National Library of Energy BETA

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

    2008-06-05

    • Metadata • Upload to Repository • Train replacements • Batch Loading • File structure created • Passed to Digital Initiatives The Model Collection • Well Organized • Self-Sufficient • Diverse • Large • Rapidly Growing Video Interview with Jeff Haberl, PhD ...

  2. Phytoremediation of landfill leachate

    SciTech Connect (OSTI)

    Jones, D.L. . E-mail: d.jones@bangor.ac.uk; Williamson, K.L.; Owen, A.G.

    2006-07-01

    Leachate emissions from landfill sites are of concern, primarily due to their toxic impact when released unchecked into the environment, and the potential for landfill sites to generate leachate for many hundreds of years following closure. Consequently, economically and environmentally sustainable disposal options are a priority in waste management. One potential option is the use of soil-plant based remediation schemes. In many cases, using either trees (including short rotation coppice) or grassland, phytoremediation of leachate has been successful. However, there are a significant number of examples where phytoremediation has failed. Typically, this failure can be ascribed to excessive leachate application and poor management due to a fundamental lack of understanding of the plant-soil system. On balance, with careful management, phytoremediation can be viewed as a sustainable, cost effective and environmentally sound option which is capable of treating 250 m{sup 3} ha{sup -1} yr{sup -1}. However, these schemes have a requirement for large land areas and must be capable of responding to changes in leachate quality and quantity, problems of scheme establishment and maintenance, continual environmental monitoring and seasonal patterns of plant growth. Although the fundamental underpinning science is well understood, further work is required to create long-term predictive remediation models, full environmental impact assessments, a complete life-cycle analysis and economic analyses for a wide range of landfill scenarios.

  3. Anaerobic Methane Oxidation in a Landfill-Leachate Plume 

    E-Print Network [OSTI]

    Grossman, E. L.; Cifuentes, L. A.; Cozzarelli, I. M.

    2002-01-01

    The alluvial aquifer adjacent to Norman Landfill, OK, provides an excellent natural laboratory for the study of anaerobic processes impacting landfill-leachate contaminated aquifers. We collected groundwaters from a transect ...

  4. Behavior of Aluminum, Arsenic, and Vanadium during the Neutralization of Red Mud Leachate by HCl, Gypsum, or Seawater

    E-Print Network [OSTI]

    Burke, Ian

    Behavior of Aluminum, Arsenic, and Vanadium during the Neutralization of Red Mud Leachate by HCl ABSTRACT: Red mud leachate (pH 13) collected from Ajka, Hungary is neutralized to via surface adsorption of As onto the Al oxyhydroxides. Gypsum addition to red mud leachate results

  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

    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

  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]

    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

  7. 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.

    1999-09-30

    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.

  8. Analysis Repository

    SciTech Connect (OSTI)

    DOE

    2012-03-16

    The Analysis Repository is a compilation of analyses and analytical models relevant to assessing hydrogen fuel and fuel cell issues. Projects in the repository relate to: hydrogen production, delivery, storage, fuel cells, and hydrogen vehicle technology; hydrogen production feedstock cost and availability; electricity production, central and distributed; energy resource estimation and forecasting.

  9. 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)

    1998-12-31

    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.

  10. Anaerobic Methane Oxidation in a Landfill-Leachate Plume

    E-Print Network [OSTI]

    Grossman, Ethan L.

    Anaerobic Methane Oxidation in a Landfill-Leachate Plume E T H A N L . G R O S S M A N , * , L U I.3 to 11 m that were oriented parallel to the flow path. The center of the leachate plume was characterized of leachate contamination into underlying aquifers. Landfills are the U.S.'s largest anthropogenic source

  11. Repository performance confirmation.

    SciTech Connect (OSTI)

    Hansen, Francis D.

    2011-09-01

    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.

  12. Midland Core Repository

    SciTech Connect (OSTI)

    Tyler, Noel

    2000-08-14

    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.

  13. Repositories Unleashing Data: Ideas 

    E-Print Network [OSTI]

    Ward, Pauline Nathalie

    2015-08-13

    Participants at Repositories Fringe (RepoFringe) 2015 were invited to discuss how new audiences (particularly beyond the academic community) and new uses for data from institutional repositories could be identified and reached. A number of questions...

  14. Leachate concentrations from water leach and column leach tests on fly ash-stabilized soils

    SciTech Connect (OSTI)

    Bin-Shafique, S.; Benson, C.H.; Edil, T.B.; Hwang, K.

    2006-01-15

    Batch water leaching tests (WLTs) and column leaching tests (CLTs) were conducted on coal-combustion fly ashes, soil, and soil-fly ash mixtures to characterize leaching of Cd, Cr, Se, and Ag. The concentrations of these metals were also measured in the field at two sites where soft fine-grained soils were mechanically stabilized with fly ash. Concentrations in leachate from the WLTs on soil-fly ash mixtures are different from those on fly ash alone and cannot be accurately estimated based on linear dilution calculations using concentrations from WLTs on fly ash alone. The concentration varies nonlinearly with fly ash content due to the variation in pH with fly ash content. Leachate concentrations are low when the pH of the leachate or the cation exchange capacity (CEC) of the soil is high. Initial concentrations from CLTs are higher than concentrations from WLTs due to differences in solid-liquid ratio, pH, and solid-liquid contact. However, both exhibit similar trends with fly ash content, leachate pH, and soil properties. Scaling factors can be applied to WLT concentrations (50 for Ag and Cd, 10 for Cr and Se) to estimate initial concentrations for CLTs. Concentrations in leachate collected from the field sites were generally similar or slightly lower than concentrations measured in CLTs on the same materials. Thus, CLTs appear to provide a good indication of conditions that occur in the field provided that the test conditions mimic the field conditions. In addition, initial concentrations in the field can be conservatively estimated from WLT concentrations using the aforementioned scaling factors provided that the pH of the infiltrating water is near neutral.

  15. Alteration of Sediments by Hyperalkaline KRich Cement Leachate: Implications for Strontium Adsorption and Incorporation

    E-Print Network [OSTI]

    Burke, Ian

    Alteration of Sediments by Hyperalkaline KRich Cement Leachate: Implications for Strontium pH cementitious leachate, there is significantly enhanced Sr retention in sediments due to changes

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

    SciTech Connect (OSTI)

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

    2010-07-08

    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.

  17. IRB RESEARCH REPOSITORY COMPLIANCE PROGRAM

    E-Print Network [OSTI]

    Chapman, Michael S.

    to destroy the materials when the specific research project that generates the materials ends. #12;What is not considered a repository. Refer to materials located on our website for additional details on the Repository with the Repository Policy within eIRB: Create a ,,Repository Only submission Create a ,,New Study submission

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

    E-Print Network [OSTI]

    Hazen, Terry

    2002-01-01

    On-Site Disposal Facility Leachate Treatment Final Report,for such a dilute leachate. Monitored Natural AttenuationOn-Site Disposal Facility Leachate Treatment Final Report,

  19. Salt Repository Research,

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

    on Salt Repository Research, Design, and Operation La Fonda Hotel Santa Fe, New Mexico September 7 - 11, 2014 Please join us Sunday September 7, 2014 for a welcome and reception at...

  20. Salt Repository Research,

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

    6 th USGerman Workshop on Salt Repository Research, Design, and Operation Hotel Pullmann Dresden Newa Dresden September 7 - 9, 2015 September 7- Monday 08:00-08:30 Registration...

  1. Repository Performance Confirmation - 12119

    SciTech Connect (OSTI)

    Hansen, F.D. [Sandia National Laboratories, Albuquerque, New Mexico 87185 (United States)

    2012-07-01

    Repository performance confirmation links the technical bases of repository science and societal acceptance. Among the countless aspects of monitoring, performance confirmation holds a special place, involving distinct activities combining technical and social significance in radioactive waste management. Discussion is divided into four themes: 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. Experience from two repository programs in the United States sheds light on how performance confirmation has been executed. Lessons learned can help the next generation of performance confirmation. (author)

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

    SciTech Connect (OSTI)

    R. L. Weiss

    2007-12-05

    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.

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

    SciTech Connect (OSTI)

    R. L. Weiss

    2007-05-30

    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.

  4. Mutagenicity and genotoxicity of coal fly ash water leachate

    SciTech Connect (OSTI)

    Chakraborty, R.; Mukherjee, A.

    2009-03-15

    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.

  5. Supporting Information for: Alteration of Sediments by Hyperalkaline K-Rich Cement Leachate

    E-Print Network [OSTI]

    Burke, Ian

    S1 Supporting Information for: Alteration of Sediments by Hyperalkaline K-Rich Cement Leachate radiolabeled sediments[5]. Fraction Target Phase Leachate Composition Leach Time Porewater Soluble Sr 2

  6. Alteration of Sediments by Hyperalkaline K-Rich Cement Leachate: Implications for Strontium Adsorption and Incorporation

    E-Print Network [OSTI]

    Burke, Ian

    1 Alteration of Sediments by Hyperalkaline K-Rich Cement Leachate: Implications for Strontium that in high pH cementitious leachate there is significantly enhanced Sr retention in sediments due to changes

  7. Experimental and modelling approaches for the assessment of chemical impacts of leachate migration

    E-Print Network [OSTI]

    Sheffield, University of

    Experimental and modelling approaches for the assessment of chemical impacts of leachate migration of landfill leachate migration on groundwater resources are conservative and generalised. Cost are evaluated as a combined approach for assessing the chem'ical impact of leachate migration in the Triassic

  8. Subsurface characterization of groundwater contaminated by landfill leachate using microbial community profile

    E-Print Network [OSTI]

    Vermont, University of

    Subsurface characterization of groundwater contaminated by landfill leachate using microbial in leachate-contaminated groundwater using only microbiological data for input. The data-driven methodology leachate. We modified a self-organizing map (SOM) to weight the input variables by their relative

  9. Characterization of organic phosphorus in leachate from a grassland soil Gurpal S. Toora,*, Leo M. Condronb

    E-Print Network [OSTI]

    Puglisi, Joseph

    Characterization of organic phosphorus in leachate from a grassland soil Gurpal S. Toora,*, Leo M in leachate from a grassland soil carried out over a two year period indicated that the majority of the P loss resonance analysis of a selected leachate sample indicated that unreactive P was mainly comprised

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

    E-Print Network [OSTI]

    Nitrogen removal via nitrite in a sequencing batch reactor treating sanitary landfill leachate, for the automation of a bench-scale SBR treating leachate generated in old landfills. Attention was given confirm the effectiveness of the nitrite route for nitrogen removal optimisation in leachate treatment

  11. Technical Assistance to Ohio Closure Site Technologies to Address Leachate from the On-Site Disposal

    E-Print Network [OSTI]

    Hazen, Terry

    LBNL-51387 Technical Assistance to Ohio Closure Site Technologies to Address Leachate from the On Management Project ­ On-Site Disposal Facility Leachate Treatment Final Report, October 7, 2002 Disclaimer.1.1 Leachate Recirculation (with air injection as an option)........................... 4 3.1.2 Reverse Osmosis

  12. Nucleosynthetic osmium isotope anomalies in acid leachates of the Murchison meteorite

    E-Print Network [OSTI]

    Nucleosynthetic osmium isotope anomalies in acid leachates of the Murchison meteorite L. Reisberg a of the total leachable osmium (weighted average of the leachates) is close to that of bulk chondrites in meteorites in sufficient quantities to influence the Os isotopic compositions of the leachates. Nevertheless

  13. 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 was operated for almost three years in an attempt to optimise the treatment of leachates generated in old and N removal were usually higher than 98% and 90%, respectively, whereas COD (of the leachate) removal

  14. 614 VOLUME 24 NUMBER 6 JUNE 2006 NATURE BIOTECHNOLOGY to concentrate the leachates and whether

    E-Print Network [OSTI]

    614 VOLUME 24 NUMBER 6 JUNE 2006 NATURE BIOTECHNOLOGY to concentrate the leachates and whether the concentrates were analyzed for their leachate composition. Critical for the interpretation of any of the leachates, reproduced in a follow-up publication shows an essential difference with the original, adding

  15. Progress Towards International Repositories

    SciTech Connect (OSTI)

    McCombie, C.; Chapman, N.

    2002-02-27

    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. Metals in Municipal Landfill Leachate And Their Health Effects

    E-Print Network [OSTI]

    Laughlin, Robert B.

    - ally.2 The largest component of municipal solid waste is pa- per, but substantial food waste, yard: The leachate from five municipal land- fills (containing no industrial waste or sewage sludge) was studied, it is not clear A wide variety of wastes from industries, residences, and municipalities have been

  17. 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)

    1995-12-01

    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.

  18. ACCELERATION PHYSICS CODE WEB REPOSITORY.

    SciTech Connect (OSTI)

    WEI, J.

    2006-06-26

    In the framework of the CARE HHH European Network, we have developed a web-based dynamic accelerator-physics code repository. We describe the design, structure and contents of this repository, illustrate its usage, and discuss our future plans, with emphasis on code benchmarking.

  19. Accelerator Physics Code Web Repository

    SciTech Connect (OSTI)

    Zimmermann, F.; Basset, R.; Bellodi, G.; Benedetto, E.; Dorda, U.; Giovannozzi, M.; Papaphilippou, Y.; Pieloni, T.; Ruggiero, F.; Rumolo, G.; Schmidt, F.; Todesco, E.; Zotter, B.W.; Payet, J.; Bartolini, R.; Farvacque, L.; Sen, T.; Chin, Y.H.; Ohmi, K.; Oide, K.; Furman, M.; /LBL, Berkeley /Oak Ridge /Pohang Accelerator Lab. /SLAC /TRIUMF /Tech-X, Boulder /UC, San Diego /Darmstadt, GSI /Rutherford /Brookhaven

    2006-10-24

    In the framework of the CARE HHH European Network, we have developed a web-based dynamic accelerator-physics code repository. We describe the design, structure and contents of this repository, illustrate its usage, and discuss our future plans, with emphasis on code benchmarking.

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

    E-Print Network [OSTI]

    Thomas, Chuck; McDonald, Robert H.

    2007-01-01

    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

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

    SciTech Connect (OSTI)

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

    2011-06-09

    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.

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

    E-Print Network [OSTI]

    Chorover, Jon

    Leachate Chemistry of Field-Weathered Spent Mushroom Substrate Mingxin Guo, Jon Chorover,* Rex reuse. During this field weathering process, leachate percolates into the underlying (Chong and Rinker leaching an SMS­peat column with distilled water at leachate and effects of infiltration. Two SMS piles

  3. Repository Services for Research Data Management 

    E-Print Network [OSTI]

    Uribe, Luis Martinez

    2008-07-31

    Repository Services for Research Data Management - findings from interviews and workshop to capture Oxford researchers' requirements for services to help them manage their data...Presentation given at the Edinburgh Repository Fringe 2008 conference...

  4. The French Geological Repository Project Cigeo - 12023

    SciTech Connect (OSTI)

    Harman, Alain; Labalette, Thibaud; Dupuis, Marie-Claude; Ouzounian, Gerald [ANDRA, Chatenay-Malabry (France)

    2012-07-01

    The French Agency for Radioactive Waste Management, ANDRA, was launched by law in 1991 to perform and develop the research programme for managing high level and intermediate level long-lived radioactive waste generated by the French nuclear fleet. After a 15-year intensive research programme, including the study of alternative solutions, an overall review and assessment of the results was organized, including a national public debate. As a result, the Parliament passed a Planning Act on radioactive waste management in 2006. Commissioning of a geological repository by 2025 was one of the most important decisions taken at that time. To reach this goal, a license application must be submitted and reviewed by the competent authorities by 2015. A detailed review and consultation process is, as well, defined in the Planning Act. Beside the legal framework the project needs to progress on two fronts. The first one is on siting. A significant milestone was reached in 2009 with the definition of a defined area to locate the underground repository facilities. This area was approved in March 2010 by the Government, after having collected the opinions and positions of all the interested parties, at both National and local levels. A new phase of dialogue with local players began to refine the implementation scenarios of surface facilities. The final site selection will be approved after a public debate planned for 2013. The second one is the industrial organization, planning and costing. The industrial project of this geological repository was called Cigeo (Centre Industriel de Stockage Geologique). Given the amount of work to be done to comply with the given time framework, a detailed organization with well-defined milestones must be set-up. Cigeo will be a specific nuclear facility, built and operated underground for over a hundred years. The consequence of this long duration is that the development of the repository facilities will take place in successive operational phases. The characteristics of the first waste packages received will determine the work and the corresponding investments by 2025 on the repository site. One of the main challenges will be to accommodate both activities of mining and nuclear operations at the same time and at the same location. From the technical standpoint, ventilation and fire risk cannot be managed through a simple transposition from current nuclear industry practices. The reversibility demand also leads to concrete proposals with regard to repository management flexibility and waste package retrievability. These proposals contribute to the dialogue with stakeholders to prepare for the public debate and a future law which will determine the reversibility conditions. New design developments are expected to be introduced in the application from the current studies conducted until 2014. The possibility of optimization beyond 2015 will be kept open taking into account the one hundred years operating time as well as the capability to integrate feedback gained from the first construction and operation works. The industrial committed work aims to reach the application stage by 2015. The license application procedure was defined by the 2006 Act. Subject to authorization, the construction might begin in 2017. (authors)

  5. Corrosion testing of spent nuclear fuel performed at Argonne National Laboratory for repository acceptance

    SciTech Connect (OSTI)

    Goldberg, M. M.

    2000-07-20

    Corrosion tests of DOE-owned spent nuclear fuel are performed at Argonne National Laboratory to support the license application for the Yucca Mountain Repository. The tests are designed to determine corrosion rates and degradation products formed when fuel is reacted at elevated temperature in different aqueous environments, including vapor, dripping water, submersion, and liquid film contact. Corrosion rates are determined from the quantity of radionuclides released from wetted fuel and from the weight loss of the test fuel specimen as a function of time. Degradation products include secondary mineral phases and dissolved, adsorbed, and colloidal species. Solid phase examinations determine fuel/mineral interface relationships, characterize radionuclide incorporation into secondary phases, and determine corrosion mechanisms at grain interfaces within the fuel. Leachate solution analyses quantify released radionuclides and determine the size and charge distribution of colloids. This paper presents selected results from corrosion tests on metallic fuels.

  6. Repository operational criteria comparative analysis

    SciTech Connect (OSTI)

    Hageman, J.P.; Chowdhury, A.H. [Southwest Research Inst., San Antonio, TX (United States). Center for Nuclear Waste Regulatory Analyses

    1994-06-01

    The objective of the ``Repository Operational Criteria (ROC) Feasibility Studies`` (or ROC task) was to conduct comprehensive and integrated analyses of repository design, construction, and operations criteria in 10 CFR Part 60 regulations considering the interfaces among the components of the regulations and impacts of any potential changes to those regulations. The ROC task addresses regulatory criteria and uncertainties related to the preclosure aspects of the geologic repository. Those parts of 10 CFR Part 60 that require routine guidance or minor changes to the rule were addressed in Hageman and Chowdhury, 1992. The ROC task shows a possible need for further regulatory clarity, by major changes to the rule, related to the design bases and siting of a geologic repository operations area and radiological emergency planning in order to assure defense-in-depth. The analyses, presented in this report, resulted in the development and refinement of regulatory concepts and their supporting rationale for recommendations for potential major changes to 10 CFR Pan 0 regulations.

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

    E-Print Network [OSTI]

    Mehevec, Adam Wade

    1994-01-01

    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 ...

  8. An Overview of Institutional Repositories

    E-Print Network [OSTI]

    Singarella, Thomas

    2005-02-04

    services to support ?peer review? activities. 3. Enhance the administrative functionality and interface. 4. Provide interoperability with institutional repository systems. (Ehling, 2004) The development of the open source publishing system at Cornell... that could be lost if not placed into a central IR. Historical Perspective A historical perspective is important regarding the evolution and development of an IR in order to understand where we are today. In the early 1990s, primarily within the high-energy...

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

    SciTech Connect (OSTI)

    Steininger, Walter; Hansen, Frank; Biurrun, Enrique; Bollingerfehr, Wilhelm

    2013-07-01

    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)

  10. BioMed Central: Open Repository: Building a hosted repository service on DSpace

    E-Print Network [OSTI]

    Cockerill, Matthew

    2005-07-07

    currently have repositories RCUK policy likely to encourage many smaller institutions to consider setting up repositories High Availability Commercial Tier-1 network datacentre 24x7 monitoring, troubleshooting and fault resolution Fully redundant...

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

    SciTech Connect (OSTI)

    Valentine, G.A.

    1996-09-01

    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.

  12. Handling Change Management using Temporal Active Repositories

    E-Print Network [OSTI]

    Gal, Avigdor

    Handling Change Management using Temporal Active Repositories Avigdor Gal and Opher Etzion and their management. In this paper we introduce an architecture of change man- agement using active temporal repositories. Flexible change management allows the support of information about past or future versions

  13. National Geothermal Data System - DOE Geothermal Data Repository...

    Energy Savers [EERE]

    - DOE Geothermal Data Repository Presentation National Geothermal Data System - DOE Geothermal Data Repository Presentation Overview of the National Geothermal Data System (NGDS)...

  14. 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.

    1983-04-01

    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.

  15. 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

  16. 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 ...

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

    SciTech Connect (OSTI)

    Dole, LR

    2004-12-17

    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.

  18. Evapotranspiration and Leachate Quality of Warm-season Turf and Native Grasses under Different Texas Landscape Climates 

    E-Print Network [OSTI]

    Pannkuk, Timothy Richard

    2012-02-14

    .) landscape crop coefficients (K[subscript L]) for landscapes comprised of different vegetation types, 2.) if regional climatic differences affect K[subscript L], and 3.) examine differences in leachate nutrient concentrations from the plant treatments. The K...

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

    SciTech Connect (OSTI)

    Forsberg, C.; Miller, W.F.

    2013-07-01

    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.

  20. New Yucca Mountain Repository Design to be Simpler, Safer and...

    Office of Environmental Management (EM)

    New Yucca Mountain Repository Design to be Simpler, Safer and More Cost-Effective New Yucca Mountain Repository Design to be Simpler, Safer and More Cost-Effective untitled More...

  1. BUOYANCY FLOW IN FRACTURES INTERSECTING A NUCLEAR WASTE REPOSITORY

    E-Print Network [OSTI]

    Wang, J.S.Y.

    2010-01-01

    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

  2. Non-biodegradable landfill leachate treatment by combined process of agitation, coagulation, SBR and filtration

    SciTech Connect (OSTI)

    Abood, Alkhafaji R. [State Key Laboratory of Biogeology and Environmental Geology, China University of Geosciences, Wuhan 430074 (China); Thi Qar University, Nasiriyah (Iraq); Bao, Jianguo, E-mail: bjianguo888@126.com [State Key Laboratory of Biogeology and Environmental Geology, China University of Geosciences, Wuhan 430074 (China); Du, Jiangkun; Zheng, Dan; Luo, Ye [State Key Laboratory of Biogeology and Environmental Geology, China University of Geosciences, Wuhan 430074 (China)

    2014-02-15

    Highlights: • A novel method of stripping (agitation) was investigated for NH{sub 3}-N removal. • PFS coagulation followed agitation process enhanced the leachate biodegradation. • Nitrification–denitrification achieved by changing operation process in SBR treatment. • A dual filter of carbon-sand is suitable as a polishing treatment of leachate. • Combined treatment success for the complete treatment of non-biodegradable leachate. - Abstract: This study describes the complete treatment of non-biodegradable landfill leachate by combined treatment processes. The processes consist of agitation as a novel stripping method used to overcome the ammonia toxicity regarding aerobic microorganisms. The NH{sub 3}-N removal ratio was 93.9% obtained at pH 11.5 and a gradient velocity (G) 150 s{sup ?1} within a five-hour agitation time. By poly ferric sulphate (PFS) coagulation followed the agitation process; chemical oxygen demand (COD) and biological oxygen demand (BOD{sub 5}) were removed at 70.6% and 49.4%, respectively at an optimum dose of 1200 mg L{sup ?1} at pH 5.0. The biodegradable ratio BOD{sub 5}/COD was improved from 0.18 to 0.31 during pretreatment step by agitation and PFS coagulation. Thereafter, the effluent was diluted with sewage at a different ratio before it was subjected to sequencing batch reactor (SBR) treatment. Up to 93.3% BOD{sub 5}, 95.5% COD and 98.1% NH{sub 3}-N removal were achieved by SBR operated under anoxic–aerobic–anoxic conditions. The filtration process was carried out using sand and carbon as a dual filter media as polishing process. The final effluent concentration of COD, BOD{sub 5}, suspended solid (SS), NH{sub 3}-N and total organic carbon (TOC) were 72.4 mg L{sup ?1}, 22.8 mg L{sup ?1}, 24.2 mg L{sup ?1}, 18.4 mg L{sup ?1} and 50.8 mg L{sup ?1} respectively, which met the discharge standard. The results indicated that a combined process of agitation-coagulation-SBR and filtration effectively eliminated pollutant loading from landfill leachate.

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

    SciTech Connect (OSTI)

    Keane, Christopher M.

    2002-05-28

    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.

  4. National Geoscience Data Repository System. Final report

    SciTech Connect (OSTI)

    Schiffries, C.M.; Milling, M.E.

    1994-03-01

    The American Geological Institute (AGI) has completed the first phase of a study to assess the feasibility of establishing a National Geoscience Data Repository System to capture and preserve valuable geoscientific data. The study was initiated in response to the fact that billions of dollars worth of domestic geological and geophysical data are in jeopardy of being irrevocably lost or destroyed as a consequence of the ongoing downsizing of the US energy and minerals industry. This report focuses on two major issues. First, it documents the types and quantity of data available for contribution to a National Geoscience Data Repository System. Second, it documents the data needs and priorities of potential users of the system. A National Geoscience Data Repository System would serve as an important and valuable source of information for the entire geoscience community for a variety of applications, including environmental protection, water resource management, global change studies, and basic and applied research. The repository system would also contain critical data that would enable domestic energy and minerals companies to expand their exploration and production programs in the United States for improved recovery of domestic oil, gas, and mineral resources.

  5. VISUALIZING ELECTRONIC DOCUMENT REPOSITORIES: DRAWING BOOKS AND

    E-Print Network [OSTI]

    Rauber,Andreas

    ' are not natural selection criteria in their known environment. Even analyzing the provided metadata to #12;nd out ranking criteria, allowing users to quickly identify both the topics covered by the library, the amountVISUALIZING ELECTRONIC DOCUMENT REPOSITORIES: DRAWING BOOKS AND PAPERS IN A DIGITAL LIBRARY Andreas

  6. Fukushima Daiichi Information Repository FY13 Status

    SciTech Connect (OSTI)

    Curtis Smith; Cherie Phelan; Dave Schwieder

    2013-09-01

    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.

  7. UT Repository 1928 3 12 12

    E-Print Network [OSTI]

    Goda, Keisuke

    Repository 770 3,66121,945663939 25 2 1 http://imglib.ioc.u-tokyo.ac.jp/ Web http://www.lib.m.u-tokyo.ac.jp/digital/index.html http://rarebook.dl.itc.u-tokyo.ac.jp/ogai/index.html URL http://www.lib.u-tokyo.ac.jp/koho/guide/coll/index.html 201110281120 2012710 2011710 20107 10 ...12502009710 9 http://www.lib.u-tokyo.ac.jp/ http://www.lib.u-tokyo.ac.jp/tenjikai/index.html

  8. Salt repository project closeout status report

    SciTech Connect (OSTI)

    1988-06-01

    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.

  9. SUBSURFACE REPOSITORY INTEGRATED CONTROL SYSTEM DESIGN

    SciTech Connect (OSTI)

    C.J. Fernado

    1998-09-17

    The purpose of this document is to develop preliminary high-level functional and physical control system architectures for the proposed subsurface repository at Yucca Mountain. This document outlines overall control system concepts that encompass and integrate the many diverse systems being considered for use within the subsurface repository. This document presents integrated design concepts for monitoring and controlling the diverse set of subsurface operations. The subsurface repository design will be composed of a series of diverse systems that will be integrated to accomplish a set of overall functions and objectives. The subsurface repository contains several Instrumentation and Control (I&C) related systems including: waste emplacement systems, ventilation systems, communication systems, radiation monitoring systems, rail transportation systems, ground control monitoring systems, utility monitoring systems (electrical, lighting, water, compressed air, etc.), fire detection and protection systems, retrieval systems, and performance confirmation systems. Each of these systems involve some level of I&C and will typically be integrated over a data communication network. The subsurface I&C systems will also integrate with multiple surface-based site-wide systems such as emergency response, health physics, security and safeguards, communications, utilities and others. The scope and primary objectives of this analysis are to: (1) Identify preliminary system level functions and interface needs (Presented in the functional diagrams in Section 7.2). (2) Examine the overall system complexity and determine how and on what levels these control systems will be controlled and integrated (Presented in Section 7.2). (3) Develop a preliminary subsurface facility-wide design for an overall control system architecture, and depict this design by a series of control system functional block diagrams (Presented in Section 7.2). (4) Develop a series of physical architectures that present preliminary concepts for integrating the diverse set of control systems to be used within the subsurface repository facility (Presented in Section 7.3). (5) Develop initial concepts for an overall subsurface data communication system that can be used to integrate critical and data-intensive control systems (Presented in Section 7.4). (6) Discuss technology trends and control system design issues (Presented in Section 7.5).

  10. Status of Proposed Repository for Latin-American Spent Fuel

    SciTech Connect (OSTI)

    Ferrada, J.J.

