finite array. In the finite array geometry, different types of heat sources can be placed in different regions at different times to more closely approximate the emplacement of waste in a repository. TEMP uses a semi-analytical technique for solving the equation for a heat producing finite length line source in an infinite and isotropic medium. Temperature contributions from individual heat sources are superimposed to determine the temperature at a specific location and time in a repository of multiple heat sources. Thermal conductivity of the geologic medium can be a function of temperature, and, when it is, an approximation is made for the temperature dependence of thermal diffusivity. This report derives the equations solved by TEMP and documents its accuracy by comparing its results to known analytical solutions and to the finite-difference and finite-element heat transfer codes HEATING5, HEATING6, THAC-SIP-3D, SPECTROM-41, and STEALTH-2D. The temperature results from TEMP are shown to be very accurate when compared to the analytical solutions and to the results from the finite-difference and finite-element codes. 8 refs., 97 figs., 39 tabs.

  12. Expected near-field thermal performance for nuclear waste repositories at potential salt sites: Technical report

    SciTech Connect (OSTI)

    McNulty, E.G.

    1987-08-01T23:59:59.000Z

    Thermal analyses were made for the environmental assessments of seven potential salt sites for a nuclear waste repository. These analyses predicted that potential repository sites in domal salts located in the Gulf Coast will experience higher temperature than those in bedded salts of Paradox and Palo Duro Basins, mainly because of higher ambient temperatures at depth. The TEMPV5 code, a semi-analytical heat transfer code for finite line sources, calculated temperatures for commercial high-level waste (CHLW) and spent fuel from pressurized-water reactors (SFPWR). Benchmarks with HEATING6, THAC-SIP-3D, STEALTH, and SPECTROM-41 showed that TEMPV5 agreed closely in the very near field around the waste package and approximately in the near-field and far-field regions of the repository. The analyses used site-specific thermal conductivities that were increased by 40% to compensate for reductions caused by testing technique, salt impurities, and other heterogeneities, and sampling disturbance. Analyses showed peak salt temperatures of 236/sup 0/C (CHLW) and 134/sup 0/C (SFPWR) for the bedded salt and 296/sup 0/C (CHLW) and 180/sup 0/C (SFPWR) for the domal salt. Analyses with uncorrected laboratory thermal conductivities would increase peak salt temperatures by about 120/sup 0/C for CHLW and about 60/sup 0/C for SFPWR. These temperature increases would increase the thermally induced flow of brine and accelerate corrosion of the waste package. 30 refs., 35 figs., 48 tabs.

  13. Collective Hamiltonian for wobbling modes

    E-Print Network [OSTI]

    Q. B. Chen; S. Q. Zhang; P. W. Zhao; J. Meng

    2014-07-14T23:59:59.000Z

    The simple, longitudinal, and transverse wobblers are systematically studied within the framework of collective Hamiltonian, where the collective potential and mass parameter included are obtained based on the tilted axis cranking approach. Solving the collective Hamiltonian by diagonalization, the energies and the wave functions of the wobbling states are obtained. The obtained results are compared with those by harmonic approximation formula and particle rotor model. The wobbling energies calculated by the collective Hamiltonian are closer to the exact solutions by particle rotor model than harmonic approximation formula. It is confirmed that the wobbling frequency increases with the rotational frequency in simple and longitudinal wobbling motions while decreases in transverse wobbling motion. These variation trends are related to the stiffness of the collective potential in the collective Hamiltonian.

  14. Collective Hamiltonian for chiral modes

    E-Print Network [OSTI]

    Q. B. Chen; S. Q. Zhang; P. W. Zhao; R. V. Jolos; J. Meng

    2013-02-23T23:59:59.000Z

    A collective model is proposed to describe the chiral rotation and vibration and applied to a system with one $h_{11/2}$ proton particle and one $h_{11/2}$ neutron hole coupled to a triaxial rigid rotor. The collective Hamiltonian is constructed from the potential energy and mass parameter obtained in the tilted axis cranking approach. By diagonalizing the collective Hamiltonian with a box boundary condition, it is found that for the chiral rotation, the partner states become more degenerate with the increase of the cranking frequency, and for the chiral vibrations, their important roles for the collective excitation are revealed at the beginning of the chiral rotation region.

