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1

Tracer method to measure landfill gas emissions from leachate collection systems  

Science Journals Connector (OSTI)

This paper describes a method developed for quantification of gas emissions from the leachate collection system at landfills and present emission data measured at two Danish landfills with no landfill gas collection systems in place: Fakse landfill and AV Miljř. Landfill top covers are often designed to prevent infiltration of water and thus are made from low permeable materials. At such sites a large part of the gas will often emit through other pathways such as the leachate collection system. These point releases of gaseous constituents from these locations cannot be measured using traditional flux chambers, which are often used to measure gas emissions from landfills. Comparing tracer measurements of methane (CH4) emissions from leachate systems at Fakse landfill and AV Miljř to measurements of total CH4 emissions, it was found that approximately 47% (351 kg CH4 d?1) and 27% (211 kg CH4 d?1), respectively, of the CH4 emitting from the sites occurred from the leachate collection systems. Emission rates observed from individual leachate collection wells at the two landfills ranged from 0.1 to 76 kg CH4 d?1. A strong influence on emission rates caused by rise and fall in atmospheric pressure was observed when continuously measuring emission from a leachate well over a week. Emission of CH4 was one to two orders of magnitude higher during periods of decreasing pressure compared to periods of increasing pressure.

Anders M. Fredenslund; Charlotte Scheutz; Peter Kjeldsen

2010-01-01T23:59:59.000Z

2

Unusual calcite stromatolites and pisoids from a landfill leachate collection system  

Science Journals Connector (OSTI)

...with leachate. The remaining void space is filled with landfill gas, which is composed mainly of methane and carbon dioxide...with leachate. The remaining void space is filled with landfill gas, which is composed mainly of methane and carbon dioxide...

3

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

E-Print Network (OSTI)

recent advances in aircraft engines, the determinant energy-saving factors are reducing weightScience Arts & MĂ©tiers (SAM) is an open access repository that collects the work of Arts et MĂ©tiers The aerospace industry is aiming, more than ever, to reduce their energy consumptions and emissions. Despite

Paris-Sud XI, Université de

4

Indicating landfill stabilization state by using leachate property from Laogang Refuse Landfill  

Science Journals Connector (OSTI)

Variation and evolution process of leachate can be applied as a reference for landfill stabilization phase. In this work, leachates ... with different ages were collected from Laogang Refuse Landfill, and charact...

Ziyang Lou; Xiaoli Chai; Youcai Zhao…

2014-06-01T23:59:59.000Z

5

Bomb-Pulse Chlorine-36 at the Proposed Yucca Mountain Repository Horizon: An Investigation of Previous Conflicting Results and Collection of New Data  

SciTech Connect

Previous studies Los Alamos National Laboratory (LANL) found elevated ratios of chlorine-36 to total chloride (36Cl/Cl) in samples of rock collected from the Exploratory Studies Facility (ESF) at Yucca Mountain (YM). The data were interpreted as an indication that fluids containing “bomb-pulse” 36Cl reached the repository horizon in the ~50 years since the peak period of above-ground nuclear testing. Due to the significance of 36Cl data to conceptual models of unsaturated zone flow, the United States Geological Survey (USGS) implemented a study to validate the LANL findings. The USGS drilled new boreholes at select locations across zones where bomb-pulse ratios had previously been identified. The drill cores were analyzed at Lawrence Livermore National Laboratory (LLNL). Because consensus was not reached between the USGS/LLNL and LANL on several fundamental points including the presence or absence of bomb-pulse 36Cl, an evaluation by the University of Nevada, Las Vegas (UNLV), was initiated. The overall objectives of the UNLV study were to investigate the source of the validation study’s conflicting results, and to obtain additional data on bomb-pulse isotopes at the repository horizon. UNLV engaged in discussions with previous investigators, reviewed reports, and analyzed archived samples. UNLV also collected new samples of rock from the ESF, soil profiles from the surface of YM, and samples of seep water from inside the ESF. Samples were analyzed for 36Cl/Cl ratios, and 99Tc and 129I in select samples. A column experiment was conducted mimicking the passage of bomb-pulse 36Cl through YM tuff. The work faced several obstacles including an extended shutdown of the tunnel. Only one sample yielded a background corrected 36Cl/Cl ratio that was higher than the accepted bomb-pulse threshold (1250 x 10-15). Specimen 01034214 obtained from the Drill Hole Wash fault (19+33) had a ratio of 1590 ± 80 (1?) x10-15, whereas the other separate sample from this fault zone yielded 1160 ± 50 (1?) x 10-15. Three samples collected from Alcove 6 averaged 490 ± 100 (1?) x10-15; a sample from Sundance Fault resulted in a ratio of 920 ± 60 (1?) x10-15, and a sample from the Bow Ridge Fault produced 530 ± 20 (1?) x10-15. The results are significant because: 1) they tend to be lower than LANL data for comparable samples, albeit in agreement with the range of data produced in the area, and 2) they show that a bomb-pulse 36Cl/Cl ratio was measured in rock collected at the repository horizon level by a second and independent group of investigators (UNLV). Because of time UNLV was not able to replicate the results, and these few data points are insufficient to draw major and definitive conclusions. Leachates of soil samples collected from the surface above the ESF yielded several ratios with bomb-pulse 36Cl, particularly for samples encompassing the wetting front. Soil samples collected above the south ramp, where there was limited soil coverage due to a large amount of rock outcrop, had relatively large ratios ranging from 2170 ± 110 (1?) x10-15 to 5670 ± 350 (1?) x10-15. Soil samples from profiles from above the north ramp ranged from 820 ± 70 (1?) x10-15 to 2390 ± 160 (1?) x10-15, which compare favorably with previous measurements near the site. Water seepage into the ESF south ramp and 36Cl standards made from NIST material were also analyzed. The standards were produced to have nominal 36Cl/Cl ratios (10-15) of 500, 2,500 and 10,000 and the results showed good agreement with the calculated ratios. The seepage samples ranged between 680 ± 40 (1?) x10-15 to 1110 ± 40 (1?) x10-15, consistent with that found for modern meteoric water, with a small bomb-pulse component. Bomb-pulse 36Cl may not have been incorporated in this fast-path water because the surface above the infiltration zone consists mostly of outcrop and the flow pathways have probably mostly been leached. 99Tc was measured in five of nine leaches of ESF rock but poor analytical recoveries and lack of data overlap with 36Cl limit interpretations of these data