    2004-10-04

    This report compiles preliminary information that supports the premise that a repository is needed in Latin America and analyzes the nuclear situation (mainly in Argentina and Brazil) in terms of nuclear capabilities, inventories, and regional spent-fuel repositories. The report is based on several sources and summarizes (1) the nuclear capabilities in Latin America and establishes the framework for the need of a permanent repository, (2) the International Atomic Energy Agency (IAEA) approach for a regional spent-fuel repository and describes the support that international institutions are lending to this issue, (3) the current situation in Argentina in order to analyze the Argentinean willingness to find a location for a deep geological repository, and (4) the issues involved in selecting a location for the repository and identifies a potential location. This report then draws conclusions based on an analysis of this information. The focus of this report is mainly on spent fuel and does not elaborate on other radiological waste sources.

  11. Selection of Corrosion Resistant Materials for Nuclear Waste Repositories

    SciTech Connect (OSTI)

    R.B. Rebak

    2006-08-28

    Several countries are considering geological repositories to dispose of nuclear waste. The environment of most of the currently considered repositories will be reducing in nature, except for the repository in the US, which is going to be oxidizing. For the reducing repositories, alloys such as carbon steel, stainless steels and titanium are being evaluated. For the repository in the US, some of the most corrosion resistant commercially available alloys are being investigated. This paper presents a summary of the behavior of the different materials under consideration for the repositories and the current understanding of the degradation modes of the proposed alloys in ground water environments from the point of view of general corrosion, localized corrosion and environmentally assisted cracking.

  12. 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

    2008-01-01

    hydrothermomechanical design of nuclear waste repositories.Associated with Nuclear Waste Repositories, Academic Press,safety of a hypothetical nuclear waste repository – BMT1 of

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

    E-Print Network [OSTI]

    Rutqvist, J.

    2008-01-01

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

  14. DOE Geothermal Data Repository: Getting More Mileage Out of Your...

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

    (b) Keywords: GDR, NGDS, geothermal, data, repository, information, node, DOE, OSTI, Data.gov, metadata, license, submissions ABSTRACT All data submitted to the U.S....

  15. Denys Poshyvanyk CSci 780: Mining Software Repositories CSci 780: Mining Software Repositories

    E-Print Network [OSTI]

    Poshyvanyk, Denys

    Denys Poshyvanyk CSci 780: Mining Software Repositories 1 CSci 780: Mining:50pm Location: McGlothlin-Street Hall 002 Instructor: Denys Poshyvanyk Office Hours: MW, 11:30am-1pm Office: McGlothlin-Street Hall, 006 Email: denys [at-sign] cs

  16. 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)

    2013-07-01

    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)

  17. A Repository of Codes of Ethics and Technical Standards in Health Informatics A Repository of Codes of Ethics and Technical Standards in Health

    E-Print Network [OSTI]

    Zaiane, Osmar R.

    A Repository of Codes of Ethics and Technical Standards in Health Informatics 1 A Repository of Codes of Ethics and Technical Standards in Health Informatics Hamman W. Samuel1 , Osmar R. Zaïane1 1 ethics repository. Keywords: health informatics ethics, repository, codes of ethics, technical standards

  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; Vandergaast, Gary; LaMonica, David

    2013-07-01

    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

    1979-01-01

    and Phenotypic Correlations of Seed Traits LITERATURE CITED APPENDIX. 55 57 61 65 VITA 78 LIST OF TABLES TABLE PAGE Harvest dates and meterological data. Model for analyses of variance within generations Model for analyses of variance within... 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...

  20. Evaluating Simple Repository Deposit for Open Educational Resources

    E-Print Network [OSTI]

    Giles, C. Lee

    Evaluating Simple Repository Deposit for Open Educational Resources Morwan Mohamed Nour, Kyle software tools have been identified as drivers for the Open Educational Resources (OER) move- ment. However resources, repository, deposit, desktop 1 Introduction Open Educational Resources (OER) are digital objects

  1. A Change Impact Analysis Approach for Workflow Repository Management

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    A Change Impact Analysis Approach for Workflow Repository Management Gustavo A. Oliva* , Marco A dependency-centric change impact analysis approach for workflow repository management. The approach relies that ranged from 11 (+10%) to 35 (+250%). Keywords--change impact analysis; dependency management; workflow

  2. Genre Taxonomy: A Knowledge Repository of Communicative Actions

    E-Print Network [OSTI]

    Genre Taxonomy: A Knowledge Repository of Communicative Actions Takeshi Yoshioka1 Center taxonomy as a knowledge repository of communicative structures or "typified actions" enacted by organizational members. The Genre taxonomy aims at helping people to make sense of diverse types of communicative

  3. A Framework for Describing Web Repositories Frank McCown

    E-Print Network [OSTI]

    Nelson, Michael L.

    , dark and grey web repos- itories; and states of recoverability (vulnerable, replicated, endangeredA Framework for Describing Web Repositories Frank McCown Department of Computer Science Harding to "lazily preserve" websites and re- construct them when they are lost. We use the term "web repositories

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

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Proceedings of 3rd USGerman Workshop on Salt Repository Research, Design, and Operation Proceedings of 3rd USGerman Workshop on Salt Repository Research, Design, and Operation...

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

    E-Print Network [OSTI]

    Xu, T.

    2009-01-01

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

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

    E-Print Network [OSTI]

    Xu, Tianfu; Senger, Rainer; Finstele, Stefan

    2008-01-01

    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

  7. 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.

    2011-09-20

    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.

  8. Collection understanding 

    E-Print Network [OSTI]

    Chang, Michelle T.

    2004-09-30

    Ambient Displays.........................................................................................................16 Informative Art.........................................................................................................16... Visualizations for Collection Understanding ...............................................................27 Using Streaming Collage for Collection Understanding..........................................28 Using an Ambient Slideshow for Collection...

  9. Standard practice for analysis of aqueous leachates from nuclear waste materials using inductively coupled plasma-atomic emission spectrometry

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This practice is applicable to the determination of low concentration and trace elements in aqueous leachate solutions produced by the leaching of nuclear waste materials, using inductively coupled plasma-atomic emission spectroscopy (ICP-AES). 1.2 The nuclear waste material may be a simulated (non-radioactive) solid waste form or an actual solid radioactive waste material. 1.3 The leachate may be deionized water or any natural or simulated leachate solution containing less than 1 % total dissolved solids. 1.4 This practice should be used by analysts experienced in the use of ICP-AES, the interpretation of spectral and non-spectral interferences, and procedures for their correction. 1.5 No detailed operating instructions are provided because of differences among various makes and models of suitable ICP-AES instruments. Instead, the analyst shall follow the instructions provided by the manufacturer of the particular instrument. This test method does not address comparative accuracy of different devices...

  10. 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 ...

  11. Viability Assessment of a Repository at Yucca Mountain

    Broader source: Energy.gov [DOE]

    The Viability Assessment of a Repository at Yucca Mountain describes the nuclear waste problem and explains why the United States and other nations are considering deep geologic disposal as the solution.

  12. Drift Natural Convection and Seepage at the Yucca Mountain Repository

    E-Print Network [OSTI]

    Halecky, Nicholaus Eugene

    2010-01-01

    2 A Simulation Code for Yucca Mountain Transport Processes:List of Figures Yucca Mountain location, southwest1 Introduction 1.1 Yucca Mountain Repository . . . . 1.1.1

  13. The National Repository at Yucca Mountain, Russ Dyer

    Office of Environmental Management (EM)

    of Energy submitted an application to the U.S. Nuclear Regulatory Commission for a license to construct a repository at Yucca Mountain 3 SBBB-GeneralBriefing070808Rev1.ppt...

  14. 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.

  15. National Geoscience Data Repository System, Phase III: Implementation and operation of the repository

    SciTech Connect (OSTI)

    American Geological Institute

    2000-03-13

    The American Geological Institute's (AGI) National Geoscience Data Repository System (NGDRS) was initiated in response to the fact that billions of dollars worth of domestic geoscience data are in jeopardy of being irrevocably lost or destroyed as a consequence of the ongoing downsizing of the U.S. energy and minerals industry. Preservation and access to domestic geological and geophysical data are critical to the energy security and economic prosperity of the nation. There is a narrow window of opportunity to act before valuable data are destroyed. The data truly represent a national treasure and immediate steps must be taken to assure their preservation.

  16. Effect of landfill leachate organic acids on trace metal adsorption by kaolinite

    SciTech Connect (OSTI)

    Schroth, B.; Garrison, Sposito

    1997-02-01

    Hexanoic (hex) and fulvic acid (FA), representing early and later stages of landfill leachate evolution, were examined for influence on trace metal adsorption by a poorly crystallized kaolinite (KGa-2). Our experiments represented a model approach to examine possible reaction mechanisms in an environmentally important ternary metal-ligand-mineral surface system. Batch experiments were conducted in 0.01 mol kg(-1) NaClO4 at pH 3-8. Concentrations of metals (Cu, Cd, and Pb) and ligands were representative of those found typically in groundwater immediately downgradient of a landfill. The presence of FA resulted in enhancement of metal adsorption below pH 5, whereas the presence of hex produced no significant net change in metal uptake. Measured surface charge properties of KGa-2 were combined with binary and ternary system data in constructing a quantitative model of the system. The simple combination of binary system results was not effective in predicting the observed ternary system behavior. In both ternary systems, the addition of ternary surface complexes (TSCs) to the models resulted in a satisfactory fit to the data. Our work suggests the strong possibility that TSC involvement in surface reactions of natural adsorbents may be a useful concept.

  17. Nucleosynthetic osmium isotope anomalies in acid leachates of the Murchison meteorite

    E-Print Network [OSTI]

    L. Reisberg; N. Dauphas; A. Luguet; D. G. Pearson; R. Gallino; C. Zimmermann

    2008-12-15

    We present osmium isotopic results obtained by sequential leaching of the Murchison meteorite, which reveal the existence of very large internal anomalies of nucleosynthetic origin. The Os isotopic anomalies are correlated, and can be explained by the variable contributions of components derived from the s, r and p-processes of nucleosynthesis. Much of the s-process rich osmium is released by relatively mild leaching, suggesting the existence of an easily leachable s-process rich presolar phase, or alternatively, of a chemically resistant r-process rich phase. The s-process composition of Os released by mild leaching diverges slightly from that released by aggressive digestion techniques, perhaps suggesting that the presolar phases attacked by these differing procedures condensed in different stellar environments. The correlation between 190Os and 188Os can be used to constrain the s-process 190Os/188Os ratio to be 1.275 pm 0.043. Such a ratio can be reproduced in a nuclear reaction network for a MACS value for 190Os of ~200 pm 22 mbarn at 30 keV. We also present evidence for extensive internal variation of 184Os abundances in the Murchison meteorite. This suggests that p process rich presolar grains (e.g., supernova condensates) may be present in meteorites in sufficient quantities to influence the Os isotopic compositions of the leachates.

  18. Characteristics of potential repository wastes. Volume 2

    SciTech Connect (OSTI)

    Not Available

    1992-07-01

    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.

  19. LIFE Materials: Fuel Cycle and Repository Volume 11

    SciTech Connect (OSTI)

    Shaw, H; Blink, J A

    2008-12-12

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

    E-Print Network [OSTI]

    2006-01-01

    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

  1. Khazar Iodine Production Plant Site Remediation in Turkmenistan. NORM Contaminated Waste Repository Establishment - 12398

    SciTech Connect (OSTI)

    Gelbutovskiy, Alexander B.; Cheremisin, Peter I.; Troshev, Alexander V.; Egorov, Alexander J.; Boriskin, Mikhail M.; Bogod, Mikhail A. [JSC 'ECOMET-S', Sosnoviy Bor, Leningrad region, 188540 (Russian Federation)

    2012-07-01

    Radiation safety provisions for NORM contaminated areas are in use in a number of the former Soviet republics. Some of these areas were formed by absorbed radionuclides at the iodine and bromine extraction sites. As a rule, there are not any plant radiation monitoring systems nor appropriate services to ensure personnel, population and environmental radiation safety. The most hazardous sites are those which are situated in the Caspian Sea coastal zone. The bulk of the accumulated waste is represented by a loose mixture of sand and charcoal, which was basically used as the iodine extraction sorbent. The amounts of these wastes were estimated to be approximately 20,000 metric tons. The waste contamination is mainly composed of Ra-226 (U-238 decay series) and Ra-224, Ra-228 (Th-232 decay series). In 2009, the 'ECOMET-S', a Closed Joint-Stock Company from St. Petersburg, Russian Federation, was authorized by the Turkmenistan government to launch the rehabilitation project. The project includes D and D activities, contaminated areas remediation, collected wastes safe transportation to the repository and its disposal following repository closure. The work at the Khazar chemical plant started in September, 2010. Comprehensive radiological surveys to estimate the waste quantities were carried out in advance. In course of the rehabilitation work at the site of the Khazar chemical plant additional waste quantities (5,000 MT, 10,000 m{sup 3}) were discovered after the sludge was dumped and drained. Disposal volumes for this waste was not provided initially. The additional volume of the construction wastes was required in order to accommodate all the waste to be disposed. For the larger disposal volume the project design enterprise VNIPIET, offered to erect a second wall outside the existing one and this solution was adopted. As of May, 2011, 40,575 m{sup 3} of contaminated waste were collected and disposed safely. This volume represents 96.6% of the initial repository volume. Now work is underway to erect the second repository wall, which will allow housing of the additional 16,800 m{sup 3} The Khazar chemical plant territory restoration work is underway as well. (authors)

  2. IMPLEMENTATION AND OPERATION OF THE REPOSITORY

    SciTech Connect (OSTI)

    Marcus Milling

    2003-10-01

    The NGDRS has facilitated 85% of cores, cuttings, and other data identified available for transfer to the public sector. Over 12 million linear feet of cores and cuttings, in addition to large numbers of paleontological samples and are now available for public use. To date, with industry contributions for program operations and data transfers, the NGDRS project has realized a 6.5 to 1 return on investment to Department of Energy funds. Large-scale transfers of seismic data have been evaluated, but based on the recommendation of the NGDRS steering committee, cores have been given priority because of the vast scale of the seismic data problem relative to the available funding. The rapidly changing industry conditions have required that the primary core and cuttings preservation strategy evolve as well. Additionally, the NGDRS clearinghouse is evaluating the viability of transferring seismic data covering the western shelf of the Florida Gulf Coast. AGI remains actively involved in working to realize the vision of the National Research Council's report of geoscience data preservation. GeoTrek has been ported to Linux and MySQL, ensuring a purely open-source version of the software. This effort is key in ensuring long-term viability of the software so that is can continue basic operation regardless of specific funding levels. Work has been on a major revision of GeoTrek, using the open-source MapServer project and its related MapScript language. This effort will address a number of key technology issues that appear to be rising for 2003, including the discontinuation of the use of Java in future Microsoft operating systems. The recent donation of BPAmoco's Houston core facility to the Texas Bureau of Economic Geology has provided substantial short-term relief of the space constraints for public repository space.

  3. In-Situ Bioremediation of Perchlorate in Groundwater and Soil

    E-Print Network [OSTI]

    Jin, Liyan

    2012-01-01

    2.24 Perchlorate in the leachate from different batch modeto drain. Collected leachate was analyzed for perchlorate,collected in the leachate, little or no perchlorate

  4. Damage to HDPE geomembrane from interface shear over gravelly compacted clay liner

    E-Print Network [OSTI]

    Thielmann, Stuart

    2012-01-01

    high-density polyethylene leachate collection and removalthe following requirements: leachate collection and removalLCRS) limiting the head of leachate on the liner system to

  5. 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

  6. 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)

    2012-07-01

    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)

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

    SciTech Connect (OSTI)

    Mariner, Paul E.; Hardin, Ernest L.; Miksova, Jitka

    2013-02-01

    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.

  8. Code requirements for concrete repository and processing facilities

    SciTech Connect (OSTI)

    Hookham, C.J. [Black & Veatch, Ann Arbor, MI (United States); Palaniswamy, R. [Bechtel Savannah River, Inc., North Augusta, SC (United States)

    1993-04-01

    The design and construction of facilities and structures for the processing and safe long-term storage of low- and high-level radioactive wastes will likely employ structural concrete. This concrete will be used for many purposes including structural support, shielding, and environmental protection. At the present time, there are no design costs, standards or guidelines for repositories, waste containers, or processing facilities. Recently, the design and construction guidelines contained in American Concrete Institute (ACI), Code Requirements for Nuclear Safety Related Concrete Structures (ACI 349), have been cited for low-level waste (LLW) repositories. Conceptual design of various high-level (HLW) repository surface structures have also cited the ACI 349 Code. However, the present Code was developed for nuclear power generating facilities and its application to radioactive waste repositories was not intended. For low and medium level radioactive wastes, concrete has a greater role and use in processing facilities, engineered barriers, and repository structures. Because of varied uses and performance/safety requirements this review of the current ACI 349 Code document was required to accommodate these special classes of structures.

  9. 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.

    2008-01-01

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

  10. 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)

    2013-07-01

    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)

  11. The Proposed Yucca Mountain Repository From A Corrosion Perspective

    SciTech Connect (OSTI)

    J.H. Payer

    2005-03-10

    Corrosion is a primary determinant of waste package performance at the proposed Yucca Mountain Repository and will control the delay time for radionuclide transport from the waste package. Corrosion is the most probable and most likely degradation process that will determine when packages will be penetrated and the shape size and distribution of those penetrations. The general issues in corrosion science, materials science and electrochemistry are well defined, and the knowledge base is substantial for understanding corrosion processes. In this paper, the Yucca Mountain Repository is viewed from a corrosion perspective.

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

    E-Print Network [OSTI]

    Smith, MacKenzie

    2002-01-01

    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, ...

  13. ANU Library | anulib.anu.edu.au October 2013 ANU Print Repository request service

    E-Print Network [OSTI]

    Journals, books and pamphlets held in the ANU Print Repository are available for loan in accordance and pamphlets held in the ANU Print Repository may be requested. The copyright declaration must be completed

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

    E-Print Network [OSTI]

    Hwang, Kai

    Designing a Secure Storage Repository for Sharing Scientific Datasets using Public Clouds Alok present an architecture for a secure data repository service designed on top of a public Cloud and Protection General Terms Public Clouds, Secure Cloud Storage, Access Control, Data Repository, eEngineering 1

  15. 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

  16. Impact of Pyrophoric Events on Long-Term Repository Performance

    SciTech Connect (OSTI)

    Richard Gregg

    2005-09-01

    This paper provides an overview of a feature, event, and process (FEP) screening argument developed for the issue of pyrophoricity as it pertains to the post-closure interment of Department of Energy (DOE) spent nuclear fuel (DSNF) at the Yucca Mountain Repository.

  17. Identifying Cross-Cutting Concerns Using Software Repository Mining

    E-Print Network [OSTI]

    Zaidman, Andy

    Identifying Cross-Cutting Concerns Using Software Repository Mining Frank Mulder Software and/or a fee. IWPSE-EVOL'10 September 20-21, 2010 Antwerp, Belgium Copyright 2010 ACM 978 Framework #12;3.2 Tool-chain Structure 3.3 Data Acquisition 3.4 Frequent Itemset Mining 3.4.1 Definition #12

  18. Building a Repository for Workflow Systems Chengfei Liu

    E-Print Network [OSTI]

    Liu, Chengfei

    . The repository technology is introduced in CASE/CAD environments to provide unified access and management of Technology, Sydney NSW 2009, Australia liu@socs.uts.edu.au Xuemin Lin School of Computer Science maria@csee.uq.edu.au Abstract Workflow technology is becoming the key technology for business process

  19. QUT Digital Repository: http://eprints.qut.edu.au/

    E-Print Network [OSTI]

    Liang, Huizhi "Elly"

    by the Association for Computing Machinery, Inc. (ACM). #12;Design from the Everyday: Continuously evolving, embeddedQUT Digital Repository: http://eprints.qut.edu.au/ Heyer, Clint & Brereton, Margot (2010) Design Conference on Designing Interactive Systems, 16-20 August, 2010, Aarhus, Denmark. © Copyright 2010

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

    SciTech Connect (OSTI)

    1996-02-01

    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).

  1. Ectomycorrhizae and forest biogeochemistry: The role of ectomycorrhizal communities in forests impacted by global change

    E-Print Network [OSTI]

    Rosenstock, Nicholas Paul

    2010-01-01

    Total  weathering  =  Leachate  +   ?CEC  +  Seedling  drainage  (total  leachate,  L t ).  All  values  were  Barbara,  CA)   and  column  leachate  was  collected  in  

  2. Water Rx - The Problem of Pharmaceuticals in Our Nation's Waters

    E-Print Network [OSTI]

    Leitman, Melanie

    2011-01-01

    specific be done with the leachate collected from thecontamina- tion because if the leachate is subjected to theoften end up in landfill leachate, which can percolate into

  3. NUCLEOSYNTHETIC TUNGSTEN ISOTOPE ANOMALIES IN ACID LEACHATES OF THE MURCHISON CHONDRITE: IMPLICATIONS FOR HAFNIUM-TUNGSTEN CHRONOMETRY

    SciTech Connect (OSTI)

    Burkhardt, Christoph; Wieler, Rainer; Kleine, Thorsten; Dauphas, Nicolas

    2012-07-01

    Progressive dissolution of the Murchison carbonaceous chondrite with acids of increasing strengths reveals large internal W isotope variations that reflect a heterogeneous distribution of s- and r-process W isotopes among the components of primitive chondrites. At least two distinct carriers of nucleosynthetic W isotope anomalies must be present, which were produced in different nucleosynthetic environments. The co-variation of {sup 182}W/{sup 184}W and {sup 183}W/{sup 184}W in the leachates follows a linear trend that is consistent with a mixing line between terrestrial W and a presumed s-process-enriched component. The composition of the s-enriched component agrees reasonably well with that predicted by the stellar model of s-process nucleosynthesis. The co-variation of {sup 182}W/{sup 184}W and {sup 183}W/{sup 184}W in the leachates provides a means for correcting the measured {sup 182}W/{sup 184}W and {sup 182}W/{sup 183}W of Ca-Al-rich inclusions (CAI) for nucleosynthetic anomalies using the isotopic variations in {sup 183}W/{sup 184}W. This new correction procedure is different from that used previously, and results in a downward shift of the initial {epsilon}{sup 182}W of CAI to -3.51 {+-} 0.10 (where {epsilon}{sup 182}W is the variation in 0.01% of the {sup 182}W/{sup 183}W ratio relative to Earth's mantle). This revision leads to Hf-W model ages of core formation in iron meteorite parent bodies that are {approx}2 Myr younger than previously calculated. The revised Hf-W model ages are consistent with CAI being the oldest solids formed in the solar system, and indicate that core formation in some planetesimals occurred within {approx}2 Myr of the beginning of the solar system.

  4. Collected Works

    E-Print Network [OSTI]

    Turner, Lance

    2011-04-26

    The collection of work presented here illustrates the constant struggle individuals face in understanding the repercussions of their past, the weight of their decisions in the present moment, and the possibilities of the ...

  5. Expected brine movement at potential nuclear waste repository salt sites

    SciTech Connect (OSTI)

    McCauley, V.S.; Raines, G.E.

    1987-08-01

    The BRINEMIG brine migration code predicts rates and quantities of brine migration to a waste package emplaced in a high-level nuclear waste repository in salt. The BRINEMIG code is an explicit time-marching finite-difference code that solves a mass balance equation and uses the Jenks equation to predict velocities of brine migration. Predictions were made for the seven potentially acceptable salt sites under consideration as locations for the first US high-level nuclear waste repository. Predicted total quantities of accumulated brine were on the order of 1 m/sup 3/ brine per waste package or less. Less brine accumulation is expected at domal salt sites because of the lower initial moisture contents relative to bedded salt sites. Less total accumulation of brine is predicted for spent fuel than for commercial high-level waste because of the lower temperatures generated by spent fuel. 11 refs., 36 figs., 29 tabs.

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

    SciTech Connect (OSTI)

    D. Rigby

    2004-11-10

    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).

  7. Nuclear waste repository research at the micro- to nanoscale

    SciTech Connect (OSTI)

    Schaefer, T.; Denecke, M. A.

    2010-04-06

    Micro- and nano-focused synchrotron radiation techniques to investigate determinant processes in contaminant transport in geological media are becoming especially an increasingly used tool in nuclear waste disposal research. There are a number of reasons for this but primarily they are driven by the need to characterize actinide speciation localized in components of heterogeneous natural systems. We summarize some of the recent research conducted by researchers of the Institute of Nuclear Waste Disposal (INE) at the Karlsruhe Institute of Technology using micro- and nano-focused X-ray beams for characterization of colloids and their interaction with minerals and of elemental and phase distributions in potential repository host rocks and actinide speciation in a repository natural analogues sample. Such investigations are prerequisite to ensuring reliable assessment of the long term radiological safety for proposed nuclear waste disposal sites.

  8. Thermal Conductivity of the Potential Repository Horizon Model Report

    SciTech Connect (OSTI)

    J. Ramsey

    2002-08-29

    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.

  9. Guide to depositing into the Murdoch Research Repository What is the Murdoch Research Repository?

    E-Print Network [OSTI]

    staff and students. It aims to collect, preserve and make publically available the scholarly output of Murdoch University. We welcome contributions of HERDC-eligible research publications (i.e. journal and its associated bodies. To make one of your research publications publically available

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

    SciTech Connect (OSTI)

    Not Available

    1985-10-01

    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.

  11. 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]

    2004-01-01

    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

  12. Sandia Energy - 2014 US/German Workshop on Salt Repository Research...

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

    2014 USGerman Workshop on Salt Repository Research, Design, and Operation Home Stationary Power Nuclear Fuel Cycle Nuclear Energy Workshops 2014 USGerman Workshop on Salt...

  13. Sandia Energy - 2016 US/German Workshop on Salt Repository Research...

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

    2016 USGerman Workshop on Salt Repository Research, Design, and Operation Home Stationary Power Nuclear Fuel Cycle Nuclear Energy Workshops 2016 USGerman Workshop on Salt...

  14. Sandia Energy - 2015 US/German Workshop on Salt Repository Research...

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

    2015 USGerman Workshop on Salt Repository Research, Design, and Operation Home Stationary Power Nuclear Fuel Cycle Nuclear Energy Workshops 2015 USGerman Workshop on Salt...

  15. 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...

  16. 6th US/German Workshop on Salt Repository Research, Design and...

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

    LIST of Participants (August 25, 2015) 6th USGerman Workshop on Salt Repository Research, Design and Operations LAST NAME FIRST NAME COMPANY EMAIL lizowski Jarosaw AGH...

  17. Request Access to the PARSIIe Project Management Lessons Learned (PMLL) Repository

    Broader source: Energy.gov [DOE]

    The page identifies the process by which PARSIIe username/password is issued to Users who only require access to the PARSIIe Project Management Lessons Learned (PMLL) Repository.

  18. Generic Repository Concepts and Thermal Analysis for Advanced Fuel Cycles

    SciTech Connect (OSTI)

    Hardin, Ernest [Sandia National Laboratories (SNL)] [Sandia National Laboratories (SNL); Blink, James [Lawrence Livermore National Laboratory (LLNL)] [Lawrence Livermore National Laboratory (LLNL); Carter, Joe [Savannah River National Laboratory (SRNL)] [Savannah River National Laboratory (SRNL); Massimiliano, Fratoni [Lawrence Livermore National Laboratory (LLNL)] [Lawrence Livermore National Laboratory (LLNL); Greenberg, Harris [Lawrence Livermore National Laboratory (LLNL)] [Lawrence Livermore National Laboratory (LLNL); Howard, Rob L [ORNL] [ORNL

    2011-01-01

    The current posture of the used nuclear fuel management program in the U.S. following termination of the Yucca Mountain Project, is to pursue research and development (R&D) of generic (i.e., non-site specific) technologies for storage, transportation and disposal. Disposal R&D is directed toward understanding and demonstrating the performance of reference geologic disposal concepts selected to represent the current state-of-the-art in geologic disposal. One of the principal constraints on waste packaging and emplacement in a geologic repository is management of the waste-generated heat. This paper describes the selection of reference disposal concepts, and thermal management strategies for waste from advanced fuel cycles. A geologic disposal concept for spent nuclear fuel (SNF) or high-level waste (HLW) consists of three components: waste inventory, geologic setting, and concept of operations. A set of reference geologic disposal concepts has been developed by the U.S. Department of Energy (DOE) Used Fuel Disposition Campaign, for crystalline rock, clay/shale, bedded salt, and deep borehole (crystalline basement) geologic settings. We performed thermal analysis of these concepts using waste inventory cases representing a range of advanced fuel cycles. Concepts of operation consisting of emplacement mode, repository layout, and engineered barrier descriptions, were selected based on international progress and previous experience in the U.S. repository program. All of the disposal concepts selected for this study use enclosed emplacement modes, whereby waste packages are in direct contact with encapsulating engineered or natural materials. The encapsulating materials (typically clay-based or rock salt) have low intrinsic permeability and plastic rheology that closes voids so that low permeability is maintained. Uniformly low permeability also contributes to chemically reducing conditions common in soft clay, shale, and salt formations. Enclosed modes are associated with temperature constraints that limit changes to the encapsulating materials, and they generally have less capacity to dissipate heat from the waste package and its immediate surroundings than open modes such as that proposed for a repository at Yucca Mountain, Nevada. Open emplacement modes can be ventilated for many years prior to permanent closure of the repository, limiting peak temperatures both before and after closure, and combining storage and disposal functions in the same facility. Open emplacement modes may be practically limited to unsaturated host formations, unless emplacement tunnels are effectively sealed everywhere prior to repository closure. Thermal analysis of disposal concepts and waste inventory cases has identified important relationships between waste package size and capacity, and the duration of surface decay storage needed to meet temperature constraints. For example, the choice of salt as the host medium expedites the schedule for geologic disposal by approximately 50 yr (other factors held constant) thereby reducing future reliance on surface decay storage. Rock salt has greater thermal conductivity and stability at higher temperatures than other media considered. Alternatively, the choice of salt permits the use of significantly larger waste packages for SNF. The following sections describe the selection of reference waste inventories, geologic settings, and concepts of operation, and summarize the results from the thermal analysis.