  15. EM Launches Comprehensive Flickr Collection

    Broader source: Energy.gov [DOE]

    WASHINGTON, D.C. – EM recently established an EM Flickr Collection, which organizes over 1,100 photos from around the EM complex.

  16. Inequality, Coalitions and Collective Action

    E-Print Network [OSTI]

    Bardhan, Pranab; Singh, Nirvikar

    2004-01-01T23:59:59.000Z

    Paper No. E04-339 Inequality, Coalitions and CollectiveSanta Cruz Keywords: inequality, self-enforcing, collectivecoalitions) and underlying inequality in the distribution of

  17. Collective Mind: towards practical and collaborative auto-tuning

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    exploration times, and lack of unified mechanisms for preserving and sharing of optimization knowledge Mind knowledge management system. In contrast with previous cTuning framework, this modular, collaborative knowledge management, public repository of knowledge, NoSQL repository, code and data sharing

  18. WORKSHOP ON DEVELOPMENT OF RADIONUCLIDE GETTERS FOR THE YUCCA MOUNTAIN WASTE REPOSITORY

    SciTech Connect (OSTI)

    K.C. Holt

    2006-03-13T23:59:59.000Z

    One of the important that the U.S. Department of Energy (DOE) is currently undertaking is the development of a high-level nuclear waste repository to be located at Yucca Mountain, Nevada. Concern is generated by the Yucca Mountain Project (YMP) is due to potential releases as groundwater contamination, as described in the Total System Performance Assessment (TSPA). The dose to an off-site individual using this groundwater for drinking and irrigation is dominated by four radionuclides: Tc-99, I-127, Np-237, and U-238. Ideally, this dose would be limited to a single radionuclide, U-238; in other words, YMP would resemble a uranium ore body, a common geologic feature in the Western U.S. For this reason and because of uncertainties in the behavior of Tc-99, I-127, and Np-237, it would be helpful to limit the amount of Tc, I, and Np leaving the repository, which would greatly increase the confidence in the long-term performance of YMP. An approach to limiting the migration of Tc, I, and Np that is complementary to the existing YMP repository design plans is to employ sequestering agents or ''getters'' for these radionuclides such that their migration is greatly hindered, thus decreasing the amount of radionuclide leaving the repository. Development of such getters presents a number of significant challenges. The getter must have a high affinity and high selectivity for the radionuclide in question since there is approximately a 20- to 50-fold excess of other fission products and a 1000-fold excess of uranium in addition to the ions present in the groundwater. An even greater challenge is that the getters must function over a period greater than the half-life of the radionuclide (greater than 5 half-lives would be ideal). Typically, materials with a high affinity for Tc, I, or Np are not sufficiently durable. For example, strong-base ion exchange resins have a very high affinity for TcO{sub 4}{sup -} but are not expected to be durable. On the other hand, durable materials, such as hydrotalcite, do not have sufficient affinity to be useful getters. Despite these problems, the great increase in the repository performance and corresponding decrease in uncertainty promised by a useful getter has generated significant interest in these materials. This report is the result a workshop sponsored by the Office of Civilian Radioactive Waste Management and Office of Science and Technology and International of the DOE to assess the state of research in this field.

  19. Strategic Basis for License Application Planning for a Potential Yucca Mountain Repository

    SciTech Connect (OSTI)

    Newberry, C. M.; Brocoum, S. J.; Gamble, R. P.; Murray, R. C.; Cline, M.

    2002-02-26T23:59:59.000Z

    If Yucca Mountain, Nevada is designated as the site for development of a geologic repository for disposal of spent nuclear fuel and high-level radioactive waste, the Department of Energy (DOE) must obtain Nuclear Regulatory Commission (NRC) approval first for repository construction, then for an operating license, and, eventually, for repository closure and decommissioning. The licensing criteria defined in Code of Federal Regulations, Title 10, Part 63 (10 CFR Part 63) establish the basis for these NRC decisions. Submittal of a license application (LA) to the NRC for authorization to construct a repository at the Yucca Mountain site is, at this point, only a potential future action by the DOE. The policy process defined in the Nuclear Waste Policy Act (NWPA), as amended, for recommendation and designation of Yucca Mountain as a repository site makes it difficult to predict whether or when the site might be designated. The DOE may only submit a LA to the NRC if the site designation takes effect. In spite of this uncertainty, the DOE must take prudent and appropriate action now, and over the next several years, to prepare for development and timely submittal of a LA. This is particularly true given the need for the DOE to develop, load, and certify the operation of its electronic information system to provide access to its relevant records as part of the licensing support network (LSN) in compliance with NRC requirements six months prior to LA submittal. The DOE must also develop a LA, which is a substantially different document from those developed to support a Site Recommendation (SR) decision. The LA must satisfy NRC licensing criteria and content requirements, and address the acceptance criteria defined by the NRC in its forthcoming Yucca Mountain Review Plan (YMRP). The content of the LA must be adequate to facilitate NRC acceptance and docketing for review, and the LA and its supporting documents must provide the documented basis for the NR C findings required for a construction authorization. The LA must also support a licensing proceeding before an Atomic Safety and Licensing Board panel prior to NRC action on any decision to authorize construction. The DOE has established a strategic basis for planning that is intended to provide the framework for development of an integrated plan for activities leading to preparation and submittal of a LA.

  20. Standardized DOE Spent Nuclear Fuel Canister and Transportation System for Shipping to the National Repository

    SciTech Connect (OSTI)

    Pincock, David Lynn; Morton, Dana Keith; Lengyel, Arpad Leslie

    2001-02-01T23:59:59.000Z

    The U.S.Department of Energy’s (DOE) National Spent Nuclear Fuel Program (NSNFP), located at the Idaho National Engineering and Environmental Laboratory (INEEL), has been chartered with the responsibility for developing spent nuclear fuel (SNF) standardized canisters and a transportation cask system for shipping DOE SNF to the national repository. The mandate for this development is outlined in the Memorandum of Agreement for Acceptance of Department of Energy Spent Nuclear Fuel and High-Level Radioactive Waste that states, “EM shall design and fabricate … DOE SNF canisters for shipment to RW.” (1) It also states, “EM shall be responsible for the design, NRC certification, and fabrication of the transportation cask system for DOE SNF canisters or bare DOE SNF in accordance with 10 CFR Part 71.” (2) In fulfillment of these requirements, the NSNFP has developed four SNF standardized canister configurations and has conceptually designed a versatile transportation cask system for shipping the canisters to the national repository.1 The standardized canister sizes were derived from the national repository waste package design for co-disposal of SNF with high-level waste (HLW). One SNF canister can be placed in the center of the waste package or one can be placed in one of five radial positions, replacing a HLW canister. The internal cavity of the transportation cask was derived using the same logic, matching the size of the internal cavity of the waste package. The size of the internal cavity for the transportation cask allows the shipment of multiple canister configurations with the application of a removable basket design. The standardized canisters have been designed to be loaded with DOE SNF, placed into interim storage, shipped to the national repository, and placed in a waste package without having to be reopened. Significant testing has been completed that clearly demonstrates that the standardized canisters can safely achieve their intended design goals. The transportation cask system will include all of the standard design features, with the addition of dual containment for the shipment of failed fuel. The transportation cask system will also meet the rigorous licensing requirements of the Nuclear Regulatory Commission (NRC) to ensure that the design and the methods of fabrication employed will result in a shipping cask that will safely contain the radioactive materials under all credible accident scenarios. The standardization of the SNF canisters and the versatile design of the transportation cask system will eliminate a proliferation of designs and simplify the operations at the user sites and the national repository.