  19. Adding OAI-ORE Support to Repository Platforms 

    E-Print Network [OSTI]

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

    2009-05-17

    ?OAI?ORE?Support?to? Repository?Pla8orms? Alexey?Maslov,?Adam?Mikeal,?Sco3?Phillips,?? John?Legge3,?Mark?McFarland? Texas?Digital?Library? OR?09? Overview? ?? Texas?Digital?Library? Use?Case?for?OAI?ORE? ?? Mapping?ORE?model?to? DSpace?architecture? ?? ImplementaJon?? ?? Results...: A case study of a digital library application?, Adam Mikeal, James Creel, Alexey Maslov, Scott Phillips, John Leggett, Mark McFarland. JCDL 2009 Current?PrioriDes? ?? Live?deployment?at?TDL? ?? Release?to?the?open?source?community? ?? Integra...

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

    SciTech Connect (OSTI)

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

    2007-07-01

    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)

  1. Dessicant materials screening for backfill in a salt repository

    SciTech Connect (OSTI)

    Simpson, D.R.

    1980-10-01

    Maintaining an anhydrous environment around nuclear waste stored in a salt repository is a concern which can be alleviated by using a desiccant material for backfilling. Such a desiccant should desiccate a brine yet be non deliquescent, the hydrated product should have moderate thermal stability, and the desiccant should have a high capacity and be readily available. From a literature search MgO and CaO were identified for detailed study. These oxides, and an intimate mixture of the two obtained by calcining dolomite, were used in experiments to further determine their suitability. They proved to be excellent desiccants with a high water capacity. The hydrates of both have moderate thermal stability and a high water content. Both MgO and CaO react in an alkaline chloride brine forming oxychloride compounds with different waters of crystallization. Some of these compounds are the Sorel Cements. CaO hydrates to Ca(OH)/sub 2/ which carbonates with CO/sub 2/ in air to form CaCO/sub 3/ and release the hydrated water. Thus the intimate mixture of CaO and MgO from calcined dolomite may serve as a desiccant and remove CO/sub 2/ from the repository atmosphere.

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

    SciTech Connect (OSTI)

    Beavers, J.A.; Durr, C.L.

    1991-05-01

    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.

  3. 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

    2013-07-01

    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)

  4. Scenarios constructed for the effects of tectonic processes on the potential nuclear waste repository at Yucca Mountain

    SciTech Connect (OSTI)

    Barr, G.E.; Borns, D.J.; Fridrich, C.

    1996-10-01

    A comprehensive collection of scenarios is presented that connect initiating tectonic events with radionuclide releases by logical and physically possible combinations or sequences of features, events and processes. The initiating tectonic events include both discrete faulting and distributed rock deformation developed through the repository and adjacent to it, as well as earthquake-induced ground motion and changes in tectonic stress at the site. The effects of these tectonic events include impacts on the engineered-barrier system, such as container rupture and failure of repository tunnels. These effects also include a wide range of hydrologic effects such as changes in pathways and flow rates in the unsaturated and saturated zones, changes in the water-table configuration, and in the development of perched-water systems. These scenarios are intended go guide performance-assessment analyses and to assist principal investigators in how essential field, laboratory, and calculational studies are used. This suite of scenarios will help ensure that all important aspects of the system disturbance related to a tectonic scenario are captured in numerical analyses. It also provides a record of all options considered by project analysts to provide documentation required for licensing agreement. The final portion of this report discusses issues remaining to be addressed with respect to tectonic activity. 105 refs.

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

    E-Print Network [OSTI]

    Lalmas, Mounia

    supports not only the repository evaluation or risk assessment exercise, but also documentation in a moreRethinking Preservation Validation with the Preserved Object and Repository Risks Ontology (PORRO and evaluation are fundamentally implicit and share similar complexity. Means are required for the identifica

  6. 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

  7. 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

  8. Model Evaluation of the Thermo-Hydrological Response in Argillaceous Sedimentary Rock Repository for Direct Disposal of Dual-Purpose Canisters

    E-Print Network [OSTI]

    Zheng, Liange

    2014-01-01

    Alternative Concepts for Direct Disposal of Dual-PurposeRock Repository for Direct Disposal of Dual-PurposeRock Repository for Direct Disposal of Dual-Purpose

  9. 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

    2004-01-01

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

  10. 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

    2011-01-01

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

  11. 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

    2011-07-15

    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

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

    SciTech Connect (OSTI)

    Rickard, W.H.

    1988-02-01

    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.

  13. CPTAC Assay Portal: a repository of targeted proteomic assays

    SciTech Connect (OSTI)

    Whiteaker, Jeffrey R.; Halusa, Goran; Hoofnagle, Andrew N.; Sharma, Vagisha; MacLean, Brendan; Yan, Ping; Wrobel, John; Kennedy, Jacob; Mani, DR; Zimmerman, Lisa J.; Meyer, Matthew R.; Mesri, Mehdi; Rodriguez, Henry; Abbateillo, Susan E.; Boja, Emily; Carr, Steven A.; Chan, Daniel W.; Chen, Xian; Chen, Jing; Davies, Sherri; Ellis, Matthew; Fenyo, David; Hiltket, Tara; Ketchum, Karen; Kinsinger, Christopher; Kuhn, Eric; Liebler, Daniel; Lin, De; Liu, Tao; Loss, Michael; MacCoss, Michael; Qian, Weijun; Rivers, Robert; Rodland, Karin D.; Ruggles, Kelly; Scott, Mitchell; Smith, Richard D.; Thomas, Stefani N.; Townsend, Reid; Whiteley, Gordon; Wu, Chaochao; Zhang, Hui; Zhang, Zhen; Paulovich, Amanda G.

    2014-06-27

    To address these issues, the Clinical Proteomic Tumor Analysis Consortium (CPTAC) of the National Cancer Institute (NCI) has launched an Assay Portal (http://assays.cancer.gov) to serve as a public repository of well-characterized quantitative, MS-based, targeted proteomic assays. The purpose of the CPTAC Assay Portal is to facilitate widespread adoption of targeted MS assays by disseminating SOPs, reagents, and assay characterization data for highly characterized assays. A primary aim of the NCI-supported portal is to bring together clinicians or biologists and analytical chemists to answer hypothesis-driven questions using targeted, MS-based assays. Assay content is easily accessed through queries and filters, enabling investigators to find assays to proteins relevant to their areas of interest. Detailed characterization data are available for each assay, enabling researchers to evaluate assay performance prior to launching the assay in their own laboratory.

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

    SciTech Connect (OSTI)

    Howard, Robert; Dupont, Mark; Blink, James A.; Fratoni, Massimiliano; Greenberg, Harris; Carter, Joe; Hardin, Ernest L.; Sutton, Mark A.

    2011-08-01

    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.

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

    SciTech Connect (OSTI)

    Weers, J.; Anderson, A.

    2014-02-01

    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).

  16. University of Southampton Research Repository ePrints Soton

    E-Print Network [OSTI]

    collection of source segregated food waste by Tsz Wing CHU Thesis for the degree of Doctor of Philosophy WASTE Tsz Wing Chu The collection of source segregated household food waste is becoming increasingly household food waste collection systems are operating in the UK and in Europe; however, studies

  17. Attitudes and aspirations in a diverse world: the Project StORe perspective on scientific repositories 

    E-Print Network [OSTI]

    Pryor, Graham

    2006-01-01

    When preparing a team of recent postgraduates who were about to embark on a survey of repository users, it became necessary to equip them with a glossary of terms for use when explaining their mission. Whilst our project’s ...

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

    E-Print Network [OSTI]

    Aponte Rivera, Fernando Luis

    2013-12-06

    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. ...

  19. Where does it go from here? The place of software in digital repositories 

    E-Print Network [OSTI]

    Chue Hong, Neil

    The open repositories community has made great strides in recent years in addressing interoperability, policy and providing the arguments for open access and sharing. One aspect of open research which has come to prominence ...

  20. 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, geospatial database modelling, interoperability, metadata, UML, Perceptory, ISO/TC 211, OGC 1. Introduction the conceptual content of object oriented application database schemas and dictionaries aligned

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

    E-Print Network [OSTI]

    Ghosh, Suchandra Tina, 1973-

    2004-01-01

    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. ...

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

    E-Print Network [OSTI]

    Wang, J.S.Y.

    2014-01-01

    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

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

    E-Print Network [OSTI]

    Driscoll, Michael J.

    1988-01-01

    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. ...

  4. The Five Great Space Repository Bodhisattvas: Lineage, Protection and Celestial Authority in Ninth-Century Japan

    E-Print Network [OSTI]

    Pedersen, Hillary

    2010-12-31

    This dissertation explores the protective role of the Five Great Space Repository Bodhisattva (Godai Kokuzo Bosastu) sculptural pentads in Japan during the mid-ninth-century. While existing art historical scholarship ...

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

    SciTech Connect (OSTI)

    C. Sanders; D. Kimball

    2005-08-02

    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.

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

    SciTech Connect (OSTI)

    Tsujimoto, Keiichi; Ahn, J.

    1999-07-01

    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.

  7. QUT Digital Repository: http://eprints.qut.edu.au/

    E-Print Network [OSTI]

    Roe, Paul

    coordinators (Busher et al., 2000, p. 184). It is precisely at this middle management level within schools, Donna L. (2006) Individual and collective leadership in school science departments. Research in Science Individual and Collective Leadership in School Science Departments Stephen M. Ritchie, Gail Mackay, & Donna L

  8. 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.

    1985-11-01

    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.

  9. QUT Digital Repository: http://eprints.qut.edu.au/

    E-Print Network [OSTI]

    Roe, Paul

    calendar- based ground patrols [1]. However, calendar-based inspection by linesman is labour the line and automatically collecting data in power line corridor; and (2) any risk assessment of power

  10. Expected near-field thermal environments in a sequentially loaded spent-fuel or high-level waste repository in salt

    SciTech Connect (OSTI)

    Rickertsen, L.D.; Arbital, J.G.; Claiborne, H.C.

    1982-01-01

    This report describes the effect of realistic waste emplacement schedules on repository thermal environments. Virtually all estimates to date have been based on instantaneous loading of wastes having uniform properties throughout the repository. However, more realistic scenarios involving sequential emplacement of wastes reflect the gradual filling of the repository over its lifetime. These cases provide temperatures that can be less extreme than with the simple approximation. At isolated locations in the repository, the temperatures approach the instantaneous-loading limit. However, for most of the repository, temperature rises in the near-field are 10 to 40 years behind the conservative estimates depending on the waste type and the location in the repository. Results are presented for both spent-fuel and high-level reprocessing waste repositories in salt, for a regional repository concept, and for a single national repository concept. The national repository is filled sooner and therefore more closely approximates the instantaneously loaded repository. However, temperatures in the near-field are still 20/sup 0/C or more below the values in the simple model for 40 years after startup of repository emplacement operations. The results suggest that current repository design concepts based on the instantaneous-loading predictions are very conservative. Therefore, experiments to monitor temperatures in a test and evaluation facility, for example, will need to take into account the reduced temperatures in order to provide data used in predicting repository performance.

  11. 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

    2008-01-01

    emplacement drift at Yucca Mountain. Journal of Contaminantniches in tuff units at Yucca Mountain. Proceedings of thetunnels, similar to the Yucca Mountain repository concept in

  12. Modeling thermal-hydrological response of the unsaturated zone at Yucca Mountain, Nevada, to thermal load at a potential repository

    E-Print Network [OSTI]

    Haukwa, C.B.; Wu, Yu-Shu; Bodvarsson, G.S.

    2002-01-01

    Repository at Yucca Mountain. In Materials Research Societystudies using the Yucca Mountain unsaturated zone model.Unsaturated Zone, Yucca Mountain, Nevada. Water Resources

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

    SciTech Connect (OSTI)

    1982-07-01

    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.

  14. 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.

  15. 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.

    2003-11-15

    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.

  16. Biogeochemical Changes at Early Stage After the Closure of Radioactive Waste Geological Repository in South Korea

    SciTech Connect (OSTI)

    Choung, Sungwook; Um, Wooyong; Choi, Seho; Francis, Arokiasamy J.; Kim, Sungpyo; Park, Jin beak; Kim, Suk-Hoon

    2014-09-01

    Permanent disposal of low- and intermediate-level radioactive wastes in the subterranean environment has been the preferred method of many countries, including Korea. A safety issue after the closure of a geological repository is that biodegradation of organic materials due to microbial activities generates gases that lead to overpressure of the waste containers in the repository and its disintegration with the release of radionuclides. As part of an ongoing large-scale in situ experiment using organic wastes and groundwater to simulate geological radioactive waste repository conditions, we investigated the geochemical alteration and microbial activities at an early stage (~63 days) intended to be representative of the initial period after repository closure. The increased numbers of both aerobes and facultative anaerobes in waste effluents indicate that oxygen content could be the most significant parameter to control biogeochemical conditions at very early periods of reaction (<35 days). Accordingly, the values of dissolved oxygen and redox potential were decreased. The activation of anaerobes after 35 days was supported by the increased concentration to ~50 mg L-1 of ethanol. These results suggest that the biogeochemical conditions were rapidly altered to more reducing and anaerobic conditions within the initial 2 months after repository closure. Although no gases were detected during the study, activated anaerobic microbes will play more important role in gas generation over the long term.

  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 1: conceptualization and characterization of the problems and summary of results

    E-Print Network [OSTI]

    2004-01-01

    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

  18. Evaluating the Long-Term Safety of a Repository at Yucca Mountain 

    SciTech Connect (OSTI)

    Van Luik, Abe

    2009-07-17

    Regulations require that the repository be evaluated for its health and safety effects for 10,000 years for the Site Recommendation process. Regulations also require potential impacts to be evaluated for up to a million years in an Environmental Impact Statement. The Yucca Mountain Project is in the midst of the Site Recommendation process. The Total System Performance Assessment (TSPA) that supports the Site Recommendation evaluated safety for these required periods of time. Results showed it likely that a repository at this site could meet the licensing requirements promulgated by the Nuclear Regulatory Commission. The TSPA is the tool that integrates the results of many years of scientific investigations with design information to allow evaluations of potential far-future impacts of building a Yucca Mountain repository. Knowledge created in several branches of physics is part of the scientific basis of the TSPA that supports the Site Recommendation process.

  19. 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)

    2006-03-01

    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.

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

    E-Print Network [OSTI]

    Mercer, Holly

    2011-04-15

    :// creativecommons.org/licenses/by/2.0/) 50. Schatz, B., Mischo, W.H., Cole, T.W., Hardin, J.B., Bishop, A.P. and Hsinchun Chen. (1996) Federating diverse collections of scientific literature. Computer 29 (5): 28-36. http://hdl.handle.net/2142/226 51. http...

  1. QUT Digital Repository: http://eprints.qut.edu.au/

    E-Print Network [OSTI]

    Liang, Huizhi "Elly"

    @student.qut.edu.au r.nayak@qut.edu.au Abstract The maintenance dataset provided by SunWater contains information about proposed. . Keywords: Text Mining, Clustering, Semantic Network, Association Rule Mining, pump failure mode for extracting useful information from the maintenance dataset that is collected by SunWater. Sun

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

    SciTech Connect (OSTI)

    Ross, B.

    1989-02-01

    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.

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

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

    Chekanov, S. V.

    2015-01-01

    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.

  4. Acceptance of waste for disposal in the potential United States repository at Yucca Mountain, Nevada

    SciTech Connect (OSTI)

    Stahl, D.; Svinicki, K.

    1996-07-01

    This paper addresses the process for the acceptance of waste into the waste management system (WMS) with a focus on the detailed requirements identified from the Waste Acceptance System Requirements Document. Also described is the recent dialogue between OCRWM and the Office of Environmental Management to resolve issues, including the appropriate interpretation and application of regulatory and system requirements to DOE-owned spent fuel. Some information is provided on the design of the repository system to aid the reader in understanding how waste that is accepted into the WMS is received and emplaced in the repository.

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

    E-Print Network [OSTI]

    S. V. Chekanov

    2015-02-06

    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.

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

    SciTech Connect (OSTI)

    Smith, M.W.; Shadle, L.J.; Hill, D.

    2007-01-01

    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.

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

    E-Print Network [OSTI]

    Bourgeat, Alain; Smai, Farid

    2010-01-01

    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.

  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]

    Boyer, Edmond

    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

  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

    of lignocellulosic fiber suspensions with in-situ and ex-situ multi-scale physical metrologies. (2015) In: 10th Investigation of hydrolysis of lignocellulosic fiber suspensions with in-situ and ex-situ multi-scale physical and chemicals production of petroleum substitutes from renewable carbon, bioconversion of lignocellulose

  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

    of the transesterification reaction between triglycerides and ethanol using near infrared spectroscopy combined with gas near infrared spectroscopy combined with gas chromatography Romain Richarda,b,c , Ying Lia,b , Brigitte method, gas chromatography-flame ionization detection was used as a reference method. The method

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

    E-Print Network [OSTI]

    Mailhes, Corinne

    . Structural composites A. Glass fibres B. Fatigue B. Fracture a b s t r a c t Helicopter blades are made tolerance properties. For example, the skin of helicopter blades is often made of a few woven plies (Fig. 1-the-thickness crack propagation due to fatigue in thin woven glass fabric laminates. A technological test specimen

  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

    . They are currently used in numerous applications like for instance helicopter blades, ship hulls or optical benches coupling has been found between the front skin and the core. The impact tests indicate that aluminium impact tests. These impacts are characterized by medium-velocities and high energies: 120 m/s and 1 k

  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

    . They are currently used in numerous applications like for instance helicopter blades, ship hulls or optical benches, 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

  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

    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 and tested against isothermal oxidation.1,2 Alternatively, amorphous Al2O3 coatings directly ap- plied

  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

    known application is probably the microbial fuel cell technology that is capable of turning biomass fuel cell; wastewater treatment Introduction Typically, biofilms have been associated with adverse of renewable energy including the development of microbial fuel cells (MFCs) and hydrogen production, through

  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

    -polyethersulfone Crosslinked sulfonated polyethersulfone Proton exchange membrane fuel cell a b s t r a c t Synthesis presented very promising performances for use in Proton Exchange Membrane Fuel Cells. 1. Introduction Ion, electrodialysis, fuel cells and many other processes. Nafions is a cation conducting mem- brane, specially

  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

    for microbial fuel cells: a review. (2012) ChemSusChem, vol. 5 (n° 6). pp. 975-987. ISSN 1864-564X Any-oatao@listes.diff.inp-toulouse.fr #12;Microbial Catalysis of the Oxygen Reduction Reaction for Microbial Fuel Cells: A Review Benjamin] microbial fuel cells (MFCs) have been believed to be a promising technology for the pro- duction

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

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    from waste cooking oil: a technological review. (2013) Chemical Engineering Journal, vol. 233 . pp. 201 waste cooking oil in fatty acid methyl esters. Intensified technologies are compared on mass intensification Biodiesel Waste cooking oil Transesterification Esterification Hydrolysis a b s t r a c

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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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    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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    intense fluctuations of turbulent kinetic energy and strong preferential concentration of particles for the aggregation of chondrules and other constituents into primitive planetesimals.3 Example in industrial and aluminum particles in solid rocket motors.6 However, the three-way coupled interactions between

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    is con- summated by an electrical car during an imposed displacement, see [1] for an overview and bound approach for minimizing the energy consumption of an electrical vehicle. (2013) In: 11th and Bound Approach for Minimizing the Energy Consumption of an Electrical Vehicle Abdelkader Merakeb D

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    transcritical multistage axial Organic Rankine Cycle turbines - 2013 Any correspondence concerning this service gas flows through transcritical multistage axial Organic Rankine Cycle turbines L. Sciacovellia , P recent studies suggest that supercritical Organic Rankine Cycles have a great potential for low

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    . This alloy is expected to be used as the material for hot ducts and for the intermediate heat exchanger). The nominal operation conditions of the exchanger, called IHX, will be in the temperature range of 800­1000 °C6 carbide types are present in the as received condition or after thermal treatments on the Inconel

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    to this article: 10.1109/WTS.2015.7117278 URL: http://dx.doi.org/10.1109/wts.2015.7117278 To cite this version Communications. In: Wireless telecommunications symposium (WTS), 15 April 2015 - 17 April 2015 (New York City

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    of sources such as gas-turbine generators, steam-turbine generators, exhaust gas boilers, and fuel and extraction. The use of a natural gas turbine, less economically efficient, turns out to be a more attractive production system (UPS), either fuel oil or natural gas, of the HDA process are carried out. In each case

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    this version : Song, Jie and Guo, Chaopeng and Wang, Zhi and Zhang, Yichan and Yu, Ge and Pierson, Jean Songa, , Chaopeng Guoa , Zhi Wanga , Yichan Zhanga , Ge Yub , Jean-Marc Piersonc a Software College

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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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    , Benjamin and Ansart, Renaud and Hemati, Mehrdji A new heat transfer fluid for concentrating solar systems-oatao@listes-diff.inp-toulouse.fr #12;doi:10.1016/j.egypro.2014.03.067 A new heat transfer fluid for concentrating solar systems , M. Hematib a Processes, Materials and Solar Energy laboratory, PROMES-CNRS, 7 rue du Four Solaire

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    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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    , bubbling fluidization of a sand fluidized bed with different biomass loadings are investigated by means Fluidization Radioactive Particle Tracking CFD simulation Bubbling Mixing a b s t r a c t In this study it is fluidized in a 152 mm diameter bed with a 228 mm static height. Using a pair of fiber optic sensors

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    in increased fatigue damage of cables and risers exposed to wind and ocean currents. In practical applications are encountered in a number of physical systems, especially in civil and offshore engineering where they result

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    in fluid mechanics for offshore engineering: a modelling perspective'. Subject Areas: ocean engineering­structure interaction mechanisms. The impact of FIV in several civil, wind, offshore and nuclear engineering are encountered in a great variety of physical systems, from the oscillations of plants in wind #12

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    parameters of creep (i.e. stress exponent, apparent activation energy) seem to be unreliable, and do involve a uniaxial press coupled with a heating device, and are known to allow the manufacturing of fully] or thermal diffusion due to possible high local tempera- ture gradients [11]. The dependence

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    . 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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    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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    , an adsorption heat pump oper- ates by cycling adsorbate between adsorber, condenser, and evaporator. In the adsorption heat pump cycle, adsorption phenomena play the same role of me- chanical power, so that the working fluid can be cir- culated in the cycle without any mechanical power [3]. An adsorption heat pump

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    of heating process of soybean oil and seeds on fatty acid biohydrogenation in vitro. (2014) Journal of Dairy to protect linoleic acid from BH. Soybean oil re- sulted in higher trans-11 isomer production than seeds: 5 increased trans-11 isomer production by 11% compared with no heating and 6-h roasted fat. Extrusion of seeds

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    Simulation and modelling of the waves transmission and generation in a stator blade row in a combustion-oatao@listes-diff.inp-toulouse.fr #12;Simulation and modelling of the waves transmission and generation in a stator blade row. The transfer functions of the blade row are compared with the model of Cumpsty and Marble that assumes

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    the diffusion coefficient and the concentration of the studied species. Results obtained with ferrocyanide

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    this version : Sun, Hongyang and Stolf, Patricia and Pierson, Jean-Marc and Da Costa, Georges Energy-aware resource management for heterogeneous datacenters Hongyang Sun , Patricia Stolf, Jean-Marc Pierson, Georges in datacenters, we are confronted with their different behaviors in terms of performance, power consumption

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    and online measurements. (2012) In: Human Factors and Ergonomics Society Europe Chapter Annual Meeting on the evaluation of flight performance) will be examined and compared to that of tests currently in use by one crashes. More specifically, Loss of Control In- flight (LOC-I) and Control Flight Into Terrain (CFIT

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    ­Al) alloys, which originate from pyrochemical treatment of spent metallic nuclear fuel by electrochemical actinide­aluminium alloys, which originate from pyrochemical recovery of actinides from spent metallic nuclear fuel by electro- chemical methods in molten LiCl­KCl. In the present work, the most important

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    promising option for nuclear fuel cycle, and molten salt electrorefining is well adapted for metallic spent fuel reprocessing, such as U­Zr and U­Pu­Zr [1­3], where the classical hydrometallurgical processes metal and Zr alloys preparation on Ni, B and C [8,21­25]. In these media, the electrochemical reduction

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    is higher than that of base metal. © 2010 Laser Institute of America. Key words: magnesium alloys, laser, magnesium alloys have one major advan- tage over all other structural metallic materials: low density.1 their fuel efficiency and reducing their CO2 emissions. In recent years, many researches intend to develop

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    electrorefining is well adapted for metallic spent fuel reprocessing, such as U­Zr and U­Pu­Zr [1­3], where strategy is considered as one of the most promising option for nuclear fuel cycle, and molten salt media of coherent Zr metal and Zr alloys preparation on Ni, B and C [8,21­25]. In these media

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    originate from pyrochemical recovery of actinides from spent metallic nuclear fuel by electro- chemical­Al) alloys, which originate from pyrochemical treatment of spent metallic nuclear fuel by electrochemical

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    ) and (ii) vertical-axis wind turbine (VAWTs). VAWTs work at low speed ratios. A lot of works was published has a vertical axis. Each turbine blade combines a rotating movement around its own axis and around wind turbines can be classified in two great families ([8]) (i) horizontal-axis wind turbine (HAWTs

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    is the high pressure turbine nozzle guide vane (NGV) downstream of the combustion chamber. Designing high

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    (1) are used. One such application is regenerative brak- ing, used to recover power in cars and electric mass transit vehicles that would otherwise lose braking energy as heat. However, super- capacitors

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

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    ]). In many cases, the dual requirements of power and heating in industrial processes are treated separately: power is purchased from an off-site energy provider and heating is produced on-site through fossil fuel Economic and environmental impacts of the energy source for the utility production system in the HDA

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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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    Fall Meeting - AGU 2014, 15 December 2014 - 19 December 2014 (San Francisco, United States). Any will measure river height, width, and slope, globally, as well as characterizing storage change in lakes the fourth utilizes at-many-stations hydraulic geometry relating width and discharge. In all cases, SWOT

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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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    -impregnated of the polyester thermoplastic adhesive have been investigated by differ- ential scanning calorimetry (DSC) and dynamic dielectric spectroscopy (DDS). The thermoplastic polyester adhesive and the oriented PET films with high shear strength is required. This polyester thermoplastic adhesive is also called the hot melt

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    on the results as much globally as locally. The Simmer-like drag model is preferred in comparison to the Large that the Simmer-like model is very sensitive to the inclusion diameter. Nomenclature a = date of the first wet

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    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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    to the grafting performance. 1. Introduction Today synthesis of organic­inorganic hybrid materials is not only-like phyllosilicates by alkoxyorganosilane grafting. Journal of Materials Chemistry, vol. 20 (n° 43). pp. 969501276a A range of talc-like phyllosilicates were prepared via a hydrothermal synthesis performed at five

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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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    such as wind or marine currents. The most common way to extract this energy is to convert it into the rotary-Sadeghi, Yahya and Langre, Emmanuel de On the efficiency of energy harvesting using vortex-induced vibrations-oatao@listes-diff.inp-toulouse.fr #12;On the efficiency of energy harvesting using vortex-induced vibrations of cables Clément Grouthier

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    of Spain) and, more recently, the British Petroleum (BP) Deep- water Horizon oil spill (in 2010, northern

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    the environmental un- derstanding (aquifer, site-pollution) to industrial process improvements (oil production: CPC Program Library, Queen's University, Belfast, N. Ireland Licensing provisions: GNU General Public License No. of lines in distributed program, including test data, etc.: 36 355 No. of bytes in distributed

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    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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    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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    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

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    dispatching strategies in smart-microgrids with storage. (2014) Renewable and Sustainable Energy Reviews, vol s t r a c t With the development of decentralized power sources based on renewable energy, power grids algorithm. Another approach using step by step optimization and exploiting an original self-adaptive dynamic

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    the work of Toulouse researchers and makes it freely available over the web where possible dedicated to imaging are presented through the analysis of the dark current behavior in pixel arrays and isolated photodiodes. The mean dark current in- crease and the dark current nonuniformity are investigated

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    salts (LiCl or CaCl2), for different purposes: high purity Si production [2], spent nuclear fuel processing (reduc- tion of rare earth oxides [3], UO2 [4], U3O8 [5], MOX [6], spent fuel [7], etc.), pure product is often polluted by carbides, due to the reduction of carbonates CO3 2- formed by the reaction

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    to handle different fuel types, i.e., metal, oxide, carbide, nitride, mixed ceramic-metal, ceramic to be present in irradiated fuels. The present investigation addresses the electrochemical reduction of Zr4 nuclear fuel. The renewed interest owes its origin to several attractive features

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    the cylinders size and by increasing the pressure inside the chamber thanks to turbo chargers. It is commonly

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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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    . 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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    E-Print Network [OSTI]

    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

  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]

    Mailhes, Corinne

    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

  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]

    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

  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]

    Mailhes, Corinne

    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

  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]

    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

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

    E-Print Network [OSTI]

    Boyer, Edmond

    .03.024 #12;Model and simulation of a solar kiln with energy storage D. Luna a , J.-P. Nadeau a,*, Y. Jannot b storage Modeling Quality a b s t r a c t A solar kiln with energy storage can be used for continuous. Introduction Solar systems are currently evolving towards integrating energy storage [1], so as to resolve

  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]

    Paris-Sud XI, Université de

    based on the experimental values of enthalpy of formation, low temperature specific heat, liquidus. Thermodynamic and thermochemical properties; E. Phase diagram, prediction 1. Introduction The development of new

  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

    The enthalpy of formation from the elements of a well-characterized synthetic Pb-jarosite sample corresponding of the heat of formation for a lead-contain- ing jarosite. Comparison to the thermochemical properties of hydronium jarosite and plumbojarosite end-members strongly suggests the existence of a negative enthalpy

  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]

    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

  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

    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

  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

    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

  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

    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

  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

    of initial configuration in gravitational spreading of material fronts. (2014) Theoretical and Computational configuration in gravitational spreading of material fronts Abstract We present the results from laboratory spreading of these destructive debris clouds, as seen in Fig. 1, sensitively depends on the building's shape

  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]

    Mailhes, Corinne

    electrolyte with phosphoric acid ester and its application for quasi solid-state supercapacitors. (2015-aqueous gel polymer electrolyte with phosphoric acid ester and its application for quasi solid, France h i g h l i g h t s New proton-conducting gel polymer electrolyte has been proposed

  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

    , Stéphane and Andrienko, Gennady and Andrienko, Natalia Wind parameters extraction from aircraft-oatao@listes-diff.inp-toulouse.fr #12;Wind parameters extraction from aircraft trajectories C. Hurter a, , R. Alligier a,b , D. Gianazza s t r a c t When supervising aircraft, air traffic controllers need to know the current wind magnitude

  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]

    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

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

    SciTech Connect (OSTI)

    Scott, J.A.