  1. CHAPTER 1. COLLECTIVE PLASMA PHENOMENA 1 Collective Plasma

    E-Print Network [OSTI]

    Callen, James D.

    CHAPTER 1. COLLECTIVE PLASMA PHENOMENA 1 Chapter 1 Collective Plasma Phenomena The properties of a medium are determined by the microscopic processes in it. In a plasma the microscopic processes is actually limited to a distance of order the Debye length in a plasma. On length scales longer than

  2. Guide to the Apollo Collection Compiled by

    E-Print Network [OSTI]

    Alabama in Huntsville, University of

    Guide to the Apollo Collection Compiled by Anne Coleman, Archivist & Vignesh Subbian, Archives to the Apollo Collection Contact Information: Department of Archives/Special Collections M. Louis Salmon Library:http://www.uah.edu/library/about/department/archives.htm Descriptive Summary Title: Apollo Collection Collection number: Special Collections Apollo Collection Creator

  3. Tritium monitor and collection system

    DOE Patents [OSTI]

    Bourne, Gary L. (Idaho Falls, ID); Meikrantz, David H. (Idaho Falls, ID); Ely, Walter E. (Los Alamos, NM); Tuggle, Dale G. (Los Alamos, NM); Grafwallner, Ervin G. (Arco, ID); Wickham, Keith L. (Idaho Falls, ID); Maltrud, Herman R. (Los Alamos, NM); Baker, John D. (Blackfoot, ID)

    1992-01-01T23:59:59.000Z

    This system measures tritium on-line and collects tritium from a flowing inert gas stream. It separates the tritium from other non-hydrogen isotope contaminating gases, whether radioactive or not. The collecting portion of the system is constructed of various zirconium alloys called getters. These alloys adsorb tritium in any of its forms at one temperature and at a higher temperature release it as a gas. The system consists of four on-line getters and heaters, two ion chamber detectors, two collection getters, and two guard getters. When the incoming gas stream is valved through the on-line getters, 99.9% of it is adsorbed and the remainder continues to the guard getter where traces of tritium not collected earlier are adsorbed. The inert gas stream then exits the system to the decay chamber. Once the on-line getter has collected tritium for a predetermined time, it is valved off and the next on-line getter is valved on. Simultaneously, the first getter is heated and a pure helium purge is employed to carry the tritium from the getter. The tritium loaded gas stream is then routed through an ion chamber which measures the tritium activity. The ion chamber effluent passes through a collection getter that readsorbs the tritium and is removable from the system once it is loaded and is then replaced with a clean getter. Prior to removal of the collection getter, the system switches to a parallel collection getter. The effluent from the collection getter passes through a guard getter to remove traces of tritium prior to exiting the system. The tritium loaded collection getter, once removed, is analyzed by liquid scintillation techniques. The entire sequence is under computer control except for the removal and analysis of the collection getter.

  4. Tritium monitor and collection system

    DOE Patents [OSTI]

    Bourne, G.L.; Meikrantz, D.H.; Ely, W.E.; Tuggle, D.G.; Grafwallner, E.G.; Wickham, K.L.; Maltrud, H.R.; Baker, J.D.

    1992-01-14T23:59:59.000Z

    This system measures tritium on-line and collects tritium from a flowing inert gas stream. It separates the tritium from other non-hydrogen isotope contaminating gases, whether radioactive or not. The collecting portion of the system is constructed of various zirconium alloys called getters. These alloys adsorb tritium in any of its forms at one temperature and at a higher temperature release it as a gas. The system consists of four on-line getters and heaters, two ion chamber detectors, two collection getters, and two guard getters. When the incoming gas stream is valved through the on-line getters, 99.9% of it is adsorbed and the remainder continues to the guard getter where traces of tritium not collected earlier are adsorbed. The inert gas stream then exits the system to the decay chamber. Once the on-line getter has collected tritium for a predetermined time, it is valved off and the next on-line getter is valved on. Simultaneously, the first getter is heated and a pure helium purge is employed to carry the tritium from the getter. The tritium loaded gas stream is then routed through an ion chamber which measures the tritium activity. The ion chamber effluent passes through a collection getter that readsorbs the tritium and is removable from the system once it is loaded and is then replaced with a clean getter. Prior to removal of the collection getter, the system switches to a parallel collection getter. The effluent from the collection getter passes through a guard getter to remove traces of tritium prior to exiting the system. The tritium loaded collection getter, once removed, is analyzed by liquid scintillation techniques. The entire sequence is under computer control except for the removal and analysis of the collection getter. 7 figs.

  5. New Directions in Technical Services For Latin American collections: Building unique collections

    E-Print Network [OSTI]

    Harvell, Tony

    2010-01-01T23:59:59.000Z

    Technical Services For Latin American collections: Buildingunique collections Tony Harvell Latin American Studiestransformation • Diminished collections budgets • Increased

  6. Recommendation by the Secretary of Energy Regarding the Suitability of the Yucca Mountain Site for a Repository Under the Nuclear Waste Policy Act of 1982

    Broader source: Energy.gov [DOE]

    Recommendation by the Secretary of Energy Regarding the Suitability of the Yucca Mountain Site for a Repository Under the Nuclear Waste Policy Act of 1982

  7. Multiscale Thermohydrologic Model Analyses of Heterogeneity and Thermal-Loading Factors for the Proposed Repository at Yucca Mountain

    SciTech Connect (OSTI)

    L.G. Glascoe; T.A. Buscheck; J. Gansemer; Y. Sun; K. Lee

    2002-11-11T23:59:59.000Z

    The MultiScale ThermoHydrologic Model (MSTHM) predicts thermohydrologic (TH) conditions in emplacement drifts and the adjoining host rock throughout the proposed nuclear-waste repository at Yucca Mountain. The MSTHM is a computationally efficient approach that accounts for TH processes occurring at a scale of a few tens of centimeters around individual waste packages and emplacement drifts, and for heat flow at the multi-kilometer scale at Yucca Mountain. The modeling effort presented here is an early investigation of the repository and is simulated at a lower temperature mode and with a different panel loading than the repository currently being considered for license application. We present these recent lower temperature mode MSTHM simulations that address the influence of repository-scale thermal-conductivity heterogeneity and the influence of preclosure operational factors affecting thermal-loading conditions. We can now accommodate a complex repository layout with emplacement drifts lying in non-parallel planes using a superposition process that combines results from multiple mountain-scale submodels. This development, along with other improvements to the MSTHM, enables more rigorous analyses of preclosure operational factors. These improvements include the ability to (1) predict TH conditions on a drift-by-drift basis, (2) represent sequential emplacement of waste packages along the drifts, and (3) incorporate distance- and time-dependent heat-removal efficiency associated with drift ventilation. Alternative approaches to addressing repository-scale thermal-conductivity heterogeneity are investigated. We find that only one of the four MSTHM submodel types needs to incorporate thermal-conductivity heterogeneity. For a particular repository design, we find that the most influential parameters are (1) percolation-flux distribution, (2) thermal-conductivity heterogeneity within the host-rock units, (3) the sequencing of waste-package emplacement, and (4) the duration of the preclosure ventilation period.

  8. Methods and Materials Sample Collection

    E-Print Network [OSTI]

    by Greenwood (1958). A 1.5-inch (3.8 em) mesh liner was laced into the cod end to retain small specimens which reported that Alaska pollock \\yas the principal species taken by these Japanese fisheries. However from flatfish samples collected in 1949 were reported by Mosher (1954); the Soviet collections of 1957

  9. Collective neutrino oscillations in supernovae

    SciTech Connect (OSTI)

    Duan, Huaiyu [Department of Physics and Astronomy, University of New Mexico, Albuquerque, NM 87131 (United States)

    2014-06-24T23:59:59.000Z

    In a dense neutrino medium neutrinos can experience collective flavor transformation through the neutrino-neutrino forward scattering. In this talk we present some basic features of collective neutrino flavor transformation in the context in core-collapse supernovae. We also give some qualitative arguments for why and when this interesting phenomenon may occur and how it may affect supernova nucleosynthesis.