    1983-03-01

    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.

  20. 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 developed a sequential model to predict the coupled thermo-hydraulic processes at a cell-scale radioactive

  1. 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

  2. Cryptonite: A Secure and Performant Data Repository on Public Clouds Alok Kumbhare, Yogesh Simmhan, Viktor Prasanna

    E-Print Network [OSTI]

    Hwang, Kai

    Cryptonite: A Secure and Performant Data Repository on Public Clouds Alok Kumbhare, Yogesh Simmhan with collaborators. However, there is heightened concern about the security and privacy of Cloud-hosted data due the persistence and avail- ability of Cloud storage but with client-controlled security and encryption, low key

  3. Toolset and Program Repository for Code Coverage-Based Test Suite Analysis and Manipulation

    E-Print Network [OSTI]

    Beszedes, Árpád

    . The aim of the SoDA (Software Development Analysis framework) library, toolset and program repository´avid Tengeri, ´Arp´ad Besz´edes, D´avid Havas and Tibor Gyim´othy Department of Software Engineering University is often used in academic and industrial practice of white-box software testing. Various test optimization

  4. 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

  5. Data and Metadata Harmonization for the RAND Survey Meta Data Repository

    E-Print Network [OSTI]

    Amin, Alerk

    2013-04-17

    The RAND Survey Meta Data Repository aims to help researchers use data and metadata from the HRS-family of surveys on aging, including studies from the US, UK/Europe and Asia. The project consists of 3 major parts: 1) Importing the metadata for each...

  6. Efficacy of backfilling and other engineered barriers in a radioactive waste repository in salt

    SciTech Connect (OSTI)

    Claiborne, H.C.

    1982-09-01

    In the United States, investigation of potential host geologic formations was expanded in 1975 to include hard rocks. Potential groundwater intrusion is leading to very conservative and expensive waste package designs. Recent studies have concluded that incentives for engineered barriers and 1000-year canisters probably do not exist for reasonable breach scenarios. The assumption that multibarriers will significantly increase the safety margin is also questioned. Use of a bentonite backfill for surrounding a canister of exotic materials was developed in Sweden and is being considered in the US. The expectation that bentonite will remain essentially unchanged for hundreds of years for US repository designs may be unrealistic. In addition, thick bentonite backfills will increase the canister surface temperature and add much more water around the canister. The use of desiccant materials, such as CaO or MgO, for backfilling seems to be a better method of protecting the canister. An argument can also be made for not using backfill material in salt repositories since the 30-cm-thick space will provide for hole closure for many years and will promote heat transfer via natural convection. It is concluded that expensive safety systems are being considered for repository designs that do not necessarily increase the safety margin. It is recommended that the safety systems for waste repositories in different geologic media be addressed individually and that cost-benefit analyses be performed.

  7. Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository

    SciTech Connect (OSTI)

    K.G. Mon; F. Hua

    2005-04-12

    This paper reviews the state-of-the-art understanding of the degradation processes by the Yucca Mountain Project (YMP) with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the first 10,000-years after repository closure. This paper provides an overview of the degradation of the waste packages and drip shields in the repository after permanent closure of the facility. The degradation modes discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking, and hydrogen induced cracking of Alloy 22 and titanium alloys. The effects of microbial activity and radiation on the degradation of Alloy 22 and titanium alloys are also discussed. Further, for titanium alloys, the effects of fluorides, bromides, and galvanic coupling to less noble metals are considered. It is concluded that the materials and design adopted will provide sufficient safety margins for at least 10,000-years after repository closure.

  8. 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.

    1982-06-01

    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.

  9. 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.

    1982-06-01

    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.

  10. Creating and Evaluating Metadata for a Large Legacy Thesis Collection: From 'Vocational Agriculture' (1922) to 'Microemulsion-mediated syntheses' (2004) 

    E-Print Network [OSTI]

    Potvin, Sarah; Creel, James Silas

    2013-05-23

    stream_source_info Creating and Evaluating Metadata for a Large Legacy Thesis Collection_Potvin and Creel (2013) rev. 3.14.13.pdf.txt stream_content_type text/plain stream_size 5933 Content-Encoding ISO-8859-1 stream_name Creating... and Evaluating Metadata for a Large Legacy Thesis Collection_Potvin and Creel (2013) rev. 3.14.13.pdf.txt Content-Type text/plain; charset=ISO-8859-1 Repository Creating and Evaluating Metadata for a Large Legacy Thesis Collection: From...

  11. A Prototype Performance Assessment Model for Generic Deep Borehole Repository for High-Level Nuclear Waste - 12132

    SciTech Connect (OSTI)

    Lee, Joon H.; Arnold, Bill W.; Swift, Peter N.; Hadgu, Teklu; Freeze, Geoff; Wang, Yifeng

    2012-07-01

    A deep borehole repository is one of the four geologic disposal system options currently under study by the U.S. DOE to support the development of a long-term strategy for geologic disposal of commercial used nuclear fuel (UNF) and high-level radioactive waste (HLW). The immediate goal of the generic deep borehole repository study is to develop the necessary modeling tools to evaluate and improve the understanding of the repository system response and processes relevant to long-term disposal of UNF and HLW in a deep borehole. A prototype performance assessment model for a generic deep borehole repository has been developed using the approach for a mined geological repository. The preliminary results from the simplified deep borehole generic repository performance assessment indicate that soluble, non-sorbing (or weakly sorbing) fission product radionuclides, such as I-129, Se-79 and Cl-36, are the likely major dose contributors, and that the annual radiation doses to hypothetical future humans associated with those releases may be extremely small. While much work needs to be done to validate the model assumptions and parameters, these preliminary results highlight the importance of a robust seal design in assuring long-term isolation, and suggest that deep boreholes may be a viable alternative to mined repositories for disposal of both HLW and UNF. (authors)

  12. 13450 13470 13490 13510 Fluorescenceyield(FF/I0)

    E-Print Network [OSTI]

    and carboys. Tygon tubing routes leachate from interaction of rainwater with plant material in trays facilitate microbial exchange with surrounding mulch. Underground tubing routes leachate into buried carboys. Leachate was manually pumped from underground carboys during periodic collections. #12;

  13. Transforming trash: reuse as a waste management and climate change mitigation strategy

    E-Print Network [OSTI]

    Vergara, Sintana Eugenia

    2011-01-01

    with MSW can produce toxic leachate when the acids producedMSW lower the pH of the leachate, which increases thefrom escaping. Fit with liners, leachate collection and gas

  14. 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.

    1983-11-01

    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.

  15. Multiscale Thermohydrologic Model Supporting the Licence Application for the Yucca Mountain Repository

    SciTech Connect (OSTI)

    T.A> Buscheck; Y. Sun; Y. Hao

    2006-03-28

    The MultiScale ThermoHydrologic Model (MSTHM) predicts thermal-hydrologic (TH) conditions within emplacement tunnels (drifts) and in the adjoining host rock at Yucca Mountain, Nevada, which is the proposed site for a radioactive waste repository in the US. Because these predictions are used in the performance assessment of the Yucca Mountain repository, they must address the influence of variability and uncertainty of the engineered- and natural-system parameters that significantly influence those predictions. Parameter-sensitivity studies show that the MSTHM predictions adequately propagate the influence of parametric variability and uncertainty. Model-validation studies show that the influence of conceptual-model uncertainty on the MSTHM predictions is insignificant compared to that of parametric uncertainty, which is propagated through the MSTHM.

  16. THE DECISION TO RECOMMEND YUCCA MOUNTAIN AND THE NEXT STEPS TOWARD LICENSED REPOSITORY DEVELOPMENT

    SciTech Connect (OSTI)

    Barrett, L. H.

    2002-02-25

    After more than 20 years of carefully planned and reviewed scientific field work by the U.S. Department of Energy, the U.S. Geological Survey, and numerous other organizations, Secretary of Energy Abraham concluded in January that the Yucca Mountain site is suitable, within the meaning of the Nuclear Waste Policy Act, for development as a permanent nuclear waste and spent fuel repository. In February, the Secretary recommended to the President that the site be developed for licensed disposal of these wastes, and the President transmitted this recommendation to Congress. This paper summarizes key technical and national interest considerations that provided the basis for the recommendation. It also discusses the program's near-term plans for repository development if Congress designates the site.

  17. 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

    2009-01-01

    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...

  18. A Review Corrosion of TI Grade 7 and Other TI Alloys in Nuclear Waste Repository Environments

    SciTech Connect (OSTI)

    F. Hua; K. Mon; P. Pasupathi; G. Gordon

    2004-05-11

    Titanium alloy degradation modes are reviewed in relation to their performance in repository environments. General corrosion, localized corrosion, stress corrosion cracking, hydrogen induced cracking, microbially influenced corrosion, and radiation-assisted corrosion of Ti alloys are considered. With respect to the Ti Grade 7 drip shields selected for emplacement in the repository at Yucca Mountain, general corrosion, hydrogen induced cracking, and radiation-assisted corrosion will not lead to failure within the 10,000 year regulatory period; stress corrosion cracking (in the absence of disruptive events) is of no consequence to barrier performance; and localized corrosion and microbially influenced corrosion are not expected to occur. To facilitate the discussion, Ti Grades 2, 5, 7, 9, 11, 12, 16, 17, 18, and 24 are included in this review.

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

    SciTech Connect (OSTI)

    Hanke, P.M.

    1987-11-04

    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.

  20. State-of-the-art for evaluating the potential impact of flooding on a radioactive waste repository

    SciTech Connect (OSTI)

    Not Available

    1980-07-16

    This report is a review of the state-of-the-art for evaluating the potential impact of flooding on a deep radioactive-waste repository, namely, for predicting the future occurrence of catastrophic flooding and for estimating the effect of such flooding on waste containment characteristics. Several detrimental effects are identified: flooding can increase groundwater seepage velocities through a repository within the framework of the existing hydrologic system and thus increase the rate of radioactive-waste leakage to the biosphere; flooding may alter repository hydrology by reversing flow gradients, relocating sources of groundwater recharge and discharge, or shortening seepage paths, thereby producing unpredictable leakage; saturation of a vadose-zone repository during flooding can increase groundwater seepage velocities by several orders of magnitude; and flooding can damage repository-media containment properties by inducing seismic or chemical instability or increasing fracture permeability in relatively shallow repository rock as a result of redistributing in-situ stresses. Short-term flooding frequency and magnitude can be predicted statistically by analyzing historical records of flooding. However, long-term flooding events that could damage a permanent repository cannot be predicted with confidence because the geologic record is neither unique nor sufficienly complete for statistical analysis. It is more important to identify parameters characterizing containment properties (such as permeability, groundwater gradient, and shortest seepage path length to the biosphere) that could be affected by future flooding, estimate the maximum magnitude of flooding that could occur within the life of the repository by examining the geologic record, and determine the impact such flooding could have on the parameter values.

  1. Integrating rock mechanics issues with repository design through design process principles and methodology

    SciTech Connect (OSTI)

    Bieniawski, Z.T.

    1996-04-01

    A good designer needs not only knowledge for designing (technical know-how that is used to generate alternative design solutions) but also must have knowledge about designing (appropriate principles and systematic methodology to follow). Concepts such as {open_quotes}design for manufacture{close_quotes} or {open_quotes}concurrent engineering{close_quotes} are widely used in the industry. In the field of rock engineering, only limited attention has been paid to the design process because design of structures in rock masses presents unique challenges to the designers as a result of the uncertainties inherent in characterization of geologic media. However, a stage has now been reached where we are be able to sufficiently characterize rock masses for engineering purposes and identify the rock mechanics issues involved but are still lacking engineering design principles and methodology to maximize our design performance. This paper discusses the principles and methodology of the engineering design process directed to integrating site characterization activities with design, construction and performance of an underground repository. Using the latest information from the Yucca Mountain Project on geology, rock mechanics and starter tunnel design, the current lack of integration is pointed out and it is shown how rock mechanics issues can be effectively interwoven with repository design through a systematic design process methodology leading to improved repository performance. In essence, the design process is seen as the use of design principles within an integrating design methodology, leading to innovative problem solving. In particular, a new concept of {open_quotes}Design for Constructibility and Performance{close_quotes} is introduced. This is discussed with respect to ten rock mechanics issues identified for repository design and performance.

  2. 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.

    1980-08-01

    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.

  3. 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.

    1992-02-01

    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.

  4. An assessment of the effect on Olkiluoto repository capacity achievable with advanced fuel cycles

    SciTech Connect (OSTI)

    Juutilainen, P.; Viitanen, T.

    2013-07-01

    Previously a few scenarios have been simulated for transition from thermal to fast reactor fleet in Finland in order to determine how much the transuranic inventory could be reduced with the partitioning and transmutation (P-T) technologies. Those calculations, performed with COSI6 code developed by CEA, are extended in the present study, in which the effect of P-T on the capacity of the planned final disposal repository at Olkiluoto (Finland) is evaluated by taking into account the created fission products and transuranic residuals from the reprocessing operations. The decay heat is assumed to be the most restrictive factor in defining the waste disposal packing density. The repository capacity evaluation of this study is based on the comparison of the decay heats produced by the deposited waste in various scenarios. The reference scenario of this article involves only Light Water Reactors (LWR) in an open fuel cycle. The capacity requirement of the geological repository is estimated in a few closed fuel cycle scenarios, all including actinide transmutation with Fast Reactors (FR). The comparison between the P-T scenarios and reference is based on the decay heat production of the deposited waste. The COSI6 code is used for simulations to provide the repository decay heat curves. Applying the closed fuel cycle would change the disposal concept and schedule, because of which it is not quite straightforward to assess the impact of P-T on the capacity. However, it can be concluded that recycling the transuranic nuclides probably decreases the required volume for the disposal, but thermal dimensioning analysis is needed for more specific conclusions.

  5. Fueling Innovation and Adoption by Sharing Data on the DOE Geothermal Data Repository

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12, 2015ExecutiveFluorescentDanKathy gdr.openei.org Geothermal Data Repository

  6. 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.

    1991-07-01

    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.

  7. Gas Generation and Release in Near-Surface Repository at Armenian NPP - 13372

    SciTech Connect (OSTI)

    Grigoryan, G.; Amirjanyan, A.; Hovhannisyan, A.; Gondakyan, Y.

    2013-07-01

    The potential nuclear waste repository at Armenian Nuclear Power Plant (ANPP) can store Low and Intermediate Level Radioactive waste (LL/ILW). In this kind of near-surface repository for radioactive waste, significant quantities of gases may be generated as a result of microbial degradation and corrosion. A discussion is presented of the microbial and chemical degradation of cellulose. For the release of gas, it is assumed that the complete conversion of cellulosic wastes to gases by the action of microbes, is, in principle, permitted. Released radioactive gases such as {sup 14}CO{sub 2} and {sup 14}CH{sub 4} could have a direct pathway to the atmosphere. The potential impact of gas generation, accumulation and migration on the long-term of repository, should therefore be assessed properly. We present here safety assessment result of gas producing radioactive waste disposal by the inhalation dose to a maximally exposed individual above ground, based on some conservative assumptions about release from waste as well as gas generation calculations. (authors)

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

    SciTech Connect (OSTI)

    NONE

    1997-12-31

    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.

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

    SciTech Connect (OSTI)

    1985-04-01

    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. Debt collection project report

    SciTech Connect (OSTI)

    Not Available

    1980-05-01

    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)

  11. 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.

    2002-02-26

    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.

  12. 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.

  13. 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

    Office of Energy Efficiency and Renewable Energy (EERE)

    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

  14. A case study on the influence of THM coupling on the near field safety of a spent fuel repository in sparsely fractured granite

    E-Print Network [OSTI]

    Nguyen, T.S.

    2009-01-01

    Jonny Rutqvist 7 Canadian Nuclear Safety Commission, Ottawa,completion: the Canadian Nuclear Safety Commission (CNSC);repository is called a safety case (Nuclear Energy Agency,

  15. National Geoscience Data Repository System, Phase II. Final report, January 30, 1995--January 28, 1997

    SciTech Connect (OSTI)

    1998-04-01

    The American Geological Institute (AGI) has completed Phase II of a project to establish a National Geoscience Data Repository System (NGDRS). The project`s primary objectives are to preserve geoscience data in jeopardy of being destroyed and to make that data available to those who have a need to use it in future investigations. These data are available for donation to the public as a result of the downsizing that has occurred in the major petroleum and mining companies in the United States for the past decade. In recent years, these companies have consolidated domestic operations, sold many of their domestic properties and relinquished many of their leases. The scientific data associated with those properties are no longer considered to be useful assets and are consequently in danger of being lost forever. The national repository project will make many of these data available to the geoscience community for the first time. To address this opportunity, AGI sought support from the Department of Energy (DOE) in 1994 to initiate the NGDRS Phase I feasibility study to determine the types and quantity of data that companies would be willing to donate. The petroleum and mining companies surveyed indicated that they were willing to donate approximately five million well logs, one hundred million miles of seismic reflection data, millions of linear feet of core and cuttings, and a variety of other types of scientific data. Based on the positive results of the Phase I study, AGI undertook Phase II of the program in 1995. Funded jointly by DOE and industry, Phase II encompasses the establishment of standards for indexing and cataloging of geoscience data and determination of the costs of transferring data from the private sector to public-sector data repositories. Pilot projects evaluated the feasibility of the project for transfer of different data types and creation of a Web-based metadata supercatalog and browser.

  16. NREL's Field Data Repository Supports Accurate Home Energy Analysis (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2012-02-01

    This fact sheet discusses NREL's work to develop a repository of research-level residential building characteristics and historical energy use data to support ongoing efforts to improve the accuracy of residential energy analysis tools and the efficiency of energy assessment processes. The objective of this project is to create a robust empirical data source to support the research goals of the Department of Energy's Building America program, which is to improve the efficiency of existing U.S. homes by 30% to 50%. Researchers can use this data source to test the accuracy of building energy simulation software and energy audit procedures, ultimately leading to more credible and less expensive energy analysis.

  17. A FRAMEWORK FOR THE ANALYSIS OF LOCALIZED CORROSION AT THE PROPOSED YUCCA MOUNTAIN REPOSITORY

    SciTech Connect (OSTI)

    Dr. J.H. Payer

    2006-04-18

    Corrosion is a primary determinant of waste package performance at the proposed Yucca Mountain Repository: (1) the most likely degradation process; (2) controls the delay time for radionuclide transport from the waste package; and (3) determines when packages will be penetrated and the shape size and distribution of those penetrations. In this presentation a framework for the analysis of localized corrosion is presented and demonstrated for a scenario: (1) water chemistry of mixed salt solutions (sodium chloride-potassium nitrate); and (2) time-temperature-relative humidity profiles for a hot, mid and cool temperature waste package.

  18. Coupling of Nuclear Waste Form Corrosion and Radionuclide Transports in Presence of Relevant Repository Sediments

    SciTech Connect (OSTI)

    Wall, Nathalie A.; Neeway, James J.; Qafoku, Nikolla P.; Ryan, Joseph V.

    2015-09-30

    Assessments of waste form and disposal options start with the degradation of the waste forms and consequent mobilization of radionuclides. Long-term static tests, single-pass flow-through tests, and the pressurized unsaturated flow test are often employed to study the durability of potential waste forms and to help create models that predict their durability throughout the lifespan of the disposal site. These tests involve the corrosion of the material in the presence of various leachants, with different experimental designs yielding desired information about the behavior of the material. Though these tests have proved instrumental in elucidating various mechanisms responsible for material corrosion, the chemical environment to which the material is subject is often not representative of a potential radioactive waste repository where factors such as pH and leachant composition will be controlled by the near-field environment. Near-field materials include, but are not limited to, the original engineered barriers, their resulting corrosion products, backfill materials, and the natural host rock. For an accurate performance assessment of a nuclear waste repository, realistic waste corrosion experimental data ought to be modeled to allow for a better understanding of waste form corrosion mechanisms and the effect of immediate geochemical environment on these mechanisms. Additionally, the migration of radionuclides in the resulting chemical environment during and after waste form corrosion must be quantified and mechanisms responsible for migrations understood. The goal of this research was to understand the mechanisms responsible for waste form corrosion in the presence of relevant repository sediments to allow for accurate radionuclide migration quantifications. The rationale for this work is that a better understanding of waste form corrosion in relevant systems will enable increased reliance on waste form performance in repository environments and potentially decrease the need for expensive engineered barriers.Our current work aims are 1) quantifying and understanding the processes associated with glass alteration in contact with Fe-bearing materials; 2) quantifying and understanding the processes associated with glass alteration in presence of MgO (example of engineered barrier used in WIPP); 3) identifying glass alteration suppressants and the processes involved to reach glass alteration suppression; 4) quantifying and understanding the processes associated with Saltstone and Cast Stone (SRS and Hanford cementitious waste forms) in various representative groundwaters; 5) investigating positron annihilation as a new tool for the study of glass alteration; and 6) quantifying and understanding the processes associated with glass alteration under gamma irradiation.

  19. Portable data collection device

    DOE Patents [OSTI]

    French, P.D.

    1996-06-11

    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. 7 figs.

  20. Portable data collection device

    DOE Patents [OSTI]

    French, Patrick D. (Aurora, CO)

    1996-01-01

    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.

  1. Information Repository

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDid you notHeat Pumps Heat Pumpsfacility doe logoInIndustry @Information

  2. Information Repository

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation CurrentHenry Bellamy,ImpactScientificInfluence of Topological Spin0 Information

  3. Information Repository

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation CurrentHenry Bellamy,ImpactScientificInfluence of Topological Spin0

  4. Information Repository

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation CurrentHenry Bellamy,ImpactScientificInfluence of Topological Spin02

  5. Information Repository

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation CurrentHenry Bellamy,ImpactScientificInfluence of Topological Spin023

  6. Information Repository

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation CurrentHenry Bellamy,ImpactScientificInfluence of Topological Spin0234

  7. New Design for an HLW Repository (for Spent Fuel and Waste from Reprocessing) in a Salt Formation in Germany - 12213

    SciTech Connect (OSTI)

    Bollingerfehr, Wilhelm; Filbert, Wolfgang; Lerch, Christian; Mueller-Hoeppe, Nina; Charlier, Frank

    2012-07-01

    In autumn 2010, after a 10-year moratorium, exploration was resumed in Gorleben, the potential site for a German HLW repository. At the same time, the Federal Government launched a two-year preliminary safety analysis to assess whether the salt dome at Gorleben is suitable to host all heat-generating radioactive waste generated by German NPPs based on the waste amounts expected at that time. The revised Atomic Energy Act of June 2011 now stipulates a gradual phase-out of nuclear energy production by 2022, which is 13 years earlier than expected in 2010. A repository design was developed which took into account an updated set of data on the amounts and types of expected heat-generating waste, the documented results of the exploration of the Gorleben salt dome, and the new 'Safety Requirements Governing the Final Disposal of Heat-Generating Radioactive Waste' of 30 September, 2010. The latter has a strong influence on the conceptual designs as it requires that retrievability of all waste containers is possible within the repository lifetime. One design considered that all waste containers will be disposed of in horizontal drifts of a geologic repository, while the other design considered that all waste containers will be disposed of in deep vertical boreholes. For both options (emplacement in drifts/emplacement in vertical boreholes), the respective design includes a selection of waste containers, the layout of drifts, respectively lined boreholes, a description of emplacement fields, and backfilling and sealing measures. The design results were described and displayed and the differences between the two main concepts were elaborated and discussed. For the first time in both repository designs the requirement was implemented to retrieve waste canisters during the operational phase. The measures to fulfill this requirement and eventually the consequences were highlighted. It was pointed out that there arises the need to keep transport- and storage casks in adequate numbers and interim storage facilities available until the repository is closed. (authors)

  8. Information Collection Management Program

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

    2006-10-11

    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.

  9. 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

  10. 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

  11. Carbon-14 in waste packages for spent fuel in a tuff repository

    SciTech Connect (OSTI)

    Van Konynenburg, R.A.; Smith, C.F.; Culham, H.W.; Smith, H.D.

    1986-10-14

    Carbon-14 is produced naturally by cosmic ray neutrons in the upper atmosphere. It is also produced in nuclear reactors, in amounts much smaller than the global inventory. About one-third of this is released directly to the atmosphere, and the other two-thirds remains in the spent fuel. Both the Environmental Protection Agency and the Nuclear Regulatory Commission have established limits on release of the {sup 14}C in spent fuel. This is of particular concern for the proposed repository in tuff, because of the unsaturated conditions and the consequent possibility of gaseous transport of {sup 14}C as CO{sub 2}. Existing measurements and calculations of the {sup 14}C inventory in spent fuel are reviewed. The physical distribution and chemical forms of the {sup 14}C are discussed. Available data on the release of {sup 14}C from spent fuel in aqueous solutions and in gaseous environments of air, nitrogen, and helium are reviewed. Projected {sup 14}C behavior in a tuff repository is described. It is concluded that {sup 14}C release measurements from spent fuel into moist air at temperatures both above and below the in situ boiling point of water as well as detailed transport calculations for the tuff geological environment will be needed to determine whether the 10CFR60 and 40CFR191 requirements can be met. 56 refs., 1 tab.

  12. Canada's Deep Geological Repository for Used Nuclear Fuel - Geo-scientific Site Evaluation Process - 13117

    SciTech Connect (OSTI)

    Blyth, Alec; Ben Belfadhel, Mahrez; Hirschorn, Sarah; Hamilton, Duncan; McKelvie, Jennifer

    2013-07-01

    The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management (APM), the approach selected by the Government of Canada for long-term management of used nuclear fuel generated by Canadian nuclear reactors. The ultimate objective of APM is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository in a suitable rock formation at a depth of approximately 500 meters (m) (1,640 feet [ft]). In May 2010, the NWMO published a nine-step site selection process that serves as the road map to decision-making on the location for the deep geological repository. The safety and appropriateness of any potential site will be assessed against a number of factors, both technical and social in nature. The selected site will be one that can be demonstrated to be able to safely contain and isolate used nuclear fuel, protecting humans and the environment over the very long term. The geo-scientific suitability of potential candidate sites will be assessed in a stepwise manner following a progressive and thorough site evaluation process that addresses a series of geo-scientific factors revolving around five safety functions. The geo-scientific site evaluation process includes: Initial Screenings; Preliminary Assessments; and Detailed Site Evaluations. As of November 2012, 22 communities have entered the site selection process (three in northern Saskatchewan and 18 in northwestern and southwestern Ontario). (authors)

  13. Implications of Plutonium isotopic separation on closed fuel cycles and repository design

    SciTech Connect (OSTI)

    Forsberg, C.

    2013-07-01

    Advances in laser enrichment may enable relatively low-cost plutonium isotopic separation. This would have large impacts on LWR closed fuel cycles and waste management. If Pu-240 is removed before recycling plutonium as mixed oxide (MOX) fuel, it would dramatically reduce the buildup of higher plutonium isotopes, Americium, and Curium. Pu-240 is a fertile material and thus can be replaced by U-238. Eliminating the higher plutonium isotopes in MOX fuel increases the Doppler feedback, simplifies reactor control, and allows infinite recycle of MOX plutonium in LWRs. Eliminating fertile Pu-240 and Pu-242 reduces the plutonium content in MOX fuel and simplifies fabrication. Reducing production of Pu-241 reduces production of Am-241 - the primary heat generator in spent nuclear fuels after several decades. Reducing heat generating Am-241 would reduce repository cost and waste toxicity. Avoiding Am- 241 avoids its decay product Np-237, a nuclide that partly controls long-term oxidizing repository performance. Most of these benefits also apply to LWR plutonium recycled into fast reactors. There are benefits for plutonium isotopic separation in fast reactor fuel cycles (particularly removal of Pu-242) but the benefits are less. (author)

  14. Considerations on the Release of C-14 from a Closed Final Repository for Low-Level Radioactive Waste

    SciTech Connect (OSTI)

    Bracke, G.; Muller, W. [ISTec - Institute for Safety Technology, Cologne (Germany)

    2007-07-01

    The contribution of C-14 to radiation exposure in the biosphere from a repository for low-level radioactive waste can be significant. The release pathways of C-14 and processes relevant to its release from a closed final repository for low-level radioactive waste are discussed. Because a conservative approach may lead to undue overestimation of the potential radiation exposure, a more realistic approach is outlined. At the present level of refinement, it has sufficient safety margins to federal limits for radiation exposure to demonstrate compliance with the ALARA (as low as reasonably achievable) principle and thus facilitate licence approval. (authors)

  15. Two phase partially miscible flow and transport modeling in porous media: application to gas migration in a nuclear waste repository

    E-Print Network [OSTI]

    Bourgeat, Alain; Smaï, Farid

    2008-01-01

    We derive a compositional compressible two-phase, liquid and gas, flow model for numerical simulations of hydrogen migration in deep geological repository for radioactive waste. This model includes capillary effects and the gas high diffusivity. Moreover, it is written in variables (total hydrogen mass density and liquid pressure) chosen in order to be consistent with gas appearance or disappearance. We discuss the well possedness of this model and give some computational evidences of its adequacy to simulate gas generation in a water saturated repository.

  16. Two phase partially miscible flow and transport modeling in porous media: application to gas migration in a nuclear waste repository

    E-Print Network [OSTI]

    Alain Bourgeat; Mladen Jurak; Farid Smaï

    2008-02-29

    We derive a compositional compressible two-phase, liquid and gas, flow model for numerical simulations of hydrogen migration in deep geological repository for radioactive waste. This model includes capillary effects and the gas high diffusivity. Moreover, it is written in variables (total hydrogen mass density and liquid pressure) chosen in order to be consistent with gas appearance or disappearance. We discuss the well possedness of this model and give some computational evidences of its adequacy to simulate gas generation in a water saturated repository.

  17. Workshop on the source term for radionuclide migration from high-level waste or spent nuclear fuel under realistic repository conditions: proceedings

    SciTech Connect (OSTI)

    Hunter, T.O.; Muller, A.B. (eds.)

    1985-07-01

    Sixteen papers were presented at the workshop. The fourteen full-length papers included in the proceedings were processed separately. Only abstracts were included for the following two papers: Data Requirements Based on Performance Assessment Analyses of Conceptual Waste Packages in Salt Repositories, and The Potential Effects of Radiation on the Source Term in a Salt Repository. (LM)

  18. Generic Repository Concepts and Thermal Analysis for Advanced Fuel Cycles - 12477

    SciTech Connect (OSTI)

    Hardin, Ernest [Sandia National Laboratories, P.O. Box 5800 MS 0736, Albuquerque, NM 87185 (United States); Blink, James [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94551-0808 (United States); Carter, Joe [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States); Fratoni, Massimiliano; Greenberg, Harris; Sutton, Mark [Lawrence Livermore National Laboratory (United States); Howard, Robert [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States)

    2012-07-01

    A geologic disposal concept for spent nuclear fuel (SNF) or high-level waste (HLW) consists of three components: waste inventory, geologic setting, and concept of operations. A set of reference geologic disposal concepts has been developed by the U.S. Department of Energy (DOE), Used Fuel Disposition campaign. Reference concepts are identified for crystalline rock, clay/shale, bedded salt, and deep borehole (crystalline basement) geologic settings. These were analyzed for waste inventory cases representing a range of waste types that could be produced by advanced nuclear fuel cycles. Concepts of operation consisting of emplacement mode, repository layout, and engineered barrier descriptions, were selected based on international progress. All of these disposal concepts are enclosed emplacement modes, whereby waste packages are in direct contact with encapsulating engineered or natural materials. Enclosed modes have less capacity to dissipate heat than open modes such as that proposed for a repository at Yucca Mountain. Thermal analysis has identified important relationships between waste package size and capacity, and the duration of surface decay storage needed to meet temperature limits for different disposal concepts. For the crystalline rock and clay/shale repository concepts, a waste package surface temperature limit of 100 deg. C was assumed to prevent changes in clay-based buffer material or clay-rich host rock. Surface decay storage of 50 to 100 years is needed for disposal of high-burnup LWR SNF in 4-PWR packages, or disposal of HLW glass from reprocessing LWR uranium oxide (UOX) fuel. High-level waste (HLW) from reprocessing of metal fuel used in a fast reactor could be disposed after decay storage of 50 years or less. For disposal in salt the rock thermal conductivity is significantly greater, and higher temperatures (200 deg. C) can be tolerated at the waste package surface. Decay storage of 10 years or less is needed for high-burnup LWR SNF in 4-PWR packages, while 12-PWR packages could be emplaced after 40 years or less. HLW from reprocessing LWR UOX fuel or metal fuel from fast reactors, could be disposed of in salt after 10 to 50 years of decay storage depending on the specific composition and other factors. For the deep borehole disposal concept no near-field temperature limits are recognized because no performance credit is taken for waste form or waste package integrity, or containment by the near-field host rock. These results show the key differences in thermal management strategies available to the U.S. repository program, given the range of disposal concepts. A host medium such as salt with greater thermal conductivity and peak temperature tolerance could shorten decay storage by 50 years, or facilitate the use of larger waste packages. The LWR UOX SNF evaluated in this study represents that which could be produced in the coming decades. The existing, lower burnup used fuel that is presently in storage at many LWR locations across the U.S. is significantly cooler, and analyses of this type could be used to show that disposal is possible with less decay storage or larger waste packages. We note that while the temperature limits and waste package capacities used in this study are similar to those used internationally and in past U.S. studies, they might be increased as the result of ongoing research and development activities. This study selected enclosed emplacement modes to conform with disposal concepts developed internationally and previously in the U.S. Open modes (such as that proposed for a repository at Yucca Mountain) afford additional flexibility in waste management and the necessary investment, because the same facility serves both storage and disposal functions. Use of open modes, and combined analysis of storage, transportation, and disposal functions, are appropriate to consider in future studies of this type. (authors)

  19. Wichita State University Football Team Airplane Crash Collection Collection Summary

    E-Print Network [OSTI]

    Wichita State University Football Team Airplane Crash Collection Collection Summary Title: Wichita State University Football Team Airplane Crash Collection Call Number: MS 87-11 Size: 12.0 linear feet University Football Team Airplane Crash Collection contains various documents relating to the airplane crash

  20. Collective network routing

    DOE Patents [OSTI]

    Hoenicke, Dirk

    2014-12-02

    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. Schema Repository for Database Schema Evolution1 This work is carried out as part of IM2 ( Interactive Multimodal Information Management) (http://www.im2.ch), Swiss National Competence Centre

    E-Print Network [OSTI]

    Pottinger, Rachel

    Schema Repository for Database Schema Evolution1 1 This work is carried out as part of IM2 of database schemas. The repository is part of a multidisciplinary approach for schema evolution called the predictive approach for database evolution. The schema repository has a dual role in the approach: (1) during

  2. Portable liquid collection electrostatic precipitator

    DOE Patents [OSTI]

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

    2005-10-18

    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.

  3. Uniting software tools for the archival, management and analysis of linguistic data: lessons from developing the Language Data Repository 

    E-Print Network [OSTI]

    Audenaert, Michael Neal

    2013-02-22

    " accessible system, providing specific examples from the system I have been working to develop, the Language Data Repository (LDR). I will conclude by laying out areas of future work, both for the development of the LDR and for the community in general....

  4. ACCELERATOR PHYSICS CODE WEB REPOSITORY F. Zimmermann, R. Basset, G. Bellodi, E. Benedetto, U. Dorda, M. Giovannozzi, Y. Papaphilippou,

    E-Print Network [OSTI]

    Sen, Tanaji

    . Franchetti, I. Hofmann, GSI, Germany; S. Machida, RAL, UK; J. Wei, BNL, USA Abstract In the framework. We describe the design, structure and contents of this repository, illustrate its usage, and dis Physics and Synchrotron De- sign" (APD) work package [1] of the CARE [2] network on "High Energy High

  5. Salt Disposal Investigations to Study Thermally Hot Radioactive Waste In A Deep Geologic Repository in Bedded Rock Salt - 12488

    SciTech Connect (OSTI)

    Nelson, Roger A. [DOE, Carlsbad Field Office, Carlsbad NM (United States); Buschman, Nancy [DOE, Office of Environmental Management, Washington DC (United States)

    2012-07-01

    A research program is proposed to investigate the behavior of salt when subjected to thermal loads like those that would be present in a high-level waste repository. This research would build upon results of decades of previous salt repository program efforts in the US and Germany and the successful licensing and operation of a repository in salt for disposal of defense transuranic waste. The proposal includes a combination of laboratory-scale investigations, numerical simulations conducted to develop validated models that could be used for future repository design and safety case development, and a thermal field test in an underground salt formation with a configuration that replicates a small portion of a conceptual repository design. Laboratory tests are proposed to measure salt and brine properties across and beyond the range of possible repository conditions. Coupled numerical models will seek to describe phenomenology (thermal, mechanical, and hydrological) observed in the laboratory tests. Finally, the field test will investigate many phenomena that have been variously cited as potential issues for disposal of thermally hot waste in salt, including buoyancy effects and migration of pre-existing trapped brine up the thermal gradient (including vapor phase migration). These studies are proposed to be coordinated and managed by the Carlsbad Field Office of DOE, which is also responsible for the operation of the Waste Isolation Pilot Plant (WIPP) within the Office of Environmental Management. The field test portion of the proposed research would be conducted in experimental areas of the WIPP underground, far from disposal operations. It is believed that such tests may be accomplished using the existing infrastructure of the WIPP repository at a lower cost than if such research were conducted at a commercial salt mine at another location. The phased field test is proposed to be performed over almost a decade, including instrumentation development, several years of measurements during heating and then subsequent cooling periods, and the eventual forensic mining back of the test bed to determine the multi-year behavior of the simulated waste/rock environment. Funding possibilities are described, and prospects for near term start-up are discussed. Mining of the access drifts required to create the test area in the WIPP underground began in November 2011. Because this mining uses existing WIPP infrastructure and labor, it is estimated to take about two years to complete the access drifts. WIPP disposal operations and facility maintenance activities will take priority over the SDI field test area mining. Funding of the SDI proposal was still being considered by DOE's Offices of Environmental Management and Nuclear Energy at the time this paper was written, so no specific estimates of the progress in 2012 have been included. (authors)

  6. Nucleic Acid Database: a Repository of Three-Dimensional Information about Nucleic Acids

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Berman, H. M.; Olson, W. K.; Beveridge, D. L.; Westbrook, J.; Gelbin, A.; Demeny, T.; Hsieh, S. H.; Srinivasan, A. R.; Schneider, B.

    The Nucleic Acid Database (NDB) provides 3-D structural information about nucleic acids.  It is a relational database designed to facilitate the easy search for nucleic acid structures using any of the stored primary or derived structural features. Reports can then be created describing any properties of the selected structures and structures may be viewed in several different formats, including the mmCIF format, the NDB Atlas format, the NDB coordinate format, or the PDB coordinate format. Browsing structure images created directly from coordinates in the repository can also be done. More than 7000 structures have been released as of May 2014. This website also includes a number of specialized tools and interfaces. The NDB Project is funded by the National Institutes of Health and has been funded by the National Science Foundation and the Department of Energy in the past.

  7. Characteristics of potential repository wastes. Peer review report for revision 1 of DOE/RW-0184

    SciTech Connect (OSTI)

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

    1992-10-01

    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.

  8. Environmental Stress Pathway Project (ESSP) Data in EIDR, the Experimental Information and Data Repository

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Arkin, Adam [LBNL; Hazen, Terry [LBNL

    ESPP is developing computational models that describe and predict the behavior of gene regulatory networks in microbes in response to the environmental conditions found in DOE waste sites. The research takes place within the Virtual Institue for Microbial Stress and Survival (VIMSS). ESPP data files are stored on one of the VIMSS file servers. They include data generated by project participants, as well as links to data stored either in BioFiles or in the Experimental Data Repository. A searchable information database, EIDR, provides links to the data files and information about the data, including design information about biomass production experiments, information about the lab analyses that generated the data, and links to more detailed information, displays, or analyses. EIDR contains more than 3000 data uploads. (Specialized Interface)

  9. Assessment of effectiveness of geologic isolation systems. Test case release consequence analysis for a spent fuel repository in bedded salt

    SciTech Connect (OSTI)

    Raymond, J.R.; Bond, F.W.; Cole, C.R.; Nelson, R.W.; Reisenauer, A.E.; Washburn, J.F.; Norman, N.A.; Mote, P.A.; Segol, G.

    1980-01-01

    Geologic and geohydrologic data for the Paradox Basin have been used to simulate movement of ground water and radioacrtive contaminants from a hypothetical nuclear reactor spent fuel repository after an assumed accidental release. The pathlines, travel times and velocity of the ground water from the repository to the discharge locale (river) were determined after the disruptive event by use of a two-dimensional finite difference hydrologic model. The concentration of radioactive contaminants in the ground water was calculated along a series of flow tubes by use of a one-dimensional mass transport model which takes into account convection, dispersion, contaminant/media interactions and radioactive decay. For the hypothetical site location and specific parameters used in this demonstration, it is found that Iodine-129 (I-129) is tthe only isotope reaching the Colorado River in significant concentration. This concentration occurs about 8.0 x 10/sup 5/ years after the repository has been breached. This I-129 ground-water concentration is about 0.3 of the drinking water standard for uncontrolled use. The groundwater concentration would then be diluted by the Colorado River. None of the actinide elements reach more than half the distance from the repository to the Colorado River in the two-million year model run time. This exercise demonstrates that the WISAP model system is applicable for analysis of contaminant transport. The results presented in this report, however, are valid only for one particular set of parameters. A complete sensitivity analysis must be performed to evaluate the range of effects from the release of contaminants from a breached repository.

  10. Kraith Collected Issue 4 

    E-Print Network [OSTI]

    Lichtenberg, Jacqueline; Clark, Beverly

    1974-01-01

    of the insert. The top of page 14 starts "Through Time and Tear!>". To the bottom of page 15 is untouched. I cut two paragraphs between "unrest" and "I'm so happy". They dealt with Sarek deciding that the proper course of events should be to adopt Kirk...-1 kRAITh coLLeCT?b volume 4 ?blTORS pREfAC? This is m.y first issue as editor of Kraith Collected. This strange state of affairs began when I had the time to type the rrRnuscripts which make up this is!'''e. Then Carol handed down the ultimatum: It...

  11. PROJECTED IMPACT OF SULFATE ATTACK ON THE LONG-TERM PERFORMANCE OF A CONCRETE REPOSITORY

    SciTech Connect (OSTI)

    Flach, G.

    2009-12-11

    Saltstone is a cementitious waste form made by mixing salt solution originating from liquid waste storage tanks at the DOE Savannah River Site with a dry mix containing blast furnace slag, fly ash, and cement or lime. The wet mix is poured into a concrete repository for on-site disposal. Solidified Saltstone is a dense, alkaline, reducing, micro-porous, monolithic, cementitious matrix, containing a solution of salts within its pore structure. Sodium sulfate concentrations in the pore fluid are around 0.15 mol/L, and external sulfate attack on concrete barriers is expected to occur over time. To predict the long-term performance of concrete repositories, the STADIUM{reg_sign} code was used to simulate the reactive transport processes leading to formation of ettringite, an expansive mineral phase often associated with spalling or cracking. STADIUM{reg_sign} is a multi-ionic transport model based on a split operator approach that separates ionic movement and chemical reactions. Ionic transport is described by the extended Nernst-Planck equation for unsaturated media, and accounts for electrical coupling between ionic species, chemical activity, transport due to water content gradient, and temperature effects. STADIUM{reg_sign} does not predict whether physical damage will occur, or the impact on transport properties should fracturing occur. Thus the presence of ettringite was assumed to coincide with physical damage for the purpose of estimating effective transport properties. Effective properties for concrete barriers were estimated assuming complete hydraulic failure behind the ettringite front and unaltered properties ahead of the front. The ettringite front advances at a rate dependent on the diffusion coefficient assumed for the failed zone. A sensitivity study indicates a service life ranging from thousands to tens of thousands of years, depending on the barrier thickness and sulfate exposure conditions among other factors.

  12. The Economic, repository and proliferation implications of advanced nuclear fuel cycle

    SciTech Connect (OSTI)

    Deinert, Mark; Cady, K B

    2011-09-04

    The goal of this project was to compare the effects of recycling actinides using fast burner reactors, with recycle that would be done using inert matrix fuel burned in conventional light water reactors. In the fast reactor option, actinides from both spent light water and fast reactor fuel would be recycled. In the inert matrix fuel option, actinides from spent light water fuel would be recycled, but the spent inert matrix fuel would not be reprocessed. The comparison was done over a limited 100-year time horizon. The economic, repository and proliferation implications of these options all hinge on the composition of isotopic byproducts of power production. We took the perspective that back-end economics would be affected by the cost of spent fuel reprocessing (whether conventional uranium dioxide fuel, or fast reactor fuel), fuel manufacture, and ultimate disposal of high level waste in a Yucca Mountain like geological repository. Central to understanding these costs was determining the overall amount of reprocessing needed to implement a fast burner, or inert matrix fuel, recycle program. The total quantity of high level waste requiring geological disposal (along with its thermal output), and the cost of reprocessing were also analyzed. A major advantage of the inert matrix fuel option is that it could in principle be implemented using the existing fleet of commercial power reactors. A central finding of this project was that recycling actinides using an inert matrix fuel could achieve reductions in overall actinide production that are nearly very close to those that could be achieved by recycling the actinides using a fast burner reactor.

  13. GEOCHEMISTRY OF ROCK UNITS AT THE POTENTIAL REPOSITORY LEVEL, YUCCA MOUNTAIN, NEVADA

    SciTech Connect (OSTI)

    Z.E. Peterman; P.L. Cloke

    2000-12-13

    The compositional variability of the phenocryst-poor member of the 12.8-million-year Topopah Spring Tuff at the potential repository level was assessed by duplicate analysis of 20 core samples from the cross drift at Yucca Mountain, Nevada. Previous analyses of outcrop and core samples of the Topopah Spring Tuff showed that the phenocryst-poor rhyolite, which includes both lithophysal and nonlithophysal zones, is relatively uniform in composition. Analyses of rock samples from the cross drift, the first from the actual potential repository block, also indicate the chemical homogeneity of this unit excluding localized deposits of vapor-phase minerals and low-temperature calcite and opal in fractures, cavities, and faults, The possible influence of vapor-phase minerals and calcite and opal coatings on rock composition at a scale sufficiently large to incorporate these heterogeneously distributed deposits was evaluated and is considered to be relatively minor. Therefore, the composition of the phenocryst-poor member of the Topopah Spring Tuff is considered to be adequately represented by the analyses of samples from the cross drift. The mean composition as represented by the 10 most abundant oxides in weight percent or grams per hundred grams is: SiO{sub 2}, 76.29; Al{sub 2}O{sub 3}, 12.55; FeO, 0.14; Fe{sub 2}O{sub 3}, 0.97; MgO, 0.13; CaO, 0.50; Na{sub 2}O, 3.52; K{sub 2}O, 4.83; TiO{sub 2}, 0.11; and MnO, 0.07.

  14. Chapter 9 GIS Data Collection 117 GIS Data Collection

    E-Print Network [OSTI]

    Wright, Dawn Jeannine

    Chapter 9 GIS Data Collection 117 GIS Data Collection OVERVIEW This chapter reviews the main methods of GIS data capture and transfer and introduces key practical management issues. It distinguishes, OCR 9 #12;Chapter 9 GIS Data Collection 118 OUTLINE 9.1 Introduction 9.2 Primary geographic data

  15. Collective systems for creative expression

    E-Print Network [OSTI]

    Ar?kan, Harun Burak

    2006-01-01

    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 ...

  16. Collective Acceleration in Solar Flares

    E-Print Network [OSTI]

    Barletta, W.

    2008-01-01

    Collective Acceleration in Solar Flares w. Barletta, S.S.COLLECTIVE ACCELERATION IN SOLAR FLARES* W. Barletta (1), S.Park, MD 20742 Abstract Solar flare data are examined with

  17. 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)

    1993-10-01

    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.

  18. 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

  19. ESTIMATING RETARDATION FROM THE FREUNDLICH ISOTHERM FOR MODELING CONTAMINANT TRANSPORT

    E-Print Network [OSTI]

    Coles, Cynthia

    to model leachate migration from landfills is needed to protect the public and the environment. Introduction A concern with landfills, and especially older unlined landfills, is the migration of leachate risk of off-site leachate migration at newer, lined landfills with leachate collection systems

  20. RoMEO Green at the University of Kansas: An experiment to encourage interest and participation among faculty and jumpstart populating the KU ScholarWorks Repository

    E-Print Network [OSTI]

    Mercer, Holly; Emmett, Ada

    2005-10-01

    Universities around the world are beginning to develop digital repositories in order to offer new methods for the distribution and preservation of the intellectual output of their faculty. The University of Kansas (KU) is ...

  1. EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada

    Broader source: Energy.gov [DOE]

    This EIS analyzes DOE's proposed action to construct, operate, monitor, and eventually close a geologic repository at Yucca Mountain  for the disposal of spent nuclear fuel and high-level...

  2. Precipitation-Front Modeling: Issues Relating to Nucleation and Metastable Precipitation in the Planned Nuclear Waste Repository at Yucca Mountain, Nevada

    E-Print Network [OSTI]

    Apps, J.A.; Sonnenthal, E.L.

    2004-01-01

    Mineralogic Model of Yucca Mountain, Nevada, Rev. 1. Reportfor fracture sealing at Yucca Mountain, Nevada. Journal ofWaste Repository at Yucca Mountain, Nevada J.A. Apps and

  3. PROCEEDINGS OF WORKSHOP ON THERMOMECHANICAL-HYDROCHEMICAL MODELING FOR A HARDROCK WASTE REPOSITORY. JULY 29-31, 1980. MARRIOTT INN, BERKELEY, CA

    E-Print Network [OSTI]

    Authors, Various

    2010-01-01

    Status of the Hydrogeology for the WIPP G. Barr and D.75 K Watt/Acre Repository at the WIPP Site," CSI-2053-04, inof the Hydrogeology for the WIPP- G. E. Barr and D. D.

  4. Solar energy collection system

    SciTech Connect (OSTI)

    Hummel, R.L.

    1982-04-06

    A solar energy collection system for a building is described. A solar energy collector is disposed at the exterior surface of the building and includes a solar energy absorbent body having a surface which is exposed to sunlight and from which solar energy can be transmitted as sensible heat. A panel which is transparent to sunlight is spaced from the said surface of the absorbent body so as to define therewith a passageway in which air contacts at least a substantial area of said surface so that air in said passageway absorbs heat transmitted from said surface when the collector is in use. The passageway has an inlet and an outlet and the absorbent body and panel are arranged with the outlet higher than the inlet so that heated air in the passageway tends to rise by convection towards the outlet. The building is provided with heating means including a circulation circuit for a heating fluid. Heat exchange means are coupled to said air passageway outlet of the solar energy collector for passage of heated air therethrough. The heat exchange means are also coupled to the circulation circuit of the building heating means and are arranged to permit heat transfer between said heated air and the heating fluid. A return air flow conduit is coupled between the heat exchange means and the inlet of the air passageway of the solar energy collector for returning heated air from the heat exchange means to the air passageway for recirculation.

  5. Use of groundwater lifetime expectancy for the performance assessment of a deep geologic waste repository: 1. Theory, illustrations, and implications

    E-Print Network [OSTI]

    Cornaton, F J; Normani, S D; Sudicky, E A; Sykes, J F

    2011-01-01

    Long-term solutions for the disposal of toxic wastes usually involve isolation of the wastes in a deep subsurface geologic environment. In the case of spent nuclear fuel, if radionuclide leakage occurs from the engineered barrier, the geological medium represents the ultimate barrier that is relied upon to ensure safety. Consequently, an evaluation of radionuclide travel times from a repository to the biosphere is critically important in a performance assessment analysis. In this study, we develop a travel time framework based on the concept of groundwater lifetime expectancy as a safety indicator. Lifetime expectancy characterizes the time that radionuclides will spend in the subsurface after their release from the repository and prior to discharging into the biosphere. The probability density function of lifetime expectancy is computed throughout the host rock by solving the backward-in-time solute transport adjoint equation subject to a properly posed set of boundary conditions. It can then be used to defi...

  6. Preliminary total-system analysis of a potential high-level nuclear waste repository at Yucca Mountain

    SciTech Connect (OSTI)

    Eslinger, P.W.; Doremus, L.A.; Engel, D.W.; Miley, T.B.; Murphy, M.T.; Nichols, W.E.; White, M.D. [Pacific Northwest Lab., Richland, WA (United States); Langford, D.W.; Ouderkirk, S.J. [Westinghouse Hanford Co., Richland, WA (United States)

    1993-01-01

    The placement of high-level radioactive wastes in mined repositories deep underground is considered a disposal method that would effectively isolate these wastes from the environment for long periods of time. This report describes modeling performed at PNL for Yucca Mountain between May and November 1991 addressing the performance of the entire repository system related to regulatory criteria established by the EPA in 40 CFR Part 191. The geologic stratigraphy and material properties used in this study were chosen in cooperation with performance assessment modelers at Sandia National Laboratories (SNL). Sandia modeled a similar problem using different computer codes and a different modeling philosophy. Pacific Northwest Laboratory performed a few model runs with very complex models, and SNL performed many runs with much simpler (abstracted) models.

  7. Death Valley Lower Carbonate Aquifer Monitoring Program Wells Down Gradient of the Proposed Yucca Mountain Nuclear Waste Repository, U. S. Department of Energy Grant DE-RW0000233 2010 Project Report, prepared by The Hydrodynamics Group, LLC for Inyo County Yucca Mountain Repository Assessment Office

    SciTech Connect (OSTI)

    King, Michael J; Bredehoeft, John D., Dr.

    2010-09-03

    Inyo County completed the first year of the U.S. Department of Energy Grant Agreement No. DE-RW0000233. This report presents the results of research conducted within this Grant agreement in the context of Inyo County's Yucca Mountain oversight program goals and objectives. The Hydrodynamics Group, LLC prepared this report for Inyo County Yucca Mountain Repository Assessment Office. The overall goal of Inyo County's Yucca Mountain research program is the evaluation of far-field issues related to potential transport, by ground water, of radionuclide into Inyo County, including Death Valley, and the evaluation of a connection between the Lower Carbonate Aquifer (LCA) and the biosphere. Data collected within the Grant is included in interpretive illustrations and discussions of the results of our analysis. The centeral elements of this Grant prgoram was the drilling of exploratory wells, geophysical surveys, geological mapping of the Southern Funeral Mountain Range. The cullimination of this research was 1) a numerical ground water model of the Southern Funeral Mountain Range demonstrating the potential of a hydraulic connection between the LCA and the major springs in the Furnace Creek area of Death Valley, and 2) a numerical ground water model of the Amargosa Valley to evaluate the potential for radionuclide transport from Yucca Mountain to Inyo County, California. The report provides a description of research and activities performed by The Hydrodynamics Group, LLC on behalf of Inyo County, and copies of key work products in attachments to this report.

  8. Initial demonstration of the NRC`s capability to conduct a performance assessment for a High-Level Waste Repository

    SciTech Connect (OSTI)

    Codell, R.; Eisenberg, N.; Fehringer, D.; Ford, W.; Margulies, T.; McCartin, T.; Park, J.; Randall, J.

    1992-05-01

    In order to better review licensing submittals for a High-Level Waste Repository, the US Nuclear Regulatory Commission staff has expanded and improved its capability to conduct performance assessments. This report documents an initial demonstration of this capability. The demonstration made use of the limited data from Yucca Mountain, Nevada to investigate a small set of scenario classes. Models of release and transport of radionuclides from a repository via the groundwater and direct release pathways provided preliminary estimates of releases to the accessible environment for a 10,000 year simulation time. Latin hypercube sampling of input parameters was used to express results as distributions and to investigate model sensitivities. This methodology demonstration should not be interpreted as an estimate of performance of the proposed repository at Yucca Mountain, Nevada. By expanding and developing the NRC staff capability to conduct such analyses, NRC would be better able to conduct an independent technical review of the US Department of Energy (DOE) licensing submittals for a high-level waste (HLW) repository. These activities were divided initially into Phase 1 and Phase 2 activities. Additional phases may follow as part of a program of iterative performance assessment at the NRC. The NRC staff conducted Phase 1 activities primarily in CY 1989 with minimal participation from NRC contractors. The Phase 2 activities were to involve NRC contractors actively and to provide for the transfer of technology. The Phase 2 activities are scheduled to start in CY 1990, to allow Sandia National Laboratories to complete development and transfer of computer codes and the Center for Nuclear Waste Regulatory Analyses (CNWRA) to be in a position to assist in the acquisition of the codes.