  10. Faris Committee Collection / Gordon Selman (collector)

    E-Print Network [OSTI]

    Handy, Todd C.

    Faris Committee Collection / Gordon Selman (collector) Compiled by Erwin Wodarczak (2004) Revised) #12;Collection Description Faris Committee Collection / Gordon Selman (collector). ­ March

  11. Federal Depository Library Program: Services and Collections

    E-Print Network [OSTI]

    Jacobs, James A

    2009-01-01T23:59:59.000Z

    Program: Services and Collections by James A. Jacobs Againstis not centered on collections. ” The Council is suggestingservices instead of collections. With this recommendation,

  12. Sharing Metadata: Building Collections and Communities

    E-Print Network [OSTI]

    Chandler, Robin L.; Westbrook, Bradley D.; Rundblad, Kevin

    2009-01-01T23:59:59.000Z

    Metadata: Building Collections  and Communities Robin afford to think about collections only in  the context of an  institution's collections. Sharing Metadata: Building 

  13. Collective network for computer structures

    DOE Patents [OSTI]

    Blumrich, Matthias A; Coteus, Paul W; Chen, Dong; Gara, Alan; Giampapa, Mark E; Heidelberger, Philip; Hoenicke, Dirk; Takken, Todd E; Steinmacher-Burow, Burkhard D; Vranas, Pavlos M

    2014-01-07T23:59:59.000Z

    A system and method for enabling high-speed, low-latency global collective communications among interconnected processing nodes. The global collective network optimally enables collective reduction operations to be performed during parallel algorithm operations executing in a computer structure having a plurality of the interconnected processing nodes. Router devices are included that interconnect the nodes of the network via links to facilitate performance of low-latency global processing operations at nodes of the virtual network. The global collective network may be configured to provide global barrier and interrupt functionality in asynchronous or synchronized manner. When implemented in a massively-parallel supercomputing structure, the global collective network is physically and logically partitionable according to the needs of a processing algorithm.

  14. Special Collections, General Collections, and Hybrid Conservation Laboratories

    E-Print Network [OSTI]

    Baker, Whitney

    2012-01-01T23:59:59.000Z

    A number of factors determine a conservation laboratory’s design, including the mission of the particular institution, the functions to be carried out in the space, and the collections that will be treated. Some laboratories primarily perform book...

  15. Bentonite alteration due to thermal-hydro-chemical processes during the early thermal period in a nuclear waste repository

    SciTech Connect (OSTI)

    Xu, T.; Senger, R.; Finsterle, S.

    2011-02-01T23:59:59.000Z

    After closure of an underground nuclear waste repository, the decay of radionuclides will raise temperature in the repository, and the bentonite buffer will resaturate by water inflow from the surrounding host rock. The perturbations from these thermal and hydrological processes are expected to dissipate within hundreds to a few thousand years. Here, we investigate coupled thermal-hydro-chemical processes and their effects on the short-term performance of a potential nuclear waste repository located in a clay formation. Using a simplified geometric configuration and abstracted hydraulic parameters of the clayey formation, we examine geochemical processes, coupled with thermo-hydrologic phenomena, and potential changes in porosity near the waste container during the early thermal period. The developed models were used for evaluating the mineral alterations and potential changes in porosity of the buffer, which can affect the repository performance. The results indicate that mineral alteration and associated changes in porosity induced by early thermal and hydrological processes are relatively small and are expected to not significantly affect flow and transport properties. Chlorite precipitation was obtained in all simulation cases. A maximum of one percent volume fraction of chlorite could be formed, whose process may reduce swelling and sorption capacity of bentonite clay, affecting the performance of the repository. llitisation process was not obtained from the present simulations.