  9. The Waste Isolation Pilot Plant Deep Geological Repository: A Domestic and Global Blueprint for Safe Disposal of High-Level Radioactive Waste - 12081

    SciTech Connect (OSTI)

    Eriksson, Leif G. [Nuclear Waste Dispositions, Winter Park, Florida 32789 (United States); Dials, George E. [B and W Conversion Services, LLC, Lexington, Kentucky 40513 (United States)

    2012-07-01

    At the end of 2011, the world's first used/spent nuclear fuel and other long-lived high-level radioactive waste (HLW) repository is projected to open in 2020, followed by two more in 2025. The related pre-opening periods will be at least 40 years, as it also would be if USA's candidate HLW-repository is resurrected by 2013. If abandoned, a new HLW-repository site would be needed. On 26 March 1999, USA began disposing long-lived radioactive waste in a deep geological repository in salt at the Waste Isolation Pilot Plant (WIPP) site. The related pre-opening period was less than 30 years. WIPP has since been re-certified twice. It thus stands to reason the WIPP repository is the global proof of principle for safe deep geological disposal of long-lived radioactive waste. It also stands to reason that the lessons learned since 1971 at the WIPP site provide a unique, continually-updated, blueprint for how the pre-opening period for a new HLW repository could be shortened both in the USA and abroad. (authors)

  10. Salt Repository Project site study plan for meteorology/air quality: Revision 1

    SciTech Connect (OSTI)

    Not Available

    1987-12-01

    The Site Study Plan for Meteorology/Air Quality describes a field program consisting of continuous measurements of wind speed and direction, temperature, humidity, dew point, and pressure neede for later modeling and dose calculations. These measurements will include upper level winds, vertical temperature structure, and vertical wind speed. All measurements will be made at a site located within the 9-m/sup 2/ site area but remote from the ESF. The SSP describes the need for each study; its design and design rationale; analysis, management, and use of data; schedule of field activities, organization of field personnel and sample management and quality assurance requirements. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Project Requirements Document. Although titled Meteorology/Air Quality, this SSP addresses only meteorology, as there are no air quality data needs in the SCP. A correction to the title will be made in a later revision. 27 refs., 6 figs., 3 tabs.

  11. SUMO, System performance assessment for a high-level nuclear waste repository: Mathematical models

    SciTech Connect (OSTI)

    Eslinger, P.W.; Miley, T.B.; Engel, D.W.; Chamberlain, P.J. II

    1992-09-01

    Following completion of the preliminary risk assessment of the potential Yucca Mountain Site by Pacific Northwest Laboratory (PNL) in 1988, the Office of Civilian Radioactive Waste Management (OCRWM) of the US Department of Energy (DOE) requested the Performance Assessment Scientific Support (PASS) Program at PNL to develop an integrated system model and computer code that provides performance and risk assessment analysis capabilities for a potential high-level nuclear waste repository. The system model that has been developed addresses the cumulative radionuclide release criteria established by the US Environmental Protection Agency (EPA) and estimates population risks in terms of dose to humans. The system model embodied in the SUMO (System Unsaturated Model) code will also allow benchmarking of other models being developed for the Yucca Mountain Project. The system model has three natural divisions: (1) source term, (2) far-field transport, and (3) dose to humans. This document gives a detailed description of the mathematics of each of these three divisions. Each of the governing equations employed is based on modeling assumptions that are widely accepted within the scientific community.

  12. Reducing the likelihood of future human activities that could affect geologic high-level waste repositories

    SciTech Connect (OSTI)

    Not Available

    1984-05-01

    The disposal of radioactive wastes in deep geologic formations provides a means of isolating the waste from people until the radioactivity has decayed to safe levels. However, isolating people from the wastes is a different problem, since we do not know what the future condition of society will be. The Human Interference Task Force was convened by the US Department of Energy to determine whether reasonable means exist (or could be developed) to reduce the likelihood of future human unintentionally intruding on radioactive waste isolation systems. The task force concluded that significant reductions in the likelihood of human interference could be achieved, for perhaps thousands of years into the future, if appropriate steps are taken to communicate the existence of the repository. Consequently, for two years the task force directed most of its study toward the area of long-term communication. Methods are discussed for achieving long-term communication by using permanent markers and widely disseminated records, with various steps taken to provide multiple levels of protection against loss, destruction, and major language/societal changes. Also developed is the concept of a universal symbol to denote Caution - Biohazardous Waste Buried Here. If used for the thousands of non-radioactive biohazardous waste sites in this country alone, a symbol could transcend generations and language changes, thereby vastly improving the likelihood of successful isolation of all buried biohazardous wastes.

  13. Geotechnical support and topical studies for nuclear waste geologic repositories: Annual report, fiscal year 1987

    SciTech Connect (OSTI)

    Not Available

    1988-01-01

    This multidisciplinary project was initiated in fiscal year 1986. It comprises 11 reports in two major interrelated tasks: The technical assistance part of the project includes reviewing the progress of the major projects in the DOE Office of Civilian Radioactive waste Management (OCRWM) Program and advising the Engineering and Geotechnology Division on significant technical issues facing each project; analyzing geotechnical data, reports, tests, surveys and plans for the different projects; reviewing and commenting on major technical reports and other program documents such as Site Characterization Plans (SCP) and Study Plans; and providing scientific and technical input at technical meetings. The topical studies activity comprises studies on scientific and technical ions and issues of significance to in-situ testing, test analysis methods, and site characterization of nuclear waste geologic repositories. The subjects of study were selected based on discussions with DOE staff. One minor topic is a preliminary consideration and planning exercise for postclosure monitoring studies. The major task, with subtasks involving various geoscience disciplines, is a study of the mechanical, hydraulic, geophysical and geochemical properties of fractures in geologic rock masses.

  14. Hanford Site's Data Packages in the Administrative Record (AR) and Public Information Repository (PIR)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    In 1989, the Department of Energy joined with the Washington State Department of Ecology and the U.S. Environmental Protection Agency in signing the Hanford Federal Facility Agreement and Consent Order more commonly known as the Tri-Party Agreement (TPA). The TPA outlines legally enforceable milestones for Hanford cleanup over the next several decades. The AR is the body of documents and information that is considered or relied upon to arrive at a final decision for remedial action or hazardous waste management. An AR is established for each operable unit (OU); treatment, storage, or disposal unit (TSD); or Expedited Response Action (ERA) group and will contain all documents having information considered in arriving at a Record of Decision or permit. Documents become part of the AR after they have been designated as an AR by the TPA or after EPA, DOE, or other official parties have identified a document or set of documents for inclusion. Furthermore, AR documents are to be kept in a Public Information Repository (PIR).Thousands of data packages that support the AR documents are available to the public in the Hanford PIR.

  15. Containment barrier metals for high-level waste packages in a Tuff repository

    SciTech Connect (OSTI)

    Russell, E.W.; McCright, R.D.; O`Neal, W.C.

    1983-10-12

    The Nevada Nuclear Waste Storage Investigations (NNWSI) Waste Package project is part of the US Department of Energy`s Civilian Radioactive Waste Management (CRWM) Program. The NNWSI project is working towards the development of multibarriered packages for the disposal of spent fuel and high-level waste in tuff in the unsaturated zone at Yucca Mountain at the Nevada Test Site (NTS). The final engineered barrier system design may be composed of a waste form, canister, overpack, borehole liner, packing, and the near field host rock, or some combination thereof. Lawrence Livermore National Laboratory`s (LLNL) role is to design, model, and test the waste package subsystem for the tuff repository. At the present stage of development of the nuclear waste management program at LLNL, the detailed requirements for the waste package design are not yet firmly established. In spite of these uncertainties as to the detailed package requirements, we have begun the conceptual design stage. By conceptual design, we mean design based on our best assessment of present and future regulatory requirements. We anticipate that changes will occur as the detailed requirements for waste package design are finalized. 17 references, 4 figures, 10 tables.

  16. Building America Webinar: Opportunities in Large Data Collection and Analysis-Presentation #2

    Broader source: Energy.gov [DOE]

    This presentation, Building America Field Data Repository, is the second in the webinar on April 16, 2014.

  17. OATAO is an open access repository that collects the work of Toulouse researchers and makes it freely available over the web where possible.

    E-Print Network [OSTI]

    Mailhes, Corinne

    a negative impact on major challenges of the energy system, such as GreenHouse Gas Emissions (GHGE), energy: carbon matter yield; energy #12;2 efficiency; greenhouse gas emissions; electrolysis water use; levelized

  18. OATAO is an open access repository that collects the work of Toulouse researchers and makes it freely available over the web where possible.

    E-Print Network [OSTI]

    Boyer, Edmond

    on major challenges of the energy system, such as GreenHouse Gas Emissions (GHGE), energy insecurity #12;2 efficiency; greenhouse gas emissions; electrolysis water use; levelized biofuels production cost

  19. OATAO is an open access repository that collects the work of Toulouse researchers and makes it freely available over the web where possible.

    E-Print Network [OSTI]

    Mailhes, Corinne

    , Michael and Sheridan, John and Lo Jacono, David Characterisation of a horizontal axis wind turbine's tip;Characterisation of a horizontal axis wind turbine's tip and root vortices Michael Sherry · John Sheridan · David Lo Jacono Abstract The vortical near wake of a model horizontal axis wind turbine has been

  20. ORISE: Data Collection and Analysis

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

    Data Collection and Analysis The Oak Ridge Institute for Science and Education (ORISE) assists government agencies and organizations in acquiring evidence from systematic data...

  1. Collaborative Collecting: A Literature Review

    E-Print Network [OSTI]

    Abreu, Amelia

    2013-01-01

    sharing. Personal and Ubiquitous Computing, 11(4), 215–234.conference on Ubiquitous computing (pp. 23-32). ACM.of personal, ubiquitous, and social computing, collecting

  2. Washington and Lee University Library Special Collections Collection Policy

    E-Print Network [OSTI]

    Marsh, David

    Washington and Lee University Library Special Collections Collection Policy This policy revises categories of books: 1. Books from the libraries of earlier incarnations of Washington and Lee University. 2. Books that include Washington and Lee University in their subject content. 3. Books about Robert E. Lee

  3. ACCOUNTING FOR A VITRIFIED PLUTONIUM WASTE FORM IN THE YUCCA MOUNTAIN REPOSITORY TOTAL SYSTEM PERFORMANCE ASSESSMENT (TSPA)

    SciTech Connect (OSTI)

    Marra, J

    2007-02-12

    A vitrification technology utilizing a lanthanide borosilicate (LaBS) glass appears to be a viable option for dispositioning excess weapons-useable plutonium that is not suitable for processing into mixed oxide (MOX) fuel. A significant effort to develop a glass formulation and vitrification process to immobilize plutonium was completed in the mid-1990s to support the Plutonium Immobilization Program (PIP). Further refinement of the vitrification process was accomplished as part of the Am/Cm solution vitrification project. The LaBS glass formulation was found to be capable of immobilizing in excess of 10 wt% Pu and to be very tolerant of the impurities accompanying the plutonium material streams. Thus, this waste form would be suitable for dispositioning plutonium owned by the Department of Energy-Office of Environmental Management (DOE-EM) that may not be well characterized and may contain high levels of impurities. The can-in-canister technology demonstrated in the PIP could be utilized to dispose of the vitrified plutonium in the federal radioactive waste repository. The can-in-canister technology involves placing small cans of the immobilized Pu form into a high level waste (HLW) glass canister fitted with a rack to hold the cans and then filling the canister with HLW glass. Testing was completed to demonstrate that this technology could be successfully employed with little or no impact to current Defense Waste Processing Facility (DWPF) operation and that the resulting canisters were essentially equivalent to the present HLW glass canisters to be dispositioned in the federal repository. The performance of wastes in the repository and, moreover, the performance of the entire repository system is being evaluated by the Department of Energy-Office of Civilian Radioactive Waste Management (DOE-RW) using a Total System Performance Assessment (TSPA) methodology. Technical bases documents (e.g., Analysis/Modeling Reports (AMR)) that address specific issues regarding waste form performance are being used to develop process models as input to the TSPA analyses. In this report, models developed in five AMRs for waste forms currently slated for disposition in the repository are evaluated for their applicability to waste forms with plutonium immobilized in LaBS glass using the can-in-canister technology. Those AMRs address: high-level waste glass degradation; radionuclide inventory; in-package chemistry; dissolved concentration limits of radioactive elements; and colloid-associated radionuclide concentrations. Based on evaluation of how the models treated HLW glass and similarities in the corrosion behaviors of borosilicate HLW glasses and LaBS glass, the models in the AMRs were deemed to be directly applicable to the disposition of excess weapons-useable plutonium. The evaluations are summarized.

  4. Equipment pressure applied to geomembrane in composite liner system

    E-Print Network [OSTI]

    thicknesses of sandy structural fill and rounded stone, i.e. a leachate collection and removal layer stone at most landfill sites. In particular, a dozer is usually used to place the leachate collection

  5. 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)

    1992-01-01

    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.

  6. 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.

    1992-01-14

    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.

  7. Collective neutrino oscillations in supernovae

    SciTech Connect (OSTI)

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

    2014-06-24

    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.

  8. 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

    2014-01-07

    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.

  9. Collective network for computer structures

    DOE Patents [OSTI]

    Blumrich, Matthias A. (Ridgefield, CT); Coteus, Paul W. (Yorktown Heights, NY); Chen, Dong (Croton On Hudson, NY); Gara, Alan (Mount Kisco, NY); Giampapa, Mark E. (Irvington, NY); Heidelberger, Philip (Cortlandt Manor, NY); Hoenicke, Dirk (Ossining, NY); Takken, Todd E. (Brewster, NY); Steinmacher-Burow, Burkhard D. (Wernau, DE); Vranas, Pavlos M. (Bedford Hills, NY)

    2011-08-16

    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 ate 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 and class structures. 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 needs of a processing algorithm.

  10. Summary of key directives governing permanent disposal in a geologic repository

    SciTech Connect (OSTI)

    Sands, S.C. III

    1993-11-01

    This document was developed in support of the Idaho National Engineering Laboratory (INEL) Spent Fuel and Waste Management Technology Development Program (SF&WMTDP). It is largely comprised of flow diagrams summarizing the key regulatory requirements which govern permanent disposal in a geologic repository. The key purposes are (1) to provide an easy and effective tool for referencing or cross referencing federal directives (i.e., regulations and orders), (2) to provide a method for examining the requirements in one directive category against the requirements in another, and (3) to list actions that must be taken to ensure directive compliance. The document is categorically broken down into a Transportation section and a Mined Geologic Disposal System (MGDS) section to ensure that the interrelationship of the entire disposal system is considered. The Transportation section describes the transportation packaging requirements, testing methods, and safety requirements imposed on fissile material shipments. The MGDS section encompasses technical aspects involved in siting, licensing, waste interaction with the container, container design features, physical characteristics of the surrounding environment, facility design features, barrier systems, safety features, criticality considerations, migration restrictions, implementation guidelines, and so forth. For purposes of illustration, the worst case scenario is outlined. It is important that the approaches and considerations contained in this document be integrated into the efforts of the SF&WMTDP so that every applicable aspect of the regulatory requirements can be evaluated to avoid investing large sums of money into projects that do not take into account all of the aspects of permanent waste disposal. Not until an overall picture and clear understanding of these regulations is established can a basis be developed to govern the direction of future activities of the SF&WMTDP.

  11. Radionuclide release from PWR fuels in a reference tuff repository groundwater

    SciTech Connect (OSTI)

    Wilson, C.N.; Oversby, V.M.

    1985-03-01

    The Nevada Nuclear Waste Storage Investigations Project (NNWSI) is studying the suitability of the welded devitrified Topopah Spring tuff at Yucca Mountain, Nye County, Nevada, for potential use as a high-level nuclear waste repository. In support of the Waste Package task of NNWSI, tests have been conducted under ambient air environment to measure radionuclide release from two pressurized water reactor (PWR) spent fuels in water obtained from the J-13 well near the Yucca Mountain site. Four specimen types, representing a range of fuel physical conditions that may exist in a failed waste canister containing a limited amount of water were tested. The specimen types were: fuel rod sections split open to expose bare fuel particles; rod sections with water-tight end fittings with a 2.5-cm long by 150-{mu}m wide slit through the cladding; rod sections with water-tight end fittings and two 200-{mu}m-diameter holes through the cladding; and undefected rod segments with water-tight end fittings. Radionuclide release results from the first 223-day test runs on H.B. Robinson spent fuel specimens in J-13 water are reported and compared to results from a previous test series in which similar Turkey Point reactor spent fuel specimens were tested on deionized water. Selected initial results are also given for Turkey Point fuel specimens tested on J-13 water. Results suggest that the actinides Pu, Am, Cm and Np are released congruently with U as the UO{sub 2} spent fuel matrix dissolves. Fractional release of {sup 137}Cs and {sup 99}Tc was greater than that measured for the actinides. Generally, lower radionuclide releases were measured for the H.B. Robinson fuel in J-13 water than for Turkey Point Fuel in deionized water. 8 references, 7 figures, 9 tables.

  12. Sub-Seabed Repository for Nuclear Waste - a Strategic Alternative - 13102

    SciTech Connect (OSTI)

    McAllister, Keith R. [Department of the Navy, 15 Turkey Foot Court, Darnestown, MD 20878 (United States)] [Department of the Navy, 15 Turkey Foot Court, Darnestown, MD 20878 (United States)

    2013-07-01

    It was recognized at the outset of nuclear power generation in the 1950's that the waste products would require isolation away from humans for periods in excess of 10,000 years. After years studying alternatives, the DOE recommended pursuing the development of a SNF/HLW disposal facility within Yucca Mountain in the desert of Nevada. That recommendation became law with passage of the NWPAA, effectively stopping development of other approaches to the waste problem. In the face of political resistance from the state of Nevada, the 2010 decision to withdraw the license application for the geologic repository at Yucca Mountain has delayed further the most mature option for safe, long-term disposal of SNF and HLW. It is time to revisit an alternative option, sub-seabed disposal within the US Exclusive Economic Zone (EEZ), which would permanently sequester waste out of the biosphere, and out of the reach of saboteurs or terrorists. A proposal is made for a full scale pilot project to demonstrate burying radioactive waste in stable, deep ocean sediments. While much of the scientific work on pelagic clays has been done to develop a sub-seabed waste sequestration capability, this proposal introduces technology from non-traditional sources such as riser-less ocean drilling and the Navy's Sound Surveillance System. The political decisions affecting the issue will come down to site selection and a thorough understanding of comparative risks. The sub-seabed sequestration of nuclear waste has the potential to provide a robust solution to a critical problem for this clean and reliable energy source. (authors)

  13. eDPS Aerosol Collection

    SciTech Connect (OSTI)

    Venzie, J.

    2015-10-13

    The eDPS Aerosol Collection project studies the fundamental physics of electrostatic aerosol collection for national security applications. The interpretation of aerosol data requires understanding and correcting for biases introduced from particle genesis through collection and analysis. The research and development undertaken in this project provides the basis for both the statistical correction of existing equipment and techniques; as well as, the development of new collectors and analytical techniques designed to minimize unwanted biases while improving the efficiency of locating and measuring individual particles of interest.

  14. Main Features for the Conceptualization of the Post-Closure Evolution Scenario of the Cigeo LIL-HL Waste Repository - 13105

    SciTech Connect (OSTI)

    Landais, Patrick; Giffaut, Eric; Pepin, Guillaume; Plas, Frederic; Schumacher, S. [Andra, 1-7 rue Jean Monnet, 92298 Chatenay Malabry (France)] [Andra, 1-7 rue Jean Monnet, 92298 Chatenay Malabry (France)

    2013-07-01

    In France, in order to commission the planned geological repository by 2025, a license application for the industrial project of this geological repository called Cigeo (Centre Industriel de Stockage Geologique) must be submitted and reviewed by the competent authorities by 2015. On the basis of its preliminary design set up in 2009 and on the associated requirements for long-term safety, an overall conceptual model has been developed in order to prepare the performance and safety analysis. The Cigeo repository makes use of the passive safety response characteristics of both the engineered and geological barriers that allow: - resisting water ingress, with repository designs favoring the limitation of the water flows; - limiting the release of radionuclides and chemical toxics; - delaying and mitigating the spread of radionuclides and chemical toxics. In order to evaluate the performance of the various elements, a conceptual model of the thermo-hydro-chemico-mechanical (THMC) evolution of the different components of the repository has been designed. It takes stock of a 20 years research effort which allowed data to be obtained from various surface geological campaigns, in-situ experiments in URLs and wastes characterization, and advances in numerical simulation to be utilised. Based on the best available knowledge to date, this conceptual model constitutes a robust basis for the definition and development of the long-term safety scenarios. It also helps identifying the residual uncertainties, and provides guidelines for additional research and system optimizations. (authors)

  15. Cost Comparison for the Transfer of Select Calcined Waste Canisters to the Monitored Geologic Repository at Yucca Mountain, NV

    SciTech Connect (OSTI)

    Michael B. Heiser; Clark B. Millet

    2005-10-01

    This report performs a life-cycle cost comparison of three proposed canister designs for the shipment and disposition of Idaho National Laboratory high-level calcined waste currently in storage at the Idaho Nuclear Technology and Engineering Center to the proposed national monitored geologic repository at Yucca Mountain, Nevada. Concept A (2 × 10-ft) and Concept B (2 × 15-ft) canisters are comparable in design, but they differ in size and waste loading options and vary proportionally in weight. The Concept C (5.5 × 17.5-ft) canister (also called the “super canister”), while similar in design to the other canisters, is considerably larger and heavier than Concept A and B canisters and has a greater wall thickness. This report includes estimating the unique life-cycle costs for the three canister designs. Unique life-cycle costs include elements such as canister purchase and filling at the Idaho Nuclear Technology and Engineering Center, cask preparation and roundtrip consignment costs, final disposition in the monitored geologic repository (including canister off-loading and placement in the final waste disposal package for disposition), and cask purchase. Packaging of the calcine "as-is" would save $2.9 to $3.9 billion over direct vitrification disposal in the proposed national monitored geologic repository at Yucca Mountain, Nevada. Using the larger Concept C canisters would use 0.75 mi less of tunnel space, cost $1.3 billion less than 10-ft canisters of Concept A, and would be complete in 6.2 years.

  16. Report on Intact and Degraded Criticality for Selected Plutonium Waste Forms in a Geologic Repository, Volume I: MOX SNF

    SciTech Connect (OSTI)

    J.A. McClure

    1998-09-21

    As part of the plutonium waste form development and down-select process, repository analyses have been conducted to evaluate the long-term performance of these forms for repository acceptance. Intact and degraded mode criticality analysis of the mixed oxide (MOX) spent fuel is presented in Volume I, while Volume II presents the evaluations of the waste form containing plutonium immobilized in a ceramic matrix. Although the ceramic immobilization development program is ongoing, and refinements are still being developed and evaluated, this analysis provides value through quick feed-back to this development process, and as preparation for the analysis that will be conducted starting in fiscal year (FY) 1999 in support of the License Application. While no MOX fuel has been generated in the United States using weapons-usable plutonium, Oak Ridge National Laboratory (ORNL) has conducted calculations on Westinghouse-type reactors to determine the expected characteristics of such a fuel. These spent nuclear fuel (SNF) characteristics have been used to determine the long-term potential for criticality in a repository environment. In all instances the methodology and scenarios used in these analyses are compatible with those developed and used for Commercial Spent Nuclear Fuel (CSNF) and Defense High Level Waste (DHLW), as tailored for the particular characteristics of the waste forms. This provides a common basis for comparison of the results. This analysis utilizes dissolution, solubility, and thermodynamic data that are currently available. Additional data on long-term behavior is being developed, and later analyses (FY 99) to support the License Application will use the very latest information that has been generated. Ranges of parameter values are considered to reflect sensitivity to uncertainty. Most of the analysis is focused on those parameter values that produce the worst case results, so that potential licensing issues can be identified.

  17. Collection Management Policy Mission Statement

    E-Print Network [OSTI]

    Abrahams, I. David

    Collection Management Policy Mission Statement: To provide an efficient and effective service care, document supply, stock management, and logistical planning and relegation of the Library Management Policy ..................................3 2. Acquisition of Content

  18. AFID: an automated approach to collecting software faults

    E-Print Network [OSTI]

    Edwards, Alex; Tucker, Sean; Demsky, Brian

    2010-01-01

    International Symposium on Software Testing and Analysis,International Symposium on Software Testing and Analysis,Software repository mining with Marmoset: an auto- mated programming project snapshot and testing

  19. Uncertainty and sensitivity analysis in the 2008 performance assessment for the proposed repository for high-level radioactive waste at Yucca Mountain, Nevada.

    SciTech Connect (OSTI)

    Helton, Jon Craig; Sallaberry, Cedric M.; Hansen, Clifford W.

    2010-05-01

    Extensive work has been carried out by the U.S. Department of Energy (DOE) in the development of a proposed geologic repository at Yucca Mountain (YM), Nevada, for the disposal of high-level radioactive waste. As part of this development, an extensive performance assessment (PA) for the YM repository was completed in 2008 [1] and supported a license application by the DOE to the U.S. Nuclear Regulatory Commission (NRC) for the construction of the YM repository [2]. This presentation provides an overview of the conceptual and computational structure of the indicated PA (hereafter referred to as the 2008 YM PA) and the roles that uncertainty analysis and sensitivity analysis play in this structure.

  20. U.S. DEPARTMENT OF ENERGY EXPERIENCE IN CREATING AND COMMUNICATING THE CASE FOR THE SAFETY OF A POTENTIAL YUCCA MOUNTAIN REPOSITORY

    SciTech Connect (OSTI)

    W.J. Boyle; A.E. Van Luik

    2005-08-30

    Experience gained by the U.S. Department of Energy (the Department) in making the recommendation for the development of the Yucca Mountain site as the nation's first high-level waste and spent nuclear fuel repository is useful for creating documents to support the next phase in the repository program, the licensing phase. The experience that supported the successful site-recommendation process involved a three-tiered approach. First, was making a highly technical case for regulatory compliance. Second, was making a broader case for safety in an Environmental Impact Statement. And third, producing plain language brochures, made available to the public in hard copy and on the Internet, to explain the Department's action and its legal and scientific bases. This paper reviews lessons learned from this process, and makes suggestions for the next stage of the repository program: licensing.

  1. Site characterization plan conceptual design report for a high-level nuclear waste repository in salt, vertical emplacement mode: Volume 1

    SciTech Connect (OSTI)

    Not Available

    1987-12-01

    This Conceptual Design Report describes the conceptual design of a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. Waste receipt, processing, packing, and other surface facility operations are described. Operations in the shafts underground are described, including waste hoisting, transfer, and vertical emplacement. This report specifically addresses the vertical emplacement mode, the reference design for the repository. Waste retrieval capability is described. The report includes a description of the layout of the surface, shafts, and underground. Major equipment items are identified. The report includes plans for decommissioning and sealing of the facility. The report discusses how the repository will satisfy performance objectives. Chapters are included on basis for design, design analyses, and data requirements for completion of future design efforts. 105 figs., 52 tabs.

  2. Collections

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 OutreachProductswsicloudwsiclouddenDVA N C E D BGene NetworkNuclearDNP 20082 P rMilitaryat Lawrence

  3. Salton Sea Geothermal Field, California, as a near-field natural analog of a radioactive waste repository in salt

    SciTech Connect (OSTI)

    Elders, W.A.; Cohen, L.H.

    1983-11-01

    Since high concentrations of radionuclides and high temperatures are not normally encountered in salt domes or beds, finding an exact geologic analog of expected near-field conditions in a mined nuclear waste repository in salt will be difficult. The Salton Sea Geothermal Field, however, provides an opportunity to investigate the migration and retardation of naturally occurring U, Th, Ra, Cs, Sr and other elements in hot brines which have been moving through clay-rich sedimentary rocks for up to 100,000 years. The more than thirty deep wells drilled in this field to produce steam for electrical generation penetrate sedimentary rocks containing concentrated brines where temperatures reach 365/sup 0/C at only 2 km depth. The brines are primarily Na, K, Ca chlorides with up to 25% of total dissolved solids; they also contain high concentrations of metals such as Fe, Mn, Li, Zn, and Pb. This report describes the geology, geophysics and geochemistry of this system as a prelude to a study of the mobility of naturally occurring radionuclides and radionuclide analogs within it. The aim of this study is to provide data to assist in validating quantitative models of repository behavior and to use in designing and evaluating waste packages and engineered barriers. 128 references, 33 figures, 13 tables.

  4. Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C. [Science Applications International Corp., Las Vegas, NV (United States); Ballou, L.B.; Revelli, M.A. [Lawrence Livermore National Lab., CA (United States); Ducharme, A.R.; Shephard, L.E. [Sandia National Labs., Albuquerque, NM (United States); Dudley, W.W.; Hoxie, D.T. [Geological Survey, Denver, CO (United States); Herbst, R.J.; Patera, E.A. [Los Alamos National Lab., NM (United States); Judd, B.R. [Decision Analysis Co., Portola Valley, CA (United States); Docka, J.A.; Rickertsen, L.D. [Weston Technical Associates, Washington, DC (United States)

    1992-01-01

    This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE`s Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ``current information`` or ``available evidence.``

  5. Death Valley Lower Carbonate Aquifer Monitoring Program Wells Down gradient of the Proposed Yucca Mountain Nuclear Waste Repository

    SciTech Connect (OSTI)

    Inyo County

    2006-07-26

    Inyo County has participated in oversight activities associated with the Yucca Mountain Nuclear Waste Repository since 1987. The overall goal of these studies are the evaluation of far-field issues related to potential transport, by ground water, or radionuclides into Inyo County, including Death Valley, and the evaluation of a connection between the Lower Carbonate Aquifer (LCA) and the biosphere. Our oversight and completed Cooperative Agreement research, and a number of other investigators research indicate that there is groundwater flow between the alluvial and carbonate aquifers both at Yucca Mountain and in Inyo County. In addition to the potential of radionuclide transport through the LCA, Czarnecki (1997), with the US Geological Survey, research indicate potential radionuclide transport through the shallower Tertiary-age aquifer materials with ultimate discharge into the Franklin Lake Playa in Inyo County. The specific purpose of this Cooperative Agreement drilling program was to acquire geological, subsurface geology, and hydrologic data to: (1) establish the existence of inter-basin flow between the Amargosa Basin and Death Valley Basin; (2) characterize groundwater flow paths in the LCA through Southern Funeral Mountain Range, and (3) Evaluation the hydraulic connection between the Yucca Mountain repository and the major springs in Death Valley through the LCA.

  6. Vitrification treatment options for disposal of greater-than-Class-C low-level waste in a deep geologic repository

    SciTech Connect (OSTI)

    Fullmer, K.S.; Fish, L.W.; Fischer, D.K.

    1994-11-01

    The Department of Energy (DOE), in keeping with their responsibility under Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985, is investigating several disposal options for greater-than-Class C low-level waste (GTCC LLW), including emplacement in a deep geologic repository. At the present time vitrification, namely borosilicate glass, is the standard waste form assumed for high-level waste accepted into the Civilian Radioactive Waste Management System. This report supports DOE`s investigation of the deep geologic disposal option by comparing the vitrification treatments that are able to convert those GTCC LLWs that are inherently migratory into stable waste forms acceptable for disposal in a deep geologic repository. Eight vitrification treatments that utilize glass, glass ceramic, or basalt waste form matrices are identified. Six of these are discussed in detail, stating the advantages and limitations of each relative to their ability to immobilize GTCC LLW. The report concludes that the waste form most likely to provide the best composite of performance characteristics for GTCC process waste is Iron Enriched Basalt 4 (IEB4).

  7. A hybrid hydrologic-geophysical inverse technique for the assessment and monitoring of leachates in the vadose zone. 1998 annual progress report

    SciTech Connect (OSTI)

    Alumbaugh, D.L.; Glass, R.J.; Yeh, T.C.; LaBrecque, D.

    1998-06-01

    'The objective of this study is to develop and field test a new, integrated Hybrid Hydrologic-Geophysical Inverse Technique (HHGIT) for characterization of the vadose zone at contaminated sites. This new approach to site characterization and monitoring can provide detailed maps of hydrogeological heterogeneity and the extent of contamination by combining information from electric resistivity tomography (ERT) surveys, statistical information about heterogeneity and hydrologic processes, and sparse hydrologic data. Because the electrical conductivity of the vadose zone (from the ERT measurements) can be correlated to the fluid saturation and/or contaminant concentration, the hydrologic and geophysical measurements are related. As of the 21st month of a 36-month project, a three-dimensional stochastic hydrologic inverse model for heterogeneous vadose zones has been developed. This model employs pressure and moisture content measurements under both transient and steady flow conditions to estimate unsaturated hydraulic parameters. In this model, an innovative approach to sequentially condition the estimate using temporal measurements has been incorporated. This allows us to use vast amounts of pressure and moisture content information measured at different times while keeping the computational effort manageable. Using this model the authors have found that the relative importance of the pressure and moisture content measurements in defining the different vadose zone parameters depends on whether the soil is wet or dry. They have also learned that pressure and moisture content measurements collected during steady state flow provide the best characterization of heterogeneity compared to other types of hydrologic data. These findings provide important guidance to the design of sampling scheme of the field experiment described below.'

  8. Deep in Data. Empirical Data Based Software Accuracy Testing Using the Building America Field Data Repository

    SciTech Connect (OSTI)

    Neymark, J.; Roberts, D.

    2013-06-01

    This paper describes progress toward developing a usable, standardized, empirical data-based software accuracy test suite using home energy consumption and building description data. Empirical data collected from around the United States have been translated into a uniform Home Performance Extensible Markup Language format that may enable software developers to create translators to their input schemes for efficient access to the data. This could allow for modeling many homes expediently, and thus implementing software accuracy test cases by applying the translated data.

  9. Advances in understanding solar energy collection materials

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

    Understanding solar energy collection materials Advances in understanding solar energy collection materials A LANL team and collaborators have made advances in the understanding of...

  10. Collecting Personally Identifiable Information Through the Web...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Federal Requirements Collecting Personally Identifiable Information Through the Web and User Research Collecting Personally Identifiable Information Through the Web and User...

  11. Information Collection Management | Department of Energy

    Energy Savers [EERE]

    Information Collection RequestsPRA (PDF) DOE Order 200.2 Information Collection Management Program - To set forth the Department of Energy (DOE) requirements and...

  12. Collecting Information on Participant Reactions. 

    E-Print Network [OSTI]

    Taylor-Powell, Ellen; Marshall, Mary G

    1988-01-01

    of benefits? What do they see as information you learned from... Texas Agricultural Extension Service Collecting Information on Participant Reactions } Evaluation Materials Texas Agricultural Extension Service. Zerle L. Carpenter, Director. The Texas A&M University System. College Station, Texas B-1615...

  13. Aluminum Waste Reaction Indicators in a Municipal Solid Waste Landfill

    E-Print Network [OSTI]

    in gas composition and pressure, nuisance odors, and changes in leachate composition and quantity. Such reactions may also cause degradation of leachate quality (e.g., increased ammonia, sodium, potassium (gas collection systems, leachate collection systems, and liner system materials), and slope

  14. Class collection PMB113 California mushrooms F2007 date of collection

    E-Print Network [OSTI]

    California at Berkeley, University of

    Class collection PMB113 California mushrooms F2007 Species: date of collection: Location by: Identified by: Class collection PMB113 California mushrooms F2007 Species: date of collection) collected by: Identified by: Class collection PMB113 California mushrooms F2007 Species: date

  15. Last spring, an Ohio waste slope collapsed, displacing 1.5 million cu yd of waste. Remedial measures can prevent similar failures at ~~grandfathered" landfills.

    E-Print Network [OSTI]

    liner system, which consists of a leachate collection and removal system, a geomembrane and a compacted and a leachate col- lection and removal system were to be placed in a 140-ft-deep rock excavation at the toe

  16. TRACER TRANSPORT THROUGH A FIELD-SCALE COMPACTED CLAY LINER OVER A 12 YEAR PERIOD

    E-Print Network [OSTI]

    " or "punctures" in the GM can form from GM deployment, construction of the leachate collection and recovery the transport of leachate from the composite system. As a result, transport through the composite liner system

  17. Social impacts of hazardous and nuclear facilities and events: Implications for Nevada and the Yucca Mountain high-level nuclear waste repository; [Final report

    SciTech Connect (OSTI)

    Freudenburg, W.R.; Carter, L.F.; Willard, W.; Lodwick, D.G.; Hardert, R.A.; Levine, A.G.; Kroll-Smith, S.; Couch, S.R.; Edelstein, M.R.

    1992-05-01

    Social impacts of a nuclear waste repository are described. Various case studies are cited such as Rocky Flats Plant, the Feed Materials Production Center, and Love Canal. The social impacts of toxic contamination, mitigating environmental stigma and loss of trust are also discussed.

  18. Identification of structures, systems, and components important to safety at the potential repository at Yucca Mountain; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

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

    1991-10-01

    This study recommends which structures, systems, and components of the potential repository at Yucca Mountain are important to safety. The assessment was completed in April 1990 and uses the reference repository configuration in the Site Characterization Plan Conceptual Design Report and follows the methodology required at that time by DOE Procedure AP6.10-Q. Failures of repository items during the preclosure period are evaluated to determine the potential offsite radiation doses and associated probabilities. Items are important to safety if, in the event they fail to perform their intended function, an accident could result which causes a dose commitment greater than 0.5 rem to the whole body or any organ of an individual in an unrestricted area. This study recommends that these repository items include the structures that house spent fuel and high-level waste, the associated filtered ventilation exhaust systems, certain waste- handling equipment, the waste containers, the waste treatment building structure, the underground waste transporters, and other items listed in this report. This work was completed April 1990. 27 refs., 7 figs., 9 tabs.

  19. A Multiattribute Utility Analysis of Sites Nominated For Characterization For the First Radioactive Waste Repository- A Decision Aiding Methodology

    Broader source: Energy.gov [DOE]

    In December 1984, the Department of Energy (DOE) published draft environmental assessments (EAs) to support the proposed nomination of five sites and the recommendation of three sites for characterization for the first radioactive-waste repository. A chapter common to all the draft EAs (Chapter 7) presented rankings of the five sites against the postclosure and the preclosure technical siting guidelines. To determine which three sites appeared most favorable for recommendation for characterization, three simple quantitative methods were used to aggregate the rankings assigned to each site for the various technical guidelines. In response to numerous comments on the methods, the DOE has undertaken a formal application of one of them (hereafter referred to as the decision-aiding methodology) for the purpose of obtaining a more rigorous evaluation of the nominated sites.

  20. Unsaturated flow and transport through fractured rock related to high-level waste repositories; Final report, Phase 3

    SciTech Connect (OSTI)

    Evans, D.D.; Rasmussen, T.C. [Arizona Univ., Tucson, AZ (USA). Dept. of Hydrology and Water Resources

    1991-01-01

    Research results are summarized for a US Nuclear Regulatory Commission contract with the University of Arizona focusing on field and laboratory methods for characterizing unsaturated fluid flow and solute transport related to high-level radioactive waste repositories. Characterization activities are presented for the Apache Leap Tuff field site. The field site is located in unsaturated, fractured tuff in central Arizona. Hydraulic, pneumatic, and thermal characteristics of the tuff are summarized, along with methodologies employed to monitor and sample hydrologic and geochemical processes at the field site. Thermohydrologic experiments are reported which provide laboratory and field data related to the effects conditions and flow and transport in unsaturated, fractured rock. 29 refs., 17 figs., 21 tabs.

  1. Room at the Mountain: Estimated Maximum Amounts of Commercial Spent Nuclear Fuel Capable of Disposal in a Yucca Mountain Repository

    SciTech Connect (OSTI)

    Kessler, John H. [Electric Power Research Institute - EPRI, 3420 Hillview Avenue, Palo Alto, California 94304 (United States); Kemeny, John [University of Arizona, Tucson AZ 85721 (United States); King, Fraser [Integrity Corrosion Consulting, Ltd., 6732 Silverview Drive NW, Calgary, Alberta (Canada); Ross, Alan M. [Alan M. Ross and Associates, 1061 Gray Fox Circle Pleasanton, CA 94566 (Canada); Ross, Benjamen [Disposal Safety, Inc., Bethesda, MD 20814 (United States)

    2006-07-01

    The purpose of this paper is to present an initial analysis of the maximum amount of commercial spent nuclear fuel (CSNF) that could be emplaced into a geological repository at Yucca Mountain. This analysis identifies and uses programmatic, material, and geological constraints and factors that affect this estimation of maximum amount of CSNF for disposal. The conclusion of this initial analysis is that the current legislative limit on Yucca Mountain disposal capacity, 63,000 MTHM of CSNF, is a small fraction of the available physical capacity of the Yucca Mountain system assuming the current high-temperature operating mode (HTOM) design. EPRI is confident that at least four times the legislative limit for CSNF ({approx}260,000 MTHM) can be emplaced in the Yucca Mountain system. It is possible that with additional site characterization, upwards of nine times the legislative limit ({approx}570,000 MTHM) could be emplaced. (authors)

  2. PMGR_COLLECTIVE V1.0

    Energy Science and Technology Software Center (OSTI)

    002339WKSTN00 The Process Manager Collective Library  http://sourceforge.net/projects/pmgrcollective/ 

  3. Apparatus for collecting solar energy

    SciTech Connect (OSTI)

    Wildenrotter, K.

    1981-08-18

    Apparatus is described for collecting solar energy comprises a collector having a solar-energy collector surface. The collector is mounted on a support and is pivotable between an exposed position in which the collector surface faces the sun and a substantially horizontal sheltered position in which the collector surface faces the earth, thereby protecting the collector surface from the elements and facilitating access thereto for maintenance.

  4. Systems study of the feasibility of high-level nuclear-waste fractionation for thermal stress control in a geologic repository: main report

    SciTech Connect (OSTI)

    McKee, R.W.; Elder, H.K.; McCallum, R.F.; Silviera, D.J.; Swanson, J.L.; Wiles, L.E.

    1983-06-01

    This study assesses the benefits and costs of fractionating the cesium and strontium (Cs/Sr) components in commercial high-level waste (HLW) to a separate waste stream for the purpose of reducing geologic-repository thermal stresses in the region of the HLW. System costs are developed for a broad range of conditions comparing the Cs/Sr fractionation concept with disposal of 10-year-old vitrified HLW and vitrified HLW aged to achieve (through decay) the same heat output as the fractionated high-level waste (FHLW). All comparisons are based on a 50,000 metric ton equivalent (MTE) system. The FHLW and the Cs/Sr waste are both disposed of as vitrified waste but emplaced in separate areas of a basalt repository. The FHLW is emplaced in high-integrity packages at relatively high waste loading but low heat loading, while the Cs/Sr waste is emplaced in minimum-integrity packages at relatively high heat loading in a separate region of the repository. System cost comparisons are based on minimum cost combinations of canister diameter, waste concentration, and canister spacing in a basalt repository. The effects on both long- and near-term safety considerations are also addressed. The major conclusion is that the Cs/Sr fractionation concept offers the prospect of a substantial total system cost advantage for HLW disposal if reduced HLW package temperatures in a basalt repository are desired. However, there is no cost advantage if currently designated maximum design temperatures are acceptable. Aging the HLW for 50 to 100 years can accomplish similar results at equivalent or lower costs. 37 figures, 58 tables.

  5. Data Collection, Analysis, and Reporting | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Business Operations Project Management Coordination Office Data Collection, Analysis, and Reporting Data Collection, Analysis, and Reporting The Data Collection, Analysis,...

  6. IMPACT ASSESSMENT OF THE OLD QUESNEL LANDFILL

    E-Print Network [OSTI]

    .................................................................................................................ll Leachate Seeps

  7. Environmental Activism as Collective Action Key words: Environmental activism, environmental behavior, collective action,

    E-Print Network [OSTI]

    Lubell, Mark

    Environmental Activism as Collective Action Key words: Environmental activism, environmental behavior, collective action, environmentalism, collective interest model. Mark Lubell Department The literature on environmental activism has failed to produce a model of individual decision- making explicitly

  8. Representing Information Collections for Visual Cognition 

    E-Print Network [OSTI]

    Koh, Eunyee

    2009-05-15

    The importance of digital information collections is growing. Collections are typically represented with text-only, in a linear list format, which turns out to be a weak representation for cognition. We learned this from empirical research...

  9. Collection Policy: Crop and Soil Sciences Introduction

    E-Print Network [OSTI]

    Angenent, Lars T.

    Collection Policy: Crop and Soil Sciences ___________________________________________________________________________________ Introduction: This 2007 collection policy review for the Department of Crops and Soil Sciences comes several the Department of Atmospheric and Earth Sciences. Since then, Crops and Soil Sciences has reorganized into three

  10. Intensifying the collective use of public place

    E-Print Network [OSTI]

    Aldrich, Darrell E. (Darrell Eugene)

    1994-01-01

    The premise of the thesis states that to intensify the collective use of public place there must exist a broad collective understanding of physical constituents that 'build' spatial relationships. These spatial understandings ...

  11. National Human Radiobiological Tissue Repository (NHRTR) at the United States Transuranium and Uranium Registries

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    The NHRTR, one component of the USTUR, contains frozen tissues, tissue solutions, microscope slides, and paraffin blocks that were collected by the USTUR at the autopsy of workers with documented intakes of plutonium, americium, uranium, and thorium. The samples are available to qualified scientists for further research. Thousands of frozen, ashed, dried, and plastic embedded bone samples from the radium studies carried out by Argonne National Laboratory, Argonne Cancer Research Hospital, the Massachusetts Institute of Technology, and the New Jersey Radium Research Project are available and linked by case number to de-identified, published case data. These data include the person's source of exposure (dial painter, therapeutic injection, etc.), estimated body burden, radiochemical results, and medical history. Other samples, including organs and whole body donations, have come from volunteer donors who were impacted by elements such as plutonium, throium, etc. See the USTUR website for information on how to apply for research samples or how to become a volunteer donor. [Information taken from http://www.ustur.wsu.edu/NHRTR/index.html#

  12. 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]

    2004-01-01

    mchiji@hazama.co.jp b. Canadian Nuclear Safety Commission (THM processes on the safety of nuclear waste repositories.coupling on the safety assessment of a nuclear fuel waste

  13. Anisotropic collective flow of a Lorentz gas

    E-Print Network [OSTI]

    Nicolas Borghini; Clement Gombeaud

    2011-06-30

    Analytical results for the anisotropic collective flow of a Lorentz gas of massless particles scattering on fixed centres are presented.

  14. Control of collective network chaos

    SciTech Connect (OSTI)

    Wagemakers, Alexandre, E-mail: alexandre.wagemakers@urjc.es; Sanjuán, Miguel A. F., E-mail: miguel.sanjuan@urjc.es [Departamento de Física, Universidad Rey Juan Carlos, Tulipán s/n, 28933 Móstoles, Madrid (Spain); Barreto, Ernest, E-mail: ebarreto@gmu.edu; So, Paul, E-mail: paso@gmu.edu [School of Physics, Astronomy, and Computational Sciences and The Krasnow Institute for Advanced Study, George Mason University, Fairfax, Virginia 22030 (United States)

    2014-06-01

    Under certain conditions, the collective behavior of a large globally-coupled heterogeneous network of coupled oscillators, as quantified by the macroscopic mean field or order parameter, can exhibit low-dimensional chaotic behavior. Recent advances describe how a small set of “reduced” ordinary differential equations can be derived that captures this mean field behavior. Here, we show that chaos control algorithms designed using the reduced equations can be successfully applied to imperfect realizations of the full network. To systematically study the effectiveness of this technique, we measure the quality of control as we relax conditions that are required for the strict accuracy of the reduced equations, and hence, the controller. Although the effects are network-dependent, we show that the method is effective for surprisingly small networks, for modest departures from global coupling, and even with mild inaccuracy in the estimate of network heterogeneity.

  15. Devices for collecting chemical compounds

    SciTech Connect (OSTI)

    Scott, Jill R; Groenewold, Gary S

    2013-12-24

    A device for sampling chemical compounds from fixed surfaces and related methods are disclosed. The device may include a vacuum source, a chamber and a sorbent material. The device may utilize vacuum extraction to volatilize the chemical compounds from a fixed surface so that they may be sorbed by the sorbent material. The sorbent material may then be analyzed using conventional thermal desorption/gas chromatography/mass spectrometry (TD/GC/MS) instrumentation to determine presence of the chemical compounds. The methods may include detecting release and presence of one or more chemical compounds and determining the efficacy of decontamination. The device may be useful in collection and analysis of a variety of chemical compounds, such as residual chemical warfare agents, chemical attribution signatures and toxic industrial chemicals.

  16. Some Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository Study (The Yucca Mountain Project)

    SciTech Connect (OSTI)

    F. Hua; P. Pasupathi; N. Brown; K. Mon

    2005-09-19

    The safe disposal of radioactive waste requires that the waste be isolated from the environment until radioactive decay has reduced its toxicity to innocuous levels for plants, animals, and humans. All of the countries currently studying the options for disposing of high-level nuclear waste (HLW) have selected deep geologic formations to be the primary barrier for accomplishing this isolation. In U.S.A., the Nuclear Waste Policy Act of 1982 (as amended in 1987) designated Yucca Mountain in Nevada as the potential site to be characterized for high-level nuclear waste (HLW) disposal. Long-term containment of waste and subsequent slow release of radionuclides into the geosphere will rely on a system of natural and engineered barriers including a robust waste containment design. The waste package design consists of a highly corrosion resistant Ni-based Alloy 22 cylindrical barrier surrounding a Type 316 stainless steel inner structural vessel. The waste package is covered by a mailbox-shaped drip shield composed primarily of Ti Grade 7 with Ti Grade 24 structural support members. The U.S. Yucca Mountain Project has been studying and modeling the degradation issues of the relevant materials for some 20 years. This paper reviews the state-of-the-art understanding of the degradation processes based on the past 20 years studies on Yucca Mountain Project (YMP) materials degradation issues with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the 10,000 years regulatory period. This paper provides an overview of the current understanding of the likely degradation behavior of the waste package and drip shield in the repository after the permanent closure of the facility. The degradation scenario discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking and hydrogen induced cracking of Alloy 22 and titanium alloys. The effects of microbial activity and radiation on degradation of Alloy 22 and titanium alloys are also discussed. Further, for titanium alloys, the effects of fluorides, bromides, calcium ions, and galvanic coupling to less noble metals are further considered. It is concluded that, as far as materials degradation is concerned, the materials and design adopted in the U.S. Yucca Mountain Project will provide sufficient safety margins within the 10,000-years regulatory period.

  17. Emissions from US waste collection vehicles

    SciTech Connect (OSTI)

    Maimoun, Mousa A.; Reinhart, Debra R.; Gammoh, Fatina T.; McCauley Bush, Pamela

    2013-05-15

    Highlights: ? Life-cycle emissions for alternative fuel technologies. ? Fuel consumption of alternative fuels for waste collection vehicles. ? Actual driving cycle of waste collection vehicles. ? Diesel-fueled waste collection vehicle emissions. - Abstract: This research is an in-depth environmental analysis of potential alternative fuel technologies for waste collection vehicles. Life-cycle emissions, cost, fuel and energy consumption were evaluated for a wide range of fossil and bio-fuel technologies. Emission factors were calculated for a typical waste collection driving cycle as well as constant speed. In brief, natural gas waste collection vehicles (compressed and liquid) fueled with North-American natural gas had 6–10% higher well-to-wheel (WTW) greenhouse gas (GHG) emissions relative to diesel-fueled vehicles; however the pump-to-wheel (PTW) GHG emissions of natural gas waste collection vehicles averaged 6% less than diesel-fueled vehicles. Landfill gas had about 80% lower WTW GHG emissions relative to diesel. Biodiesel waste collection vehicles had between 12% and 75% lower WTW GHG emissions relative to diesel depending on the fuel source and the blend. In 2011, natural gas waste collection vehicles had the lowest fuel cost per collection vehicle kilometer travel. Finally, the actual driving cycle of waste collection vehicles consists of repetitive stops and starts during waste collection; this generates more emissions than constant speed driving.

  18. ART COLLECTIONS University Policy No: BP3310

    E-Print Network [OSTI]

    Victoria, University of

    1 ART COLLECTIONS University Policy No: BP3310 Classification: External Relations Approving: Mandated Review: Annually Associated Procedures: Procedures for Art Collections Terms of Reference for Art, refinement, access, and care of the Permanent Collection of the University of Victoria Legacy Art Galleries

  19. Hazard Lewis Farms Collection Binghamton University Libraries

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    Hazard Lewis Farms Collection Binghamton University Libraries Special Collections Hazard Lewis and University Archives #12;Hazard Lewis Farms Collection Biographical Note The Hazard Lewis Farm was situated Hazard Lewis, one of the early pioneer settlers of Broome County. Colonel Lewis at one time with Christor

  20. JavaKollektionen Java Collection Framework

    E-Print Network [OSTI]

    Schürmann, Michael

    459 JavaKollektionen Java Collection Framework Bereitstellung wichtiger Kollektionen (Listen Implementierung häufig benutzter Algorithmen (Suchen, Sortieren, kleines/grö�tes Element, ...) Basis: java.util.Collection #12;460 Schnittstelle für alle Kollektionsklassen (1) Schnittstelle java.util.Collection Grö�e der

  1. Use of groundwater lifetime expectancy for the performance assessment of a deep geologic radioactive waste repository:2. Application to a Canadian Shield environment

    E-Print Network [OSTI]

    Park, Y -J; Normani, S D; Sykes, J F; Sudicky, E A

    2011-01-01

    Cornaton et al. [2007] introduced the concept of lifetime expectancy as a performance measure of the safety of subsurface repositories, based upon the travel time for contaminants released at a certain point in the subsurface to reach the biosphere or compliance area. The methodologies are applied to a hypothetical but realistic Canadian Shield crystalline rock environment, which is considered to be one of the most geologically stable areas on Earth. In an approximately 10\\times10\\times1.5 km3 hypothetical study area, up to 1000 major and intermediate fracture zones are generated from surface lineament analyses and subsurface surveys. In the study area, mean and probability density of lifetime expectancy are analyzed with realistic geologic and hydrologic shield settings in order to demonstrate the applicability of the theory and the numerical model for optimally locating a deep subsurface repository for the safe storage of spent nuclear fuel. The results demonstrate that, in general, groundwater lifetime exp...

  2. Evaluation of alternative leachate liner materials 

    E-Print Network [OSTI]

    Biles, Daniel Franklin

    1994-01-01

    The purpose of this study is to evaluate alternative landfill liner materials that could be utilized in conjunction with current liners in order to improve the liner's performance by preventing the release of hazardous chemicals into the subsurface...

  3. Radioactive waste isolation in salt: Peer review of the Fluor Technology, Inc. , report and position paper concerning waste emplacement mode and its effect on repository conceptual design

    SciTech Connect (OSTI)

    Hambley, D.F.; Russell, J.E.; Whitfield, R.G.; McGinnis, L.D.; Harrison, W.; Jacoby, C.H.; Bump, T.R.; Mraz, D.Z.; Busch, J.S.; Fischer, L.E.

    1987-02-01

    Recommendations for revising the Fluor Technology, Inc., draft position paper entitled Evaluation of Waste Emplacement Mode and the final report entitled Waste Package/Repository Impact Study include: reevaluate the relative rankings for the various emplacement modes; delete the following want objectives: maximize ability to locate the package horizon because sufficient flexibility exists to locate rooms in the relatively clean San Andres Unit 4 Salt and maximize far-field geologic integrity during retrieval because by definition the far field will be unaffected by thermal and stress perturbations caused by remining; give greater emphasis to want objectives regarding cost and use of present technology; delete the following statements from pages 1-1 and 1-2 of the draft position paper: ''No thought or study was given to the impacts of this configuration (vertical emplacement) on repository construction or short and long-term performance of the site'' and ''Subsequent salt repository designs adopted the vertical emplacement configuration as the accepted method without further evaluation.''; delete App. E and lines 8-17 of page 1-4 of the draft position paper because they are inappropriate; adopt a formal decision-analysis procedure for the 17 identified emplacement modes; revise App. F of the impact study to more accurately reflect current technology; consider designing the underground layout to take advantage of stress-relief techniques; consider eliminating reference to fuel assemblies <10 yr ''out-of-reactor''; model the temperature distribution, assuming that the repository is constructed in an infinitely large salt body; state that the results of creep analyses must be considered tentative until they can be validated by in situ measurements; and reevaluate the peak radial stresses on the waste package so that the calculated stress conditions more closely approximate expected in situ conditions.

  4. Citing and Reading Behaviors of High-Energy Physics or How a Community Stopped Worrying about Journals and Learned to Love Repositories

    SciTech Connect (OSTI)

    Gentil-Beccot, Anne; Mele, Salvatore; /CERN; Brooks, Travis C.; /SLAC

    2009-10-17

    Contemporary scholarly discourse follows many alternative routes in addition to the three-century old tradition of publication in peer-reviewed journals. The field of High-Energy Physics (HEP) has explored alternative communication strategies for decades, initially via the mass mailing of paper copies of preliminary manuscripts, then via the inception of the first online repositories and digital libraries. This field is uniquely placed to answer recurrent questions raised by the current trends in scholarly communication: is there an advantage for scientists to make their work available through repositories, often in preliminary form? Is there an advantage to publishing in Open Access journals? Do scientists still read journals or do they use digital repositories? The analysis of citation data demonstrates that free and immediate online dissemination of preprints creates an immense citation advantage in HEP, whereas publication in Open Access journals presents no discernible advantage. In addition, the analysis of clickstreams in the leading digital library of the field shows that HEP scientists seldom read journals, preferring preprints instead.

  5. Illustration of sampling-based approaches to the calculation of expected dose in performance assessments for the proposed high level radioactive waste repository at Yucca Mountain, Nevada.

    SciTech Connect (OSTI)

    Helton, Jon Craig (Arizona State University, Tempe, AZ); Sallaberry, Cedric J. PhD. (.; .)

    2007-04-01

    A deep geologic repository for high level radioactive waste is under development by the U.S. Department of Energy at Yucca Mountain (YM), Nevada. As mandated in the Energy Policy Act of 1992, the U.S. Environmental Protection Agency (EPA) has promulgated public health and safety standards (i.e., 40 CFR Part 197) for the YM repository, and the U.S. Nuclear Regulatory Commission has promulgated licensing standards (i.e., 10 CFR Parts 2, 19, 20, etc.) consistent with 40 CFR Part 197 that the DOE must establish are met in order for the YM repository to be licensed for operation. Important requirements in 40 CFR Part 197 and 10 CFR Parts 2, 19, 20, etc. relate to the determination of expected (i.e., mean) dose to a reasonably maximally exposed individual (RMEI) and the incorporation of uncertainty into this determination. This presentation describes and illustrates how general and typically nonquantitive statements in 40 CFR Part 197 and 10 CFR Parts 2, 19, 20, etc. can be given a formal mathematical structure that facilitates both the calculation of expected dose to the RMEI and the appropriate separation in this calculation of aleatory uncertainty (i.e., randomness in the properties of future occurrences such as igneous and seismic events) and epistemic uncertainty (i.e., lack of knowledge about quantities that are poorly known but assumed to have constant values in the calculation of expected dose to the RMEI).