  16. Collectibility for Mixed Quantum States

    E-Print Network [OSTI]

    ?ukasz Rudnicki; Zbigniew Pucha?a; Pawe? Horodecki; Karol ?yczkowski

    2012-11-02T23:59:59.000Z

    Bounds analogous to entropic uncertainty relations allow one to design practical tests to detect quantum entanglement by a collective measurement performed on several copies of the state analyzed. This approach, initially worked out for pure states only [Phys. Rev. Lett. 107, 150502 (2011)], is extended here for mixed quantum states. We define collectibility for any mixed states of a multipartite system. Deriving bounds for collectibility for positive partially transposed states of given purity provides a new insight into the structure of entangled quantum states. In case of two qubits the application of complementary measurements and coincidence based detections leads to a new test of entanglement of pseudopure states.

  17. Brane Tilings and Exceptional Collections

    E-Print Network [OSTI]

    Amihay Hanany; Christopher P. Herzog; David Vegh

    2006-04-17T23:59:59.000Z

    Both brane tilings and exceptional collections are useful tools for describing the low energy gauge theory on a stack of D3-branes probing a Calabi-Yau singularity. We provide a dictionary that translates between these two heretofore unconnected languages. Given a brane tiling, we compute an exceptional collection of line bundles associated to the base of the non-compact Calabi-Yau threefold. Given an exceptional collection, we derive the periodic quiver of the gauge theory which is the graph theoretic dual of the brane tiling. Our results give new insight to the construction of quiver theories and their relation to geometry.

  18. CONTACTS FOR INFORMATION MANAGEMENT: Forms, Information Collection...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    CONTACTS FOR INFORMATION MANAGEMENT: Forms, Information Collection, Privacy & Records CONTACTS FOR INFORMATION MANAGEMENT: Forms, Information Collection, Privacy & Records Troy...

  19. Utility Energy Services Contract Data Collection Confidentiality...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Contract Data Collection Confidentiality Statement Utility Energy Services Contract Data Collection Confidentiality Statement Document shows the confidentiality statement for...

  20. Corrosion-induced gas generation in a nuclear waste repository: Reactive geochemistry and multiphase flow effect

    SciTech Connect (OSTI)

    Xu, T.; Senger, R.; Finsterle, S.

    2008-10-15T23:59:59.000Z

    Corrosion of steel canisters, stored in a repository for spent fuel and high-level nuclear wastes, leads to the generation and accumulation of hydrogen gas in the backfilled emplacement tunnels, which may significantly affect long-term repository safety. Previous studies used H{sub 2} generation rates based on the volume of the waste or canister material and the stoichiometry of the corrosion reaction. However, iron corrosion and H{sub 2} generation rates vary with time, depending on factors such as amount of iron, water availability, water contact area, and aqueous and solid chemistry. To account for these factors and feedback mechanisms, we developed a chemistry model related to iron corrosion, coupled with two-phase (liquid and gas) flow phenomena that are driven by gas-pressure buildup associated with H{sub 2} generation and water consumption. Results indicate that by dynamically calculating H{sub 2} generation rates based on a simple model of corrosion chemistry, and by coupling this corrosion reaction with two-phase flow processes, the degree and extent of gas pressure buildup could be much smaller compared to a model that neglects the coupling between flow and reactive transport mechanisms. By considering the feedback of corrosion chemistry, the gas pressure increases initially at the canister, but later decreases and eventually returns to a stabilized pressure that is slightly higher than the background pressure. The current study focuses on corrosion under anaerobic conditions for which the coupled hydrogeochemical model was used to examine the role of selected physical parameters on the H{sub 2} gas generation and corresponding pressure buildup in a nuclear waste repository. The developed model can be applied to evaluate the effect of water and mineral chemistry of the buffer and host rock on the corrosion reaction for future site-specific studies.