  6. Restoration of areas disturbed by site studies for a mined commercial radioactive waste repository: The Basalt Waste Isolation Project (BWIP)

    SciTech Connect (OSTI)

    Brandt, C.A.; Rickard, W.H. Jr.; Biehert, R.W.; Newell, R.L.; Page, T.L.

    1989-01-01

    The Basalt Waste Isolation Project (BWIP) was undertaken to environmentally characterize a portion of the US Department of Energy's Hanford Site in Washington State as a potential host for the nation's first mined commercial nuclear waste repository. Studies were terminated by Congress in 1987. Between 1976 and 1987, 72 areas located across the Hanford Site were disturbed by the BWIP. These areas include borehole pads, a large Exploratory Shaft Facility, and the Near Surface Test Facility. Most boreholes were cleared of vegetation, leveled, and stabilized with a thick layer of compacted pit-run gravel and sand. The Near Surface Test Facility consists of three mined adits, a rock-spoils bench, and numerous support facilities. Restoration began in 1988 with the objective of returning sites to pre-existing conditions using native species. The Hanford Site retains some of the last remnants of the shrub-steppe ecosystem in Washington. The primary constraints to restoring native vegetation at Hanford are low precipitation and the presence of cheatgrass, an extremely capable alien competitor. 5 figs.

  7. Closure development for high-level nuclear waste containers for the tuff repository; Phase 1, Final report

    SciTech Connect (OSTI)

    Robitz, E.S. Jr.; McAninch, M.D. Jr.; Edmonds, D.P. [Babcock and Wilcox Co., Lynchburg, VA (USA). Nuclear Power Div.]|[Babcock and Wilcox Co., Alliance, OH (USA). Research and Development Div.

    1990-09-01

    This report summarizes Phase 1 activities for closure development of the high-level nuclear waste package task for the tuff repository. Work was conducted under U.S. Department of Energy (DOE) Contract 9172105, administered through the Lawrence Livermore National Laboratory (LLNL), as part of the Yucca Mountain Project (YMP), funded through the DOE Office of Civilian Radioactive Waste Management (OCRWM). The goal of this phase was to select five closure processes for further evaluation in later phases of the program. A decision tree methodology was utilized to perform an objective evaluation of 15 potential closure processes. Information was gathered via a literature survey, industrial contacts, and discussions with project team members, other experts in the field, and the LLNL waste package task staff. The five processes selected were friction welding, electron beam welding, laser beam welding, gas tungsten arc welding, and plasma arc welding. These are felt to represent the best combination of weldment material properties and process performance in a remote, radioactive environment. Conceptual designs have been generated for these processes to illustrate how they would be implemented in practice. Homopolar resistance welding was included in the Phase 1 analysis, and developments in this process will be monitored via literature in Phases 2 and 3. Work was conducted in accordance with the YMP Quality Assurance Program. 223 refs., 20 figs., 9 tabs.

  8. A simple lysimeter for soil water sampling in south Kati W. Migliaccio, Yuncong Li, Harry Trafford, and Edward Evans2

    E-Print Network [OSTI]

    Migliaccio, Kati White

    in leachate assists in assessing the effectiveness of management practices. One device researchers often use to estimate leachate properties is the lysimeter. Lysimeters are devices used to collect soil water in order soil types such as Krome soil and unusual research objectives such as capturing total leachate volumes

  9. Education Collections as Museum Collections SHANE J. MACFARLAN AND EILEEN JOHNSON

    E-Print Network [OSTI]

    concept behind education collections and hands-on exhibits is that visitors prefer them to static exhibitsEducation Collections as Museum Collections · · · · · SHANE J. MACFARLAN AND EILEEN JOHNSON abstract Museum education collections are inarguably a part of a museum's actual collec- tion, just

  10. Federal Depository Library Program: Services and Collections

    E-Print Network [OSTI]

    Jacobs, James A

    2009-01-01

    A society without digital libraries will be relying only onlibrary,” the idea of digital library collections naturallyIn the age of digital information, libraries and librarians

  11. Grier Periodical Collection and Diana Press Records

    E-Print Network [OSTI]

    Dean, Courtney

    2013-01-01

    Collection and Diana Press Records O ver the course of theSeattle’s Lesbian Resource Press, the preeminent lesbianmagazines, journals, and small press publications weekly

  12. Strategies for Collecting Household Energy Data | Department...

    Broader source: Energy.gov (indexed) [DOE]

    Strategies for Collecting Household Energy Data, Call Slides and Discussion Summary, July 19, 2012. Call Slides and Discussion Summary More Documents & Publications Homeowner and...

  13. Spent fuel disassembly hardware and other non-fuel bearing components: characterization, disposal cost estimates, and proposed repository acceptance requirements

    SciTech Connect (OSTI)

    Luksic, A.T.; McKee, R.W.; Daling, P.M.; Konzek, G.J.; Ludwick, J.D.; Purcell, W.L.

    1986-10-01

    There are two categories of waste considered in this report. The first is the spent fuel disassembly (SFD) hardware. This consists of the hardware remaining after the fuel pins have been removed from the fuel assembly. This includes end fittings, spacer grids, water rods (BWR) or guide tubes (PWR) as appropriate, and assorted springs, fasteners, etc. The second category is other non-fuel-bearing (NFB) components the DOE has agreed to accept for disposal, such as control rods, fuel channels, etc., under Appendix E of the standard utiltiy contract (10 CFR 961). It is estimated that there will be approximately 150 kg of SFD and NFB waste per average metric ton of uranium (MTU) of spent uranium. PWR fuel accounts for approximately two-thirds of the average spent-fuel mass but only 50 kg of the SFD and NFB waste, with most of that being spent fuel disassembly hardware. BWR fuel accounts for one-third of the average spent-fuel mass and the remaining 100 kg of the waste. The relatively large contribution of waste hardware in BWR fuel, will be non-fuel-bearing components, primarily consisting of the fuel channels. Chapters are devoted to a description of spent fuel disassembly hardware and non-fuel assembly components, characterization of activated components, disposal considerations (regulatory requirements, economic analysis, and projected annual waste quantities), and proposed acceptance requirements for spent fuel disassembly hardware and other non-fuel assembly components at a geologic repository. The economic analysis indicates that there is a large incentive for volume reduction.

  14. Commercial Building Energy Asset Score 2013 Pilot Data Collection...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Pilot Data Collection Form Commercial Building Energy Asset Score 2013 Pilot Data Collection Form This form is intended to facilitate your data collection. The Energy Asset Scoring...

  15. Hybrid Traffic Data Collection Roadmap: Objectives and Methods

    E-Print Network [OSTI]

    Bayen, Alexandre

    2013-01-01

    information environment. Hybrid Traffic Data CollectionBibliography Bibliography Hybrid Traffic Data Collection19, no. 1, p. 15–25, 2003. Hybrid Traffic Data Collection

  16. Hybrid Traffic Data Collection Roadmap: Objectives and Methods

    E-Print Network [OSTI]

    Bayen, Alexandre

    2013-01-01

    Traffic Data Collection Roadmap: Objectives and MethodsTraffic Data Collection Roadmap: Objectives and MethodsTraffic Data Collection Roadmap: Objectives and Methods

  17. Supplementary Information ISI Data Collection Appendix

    E-Print Network [OSTI]

    Igic, Boris

    Supplementary Information ISI Data Collection Appendix We collected reports from which relative a measure along with transparent calculation procedures. We searched the online databases ISI Web explicitly. Negative ISI values were set to zero in the main text analyses. A histogram of unmodified ISI

  18. Cambridge University Library Collection Development Policy framework

    E-Print Network [OSTI]

    Cambridge, University of

    importance by stating that it will continue its cultural heritage role as a National Research LibraryCambridge University Library Collection Development Policy framework 1. Scope This policy is intended as a framework to guide collection development in Cambridge University Library and its affiliated

  19. Collective Mind: Continuous, Automatic Learning to

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    : ?? Collective: Peers are units with similar operational & maintenance profiles Peer experience forms Mission: Actively Manage the Maintenance Process ­ Operating at All Levels, All Phases of Operations ­ ContinuouslyCollective Mind: Continuous, Automatic Learning to Improve Equipment Maintenance DoD Great Ideas

  20. Collective neutrino oscillations and spontaneous symmetry breaking

    E-Print Network [OSTI]

    Duan, Huaiyu

    2015-01-01

    Neutrino oscillations in a hot and dense astrophysical environment such as a core-collapse supernova pose a challenging, seven-dimensional flavor transport problem. To make the problem even more difficult (and interesting), neutrinos can experience collective oscillations through nonlinear refraction in the dense neutrino medium in this environment. Significant progress has been made in the last decade towards the understanding of collective neutrino oscillations in various simplified neutrino gas models with imposed symmetries and reduced dimensions. However, a series of recent studies seem to have "reset" this progress by showing that these models may not be compatible with collective neutrino oscillations because the latter can break the symmetries spontaneously if they are not imposed. We review some of the key concepts of collective neutrino oscillations by using a few simple toy models. We also elucidate the breaking of spatial and directional symmetries in these models because of collective oscillation...

  1. Sample collection system for gel electrophoresis

    DOE Patents [OSTI]

    Olivares, Jose A.; Stark, Peter C.; Dunbar, John M.; Hill, Karen K.; Kuske, Cheryl R.; Roybal, Gustavo

    2004-09-21

    An automatic sample collection system for use with an electrophoretic slab gel system is presented. The collection system can be used with a slab gel have one or more lanes. A detector is used to detect particle bands on the slab gel within a detection zone. Such detectors may use a laser to excite fluorescently labeled particles. The fluorescent light emitted from the excited particles is transmitted to low-level light detection electronics. Upon the detection of a particle of interest within the detection zone, a syringe pump is activated, sending a stream of buffer solution across the lane of the slab gel. The buffer solution collects the sample of interest and carries it through a collection port into a sample collection vial.

  2. Towards Collecting Sustainability Data in Supply Chains with Flexible Data Collection

    E-Print Network [OSTI]

    Ulm, Universität

    Towards Collecting Sustainability Data in Supply Chains with Flexible Data Collection Processes) face rising pressure from customers and legal regulations to produce more sustainable products. This involves the reporting and publishing of various sustainability indicators. However, the demands of legal

  3. A compound power-law model for volcanic eruptions: Implications for risk assessment of volcanism at the proposed nuclear waste repository at Yucca Mountain, Nevada

    SciTech Connect (OSTI)

    Ho, Chih-Hsiang

    1994-10-17

    Much of the ongoing debate on the use of nuclear power plants in U.S.A. centers on the safe disposal of the radioactive waste. Congress, aware of the importance of the waste issue, passed the Nuclear Waste Policy Act of 1982, requiring the federal government to develop a geologic repository for the permanent disposal of high level radioactive wastes from civilian nuclear power plants. The Department of Energy (DOE) established the Office of Civilian Radioactive Waste Management (OCRWM) in 1983 to identify potential sites. When OCRWM had selected three potential sites to study, Congress enacted the Nuclear Waste Policy Amendments Act of 1987, which directed the DOE to characterize only one of those sites, Yucca Mountain, in southern Nevada. For a site to be acceptable, theses studies must demonstrate that the site could comply with regulations and guidelines established by the federal agencies that will be responsible for licensing, regulating, and managing the waste facility. Advocates and critics disagree on the significance and interpretation of critical geological features which bear on the safety and suitability of Yucca Mountain as a site for the construction of a high-level radioactive waste repository. Recent volcanism in the vicinity of Yucca Mountain is readily recognized as an important factor in determining future public and environmental safety because of the possibility of direct disruption of a repository site by volcanism. In particular, basaltic volcanism is regarded as direct and unequivocal evidence of deep-seated geologic instability. In this paper, statistical analysis of volcanic hazard assessment at the Yucca Mountain site is discussed, taking into account some significant geological factors raised by experts. Three types of models are considered in the data analysis. The first model assumes that both past and future volcanic activities follow a homogeneous Poisson process (HPP).

  4. Geology of the Yucca Mountain Region, Chapter in Stuckless, J.S., ED., Yucca Mountain, Nevada - A Proposed Geologic Repository for High-Level Radioactive Waste

    SciTech Connect (OSTI)

    J.S. Stuckless; D. O'Leary

    2006-09-25

    Yucca Mountain has been proposed as the site for the Nation's first geologic repository for high-level radioactive waste. This chapter provides the geologic framework for the Yucca Mountain region. The regional geologic units range in age from late Precambrian through Holocene, and these are described briefly. Yucca Mountain is composed dominantly of pyroclastic units that range in age from 11.4 to 15.2 Ma. The proposed repository would be constructed within the Topopah Spring Tuff, which is the lower of two major zoned and welded ash-flow tuffs within the Paintbrush Group. The two welded tuffs are separated by the partly to nonwelded Pah Canyon Tuff and Yucca Mountain Tuff, which together figure prominently in the hydrology of the unsaturated zone. The Quaternary deposits are primarily alluvial sediments with minor basaltic cinder cones and flows. Both have been studied extensively because of their importance in predicting the long-term performance of the proposed repository. Basaltic volcanism began about 10 Ma and continued as recently as about 80 ka with the eruption of cones and flows at Lathrop Wells, approximately 10 km south-southwest of Yucca Mountain. Geologic structure in the Yucca Mountain region is complex. During the latest Paleozoic and Mesozoic, strong compressional forces caused tight folding and thrust faulting. The present regional setting is one of extension, and normal faulting has been active from the Miocene through to the present. There are three major local tectonic domains: (1) Basin and Range, (2) Walker Lane, and (3) Inyo-Mono. Each domain has an effect on the stability of Yucca Mountain.

  5. Conceptual waste package interim product specifications and data requirements for disposal of borosilicate glass defense high-level waste forms in salt geologic repositories

    SciTech Connect (OSTI)

    Not Available

    1983-06-01

    The conceptual waste package interim product specifications and data requirements presented are applicable specifically to the normal borosilicate glass product of the Defense Waste Processing Facility (DWPF). They provide preliminary numerical values for the defense high-level waste form parameters and properties identified in the waste form performance specification for geologic isolation in salt repositories. Subject areas treated include containment and isolation, operational period safety, criticality control, waste form/production canister identification, and waste package performance testing requirements. This document was generated for use in the development of conceptual waste package designs in salt. It will be revised as additional data, analyses, and regulatory requirements become available.

  6. Characterization, propagation and analysis of aleatory and epistemic uncertainty in the 2008 performance assessment for the proposed repository for radioactive waste at Yucca Mountain, Nevada.

    SciTech Connect (OSTI)

    Helton, Jon Craig; Sallaberry, Cedric M.; Hansen, Clifford W.

    2010-10-01

    The 2008 performance assessment (PA) for the proposed repository for high-level radioactive waste at Yucca Mountain (YM), Nevada, illustrates the conceptual structure of risk assessments for complex systems. The 2008 YM PA is based on the following three conceptual entities: a probability space that characterizes aleatory uncertainty; a function that predicts consequences for individual elements of the sample space for aleatory uncertainty; and a probability space that characterizes epistemic uncertainty. These entities and their use in the characterization, propagation and analysis of aleatory and epistemic uncertainty are described and illustrated with results from the 2008 YM PA.

  7. Background studies in support of a feasibility assessment on the use of copper-base materials for nuclear waste packages in a repository in tuff

    SciTech Connect (OSTI)

    Van Konynenburg, R.A.; Kundig, K.J.A.; Lyman, W.S.; Prager, M.; Meyers, J.R.; Servi, I.S.

    1990-06-01

    This report combines six work units performed in FY`85--86 by the Copper Development Association and the International Copper Research Association under contract with the University of California. The work includes literature surveys and state-of-the-art summaries on several considerations influencing the feasibility of the use of copper-base materials for fabricating high-level nuclear waste packages for the proposed repository in tuff rock at Yucca Mountain, Nevada. The general conclusion from this work was that copper-base materials are viable candidates for inclusion in the materials selection process for this application. 55 refs., 48 figs., 22 tabs.

  8. Investigation of two-phase flow phenomena associated with corrosion in an SF/HLW repository in Opalinus Clay, Switzerland

    SciTech Connect (OSTI)

    Senger, R.; Marschall, P.; Finsterle, S.

    2008-08-04

    Gas generation from corrosion of the waste canisters and gas accumulation in the backfilled emplacement tunnels is a key issue in the assessment of long-term radiological safety of the proposed repository for spent fuel and high-level waste (SF/HLW) sited in the Opalinus Clay formation of Northern Switzerland. Previous modeling studies indicated a significant pressure buildup in the backfilled emplacement tunnels for those sensitivity runs, where corrosion rates were high and the permeability of the Opalinus Clay was very low. As an extension to those studies, a refined process model of the canister corrosion phenomena has been developed, which accounts not only for the gas generation but also for the water consumption associated with the chemical reaction of corrosion of steel under anaerobic conditions. The simulations with the new process model indicate, that with increasing corrosion rates and decreasing host-rock permeability, pressure buildup increased, as expected. However, the simulations taking into account water consumption show that the pressure buildup is reduced compared to the simulation considering only gas generation. The pressure reduction is enhanced for lower permeability of the Opalinus Clay and for higher corrosion rates, which correspond to higher gas generations rates and higher water consumption rates. Moreover, the simulated two-phase flow patterns in the engineered barrier system (EBS) and surrounding Opalinus Clay show important differences at late time of the gas production phase as the generated gas continues to migrate outward into the surrounding host rock. For the case without water consumption, the water flow indicates overall downward flow due to a change in the overall density of the gas-fluid mixture from that based on the initially prescribed hydrostatic pressure gradient. For the case with water consumption, water flow converges toward the waste canister at a rate corresponding to the water consumption rate associated with the corrosion reaction. The water flow toward the canister is maintained even for very low permeabilities of the Opalinus clay, sustaining the anaerobic corrosion of the steel canister.

  9. Collective plasma effects in scattering of radiation in astrophysical plasmas (Collective plasma processes and the solar neutrino problem)

    E-Print Network [OSTI]

    Tsytovich, V N; De Angelis, U; Forlani, A

    1995-01-01

    Collective plasma effects in scattering of radiation in astrophysical plasmas (Collective plasma processes and the solar neutrino problem)

  10. Web Feeds and Repositories

    E-Print Network [OSTI]

    Downing, Jim

    2008-12-09

    ="http://example.org/2003/12/13/atom03"/> urn:uuid:1225c695-cfb8-4ebb-aaaa-80da344efa6a 2003-12-13T18:30:02Z Some text. Subscription Feed

  11. Request Repository Mailing List

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDid youOxygen Generation |Publications TheGashome / Related LinksEnergySREL

  12. 2015 Information Repository Documents

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.TheoryTuesday, August 10, 2010 james-r.giusti@srs.govTuesday,25 Information

  13. Salt Repository Research,

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust, High-Throughput Analysis of Protein1-0845*RV6STATDecember29/2011Yes Virginia, There is an

  14. Salt Repository Research,

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust, High-Throughput Analysis of Protein1-0845*RV6STATDecember29/2011Yes Virginia, There is

  15. Geothermal Data Repository

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDid you not findGeoscience/Environment Geoscience/Environment Print From

  16. Geothermal Data Repository

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDid you not findGeoscience/Environment Geoscience/Environment Print

  17. Geothermal Data Repository

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDid you not findGeoscience/Environment Geoscience/Environment PrintNot

  18. Geothermal Data Repository

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory of rare Kaonforsupernovae model (Journal About DOE ButtonFSOWiki Apps Datasets

  19. Geothermal Data Repository

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation Current HABFESOpportunities NuclearlongGeneralGeorgePage Unknown The page you

  20. OSTI OAI Repository Manual

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformationJesseworkSURVEY UNIVERSEHow ORISE isParisTeam Office ofScientificSharing

  1. Ya ri a bsod Collection 7

    E-Print Network [OSTI]

    Sha bo don 'grub rdo rje; Skal dbang skyid

    /?????????? ??????????????????????? ??????????????????? ??????????? Tape No. / Track / Item No. Ya ri a bsod Collection 7.MP3 Length of track 00:01:27 Related tracks (include description/relationship if appropriate) Title of track Praise Song...

  2. Internal Benchmarking Outreach and Data Collection Techniques

    Broader source: Energy.gov [DOE]

    U.S. Department of Energy (DOE) Technical Assistance Program (TAP) presentation at a TAP webinar held on April 11, 2013 and dealing with internal benchmarking outreach and data collection techniques.

  3. Underwater Data Collection Using Robotic Sensor Networks

    E-Print Network [OSTI]

    Hollinger, Geoffrey A.

    We examine the problem of utilizing an autonomous underwater vehicle (AUV) to collect data from an underwater sensor network. The sensors in the network are equipped with acoustic modems that provide noisy, range-limited ...

  4. Ya ri a bsod Collection 6

    E-Print Network [OSTI]

    Sha bo don 'grub rdo rje; Skal dbang skyid

    /?????????? ??????????????????????? ??????????????????? ??????????? Tape No. / Track / Item No. Ya ri a bsod Collection 6.MP3 Length of track 00:00:22 Related tracks (include description/relationship if appropriate) Title of track Unknown Translation...

  5. ELECTRICITY AND NATURAL GAS DATA COLLECTION

    E-Print Network [OSTI]

    CALIFORNIA ENERGY COMMISSION HISTORICAL ELECTRICITY AND NATURAL GAS DATA COLLECTION Formsand of Power Plants Semi-Annual Report ..................................... 44 CEC-1306D UDC Natural Gas Tolling Agreement Quarterly Report.......................... 46 i #12;Natural Gas Utilities and Retailers

  6. COLLECTIVE AGREEMENT THE UNIVERSITY OF WESTERN ONTARIO

    E-Print Network [OSTI]

    Lennard, William N.

    COLLECTIVE AGREEMENT Between THE UNIVERSITY OF WESTERN ONTARIO and CANADIAN UNION OF PUBLIC into the 1st day of July 2014 BETWEEN: THE UNIVERSITY OF WESTERN ONTARIO (hereinafter called the "Employer

  7. Nanodiamond Collective Electron States and their Localization

    E-Print Network [OSTI]

    Ivan A. Denisov; Andrey A. Zimin; Leslie A. Bursill; Peter I. Belobrov

    2013-07-24

    The existence and localization of collective electron states for nanodiamond particles were studied both by solving a one-particle one-dimensional Schr\\"odinger equation in the Kronig-Penney potential and by ab initio computations of ground state wavefunctions of diamondoids C78H64, C123H100 and C211H140 at the DFT R-B3LYP/6-31G(d,p) level of theory. Three distinct classes of collective electron states have been found: collective bonding orbitals resembling the morphology of 3D-modulated particle in a box solutions; surface-localized non-bonding conductive Tamm states and subsurface-localized bonding states for non-uniformly compressed nanodiamond. Quantum-mechanical analysis shows that collective unpaired electrons are intrinsic to nanodiamond. Their subsurface localization is described in terms of surface compression arising from a self-consistency condition of the electron-nuclear wavefunction. Intrinsic spin existence is supposed to result from the collective and spread nature of subsurface orbitals, allowing spin-density fluctuation effects to become significant on this length scale. Suggested model allows to explain free spins of nanodiamond exhibited in experiments.

  8. Data Collection1 Associated with Fish Tagging/Marking Technologies

    E-Print Network [OSTI]

    Data Collection1 Associated with Fish Tagging/Marking Technologies Tag/Mark & Release Juvenile fish application: automated Data collection: manual Data upload: manual Collection locations: mainstem, tributary Data collection: visual/manual Data upload: manual Data collection: visual/manual Data upload: manual

  9. Disposal of oil spill cleanup collections

    SciTech Connect (OSTI)

    Wehrle, J.P.; Fisher, E.C.; Ness, J.R.; Howell, B.

    1995-12-01

    When in-situ ignition and burning oil slicks is not feasible, skimming the oil slicks by means of skimmer vessels has been used. The skimmer vessels collect the oil from the oil slick locations with a significant amount of water, such as 9 gallons of water for each gallon of oil recovered. The containment tanks associated with such skimmer vessels are rapidly filled with volumetrically large oil and water collections having relatively small amounts of the oil requiring frequent returns to shore for off-loading, causing interruptions in the cleanup operation during which oil slick spreading occurs. Because of such cleanup interruption difficulty, oil combustion aboard the skimming vessel may be used for a more rapid and continuous cleanup operation. However, such on-board combustion of the collected oil also involves considerable air pollution from in-situ discharge of gas combustion products.

  10. Superradiance and collective gain in multimode optomechanics

    E-Print Network [OSTI]

    T. Kipf; G. S. Agarwal

    2014-10-21

    We present a description of a strongly driven multimode optomechanical system that shows the emergence of cooperative effects usually known from systems of atom-light interaction. Our calculations show that under application of a coherent pump field the system's response can be switched from a superradiant regime to a collective gain regime by varying the frequency detuning of the pump. In the superradiant regime, enhanced optical cooling of a single vibrational mode is possible, whereas the collective gain regime would potentially enable one to achieve almost thresholdless phonon laser action. The threshold pumping power scales as 1/N.

  11. Climate Change as a ‘Hard’ Case of Collective Responsibility 

    E-Print Network [OSTI]

    Seibokaite, Aiste

    2013-01-01

    Climate change poses a challenge to moral philosophy. Because of the nature of the harms – brought about collectively, it seems like a case of collective responsibility1. But none of the existing theories of collective responsibility seem capable...

  12. Evaluation of pedestrian data collection methods within a simulation framework

    E-Print Network [OSTI]

    Bierlaire, Michel

    Evaluation of pedestrian data collection methods within a simulation framework Mamy Fetiarison Gunnar Flötteröd Michel Bierlaire STRC 2010 September 2010 #12;Evaluation of pedestrian data collection methods within a simulation framework September 2010 STRC 2010 Evaluation of pedestrian data collection

  13. YUCCA MOUNTAIN PROJECT 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

    SciTech Connect (OSTI)

    NA

    2002-03-26

    For more than half a century, since nuclear science helped us win World War II and ring in the Atomic Age, scientists have known that !he Nation would need a secure, permanent facility in which to dispose of radioactive wastes. Twenty years ago, when Congress adopted the Nuclear Waste Policy Act of 1982 (NWPA or ''the Act''), it recognized the overwhelming consensus in the scientific community that the best option for such a facility would be a deep underground repository. Fifteen years ago, Congress directed the Secretary of Energy to investigate and recommend to the President whether such a repository could be located safely at Yucca Mountain, Nevada. Since then, our country has spent billions of dollars and millions of hours of research endeavoring to answer this question. I have carefully reviewed the product of this study. In my judgment, it constitutes sound science and shows that a safe repository can be sited there. I also believe that compelling national interests counsel in favor of proceeding with this project. Accordingly, consistent with my responsibilities under the NWPA, today I am recommending that Yucca Mountain be developed as the site for an underground repository for spent fuel and other radioactive wastes. The first consideration in my decision was whether the Yucca Mountain site will safeguard the health and safety of the people, in Nevada and across the country, and will be effective in containing at minimum risk the material it is designed to hold. Substantial evidence shows that it will. Yucca Mountain is far and away the most thoroughly researched site of its kind in the world. It is a geologically stable site, in a closed groundwater basin, isolated on thousands of acres of Federal land, and farther from any metropolitan area than the great majority of less secure, temporary nuclear waste storage sites that exist in the country today. This point bears emphasis. We are not confronting a hypothetical problem. We have a staggering amount of radioactive waste in this country--nearly 100,000,000 gallons of high-level nuclear waste and more than 40,000 metric tons of spent nuclear fuel with more created every day. Our choice is not between, on the one hand, a disposal site with costs and risks held to a minimum, and, on the other, a magic disposal system with no costs or risks at all. Instead, the real choice is between a single secure site, deep under the ground at Yucca Mountain, or making do with what we have now or some variant of it--131 aging surface sites, scattered across 39 states. Every one of those sites was built on the assumption that it would be temporary. As time goes by. every one is closer to the limit of its safe life span. And every one is at least a potential security risk--safe for today, but a question mark in decades to come.

  14. Heat Flow Database Expansion for NGDS Data Development, Collection...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Heat Flow Database Expansion for NGDS Data Development, Collection and Maintenance (SMU) Heat Flow Database Expansion for NGDS Data Development, Collection and Maintenance (SMU)...

  15. Building America Webinar: Opportunities in Large Data Collection...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    in Large Data Collection and Analysis-Presentation 1 Building America Webinar: Opportunities in Large Data Collection and Analysis-Presentation 1 This presentation is titled...

  16. EPA-GHG Inventory Targeted Data Collection Strategies and Software...

    Open Energy Info (EERE)

    EPA-GHG Inventory Targeted Data Collection Strategies and Software Tools (Redirected from US EPA GHG Inventory Targeted Data Collection Strategies and Software Tools) Jump to:...

  17. Wireless technology collects real-time information from oil and...

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

    Wireless technology collects real-time information from oil and gas wells Wireless technology collects real-time information from oil and gas wells The patented system delivers...

  18. Using Public Participation to Improve MELs Energy Data Collection

    E-Print Network [OSTI]

    Cheung, Iris Hoi Ying

    2014-01-01

    to Improve MELs Energy Data Collection Iris Cheung,for collecting MELs energy data through crowdsourcing. Weon test devices rather than energy data, but the goal was to

  19. Scalable Run Time Data Collection Analysis and Visualization...

    Office of Scientific and Technical Information (OSTI)

    Scalable Run Time Data Collection Analysis and Visualization (Presentation). Citation Details In-Document Search Title: Scalable Run Time Data Collection Analysis and Visualization...

  20. Understanding Collection-Related Losses in Organic Solar Cells...

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

    Understanding Collection-Related Losses in Organic Solar Cells Home > Research > ANSER Research Highlights > Understanding Collection-Related Losses in Organic Solar Cells...