Cizdziel, James

2006-07-31T23:59:59.000Z

6

Geochemistry of trench leachates from Maxey Flats disposal site  

SciTech Connect

The results of the analysis of trench leachates collected at Maxey Flats in October 1981 are presented, and the geochemical factors controlling the trench water chemistry are discussed. In addition, results of laboratory oxidation experiments performed on trench leachates, simulating the behavior of anoxic trench waters as they encounter upon migration an oxidizing environment, are presented.

Dayal, R.; Pietrzak, R.F.; Clinton, J.; Kinsley, M.

1983-01-01T23:59:59.000Z

7

Landfill Leachate Control  

Science Journals Connector (OSTI)

Leachate refers to the liquid, contaminated water, that results from the interaction between any water in a landfill, e.g., as the result of rainwater infiltration, and the waste emplaced in the landfill. Lea...

Dr. Haluk Akgün; Jaak J. K. Daemen

2012-01-01T23:59:59.000Z

8

Reverse osmosis module successfully treats landfill leachate  

SciTech Connect

By law, modern landfills are to be constructed with double liners to prevent contaminants from leaching into surface and ground water. Despite this design feature, however, both hazardous and non-hazardous compounds do leach from the waste disposed in landfills. The resulting contaminated water, or leachate, must be collected and treated. Rochem Environmental, Inc. (Houston, Texas) has developed a new membrane process, known as the Disc Tube{trademark} system, to remove a variety of contaminants from landfill leachate. 1 ref., 1 fig., 2 tabs.

NONE

1995-03-01T23:59:59.000Z

9

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

E-Print Network (OSTI)

should be sent to the repository Administrator : archiveouverte@ensam.eu #12;OIPE (Optimization and furthermore they can cause magnet heating which increases the risk of magnet demagnetization, leading finally

Boyer, Edmond

10

Leachate Free Hazardous Waste Landfill  

Science Journals Connector (OSTI)

Experiences of the past few decades have shown that controlling leachate cannot be done by sealing only the landfill bed, but rather by sealing landfill top cover.

Dipl.Ing. Karl Rohrhofer; Dr.Techn. Fariar Kohzad

1990-01-01T23:59:59.000Z

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)

) Hydrogen embrittlement susceptibility of a high strength steel X80. Materials Science and Engineering A be sent to the repository administrator: staff-oatao@inp-toulouse.fr. #12;Hydrogen embrittlement/INPT/CNRS, 4 allée Emile Monso, 31432 Toulouse Cedex 4, France Keywords: X80 Hydrogen embrittlement HELP HID

Mailhes, Corinne

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)

) Influence of the anion specificity on the anodic polarization of titanium. Corrosion Science, vol. 53 (n° 4 to the repository administrator: staff-oatao@inp-toulouse.fr. #12;Influence of the anion specificity on the anodic Keywords: A. Titanium B. Polarization C. Pitting corrosion a b s t r a c t The anodic polarization

Mailhes, Corinne

13

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

E-Print Network (OSTI)

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

14

Electrochemical treatment of landfill leachate  

Science Journals Connector (OSTI)

Electrochemical methods can offer an elegant contribution towards environmental control as electrons provide a means of removing pollutants by redox reactions. In the process of electrochemical oxidation the main aim has been to convert oxidisable species into carbon dioxide. Leachate originating in landfills is complex wastewater that could exert high environmental impact. This study aims to treat the landfill leachate in order to meet the inland disposal standards. The removal of pollutants was studied with different anode materials in electrochemical process. The treatment of leachate by electrochemical oxidation was carried out in a batch electrolytic parallel plate reactor. The electrochemical process was carried out separately with stainless steel as cathode and anode materials aluminium and titanium/platinum electrodes. The effects of the operating factors such as current density, reaction time, chloride ion concentration, additional electrolyte such as sulphuric acid that influence the removal of pollutant from leachate electrochemically were studied.

C. Ramprasad; A. Navaneetha Gopalakrishnan

2012-01-01T23:59:59.000Z

15

Recirculation of municipal landfill leachate  

E-Print Network (OSTI)

RECIRCULATION OF MUNICIPAL LANDFILL LEACHATE A Thesis by BRIAN JUDE PINKO4ISKI Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE May 1987 Major Subject...: Civil Engineering RECIRCULATION OF MUNICIPAL LANDFILL LEACHATE A Thesis by BRIAN JUDE PINKOWSKI Approved as to style and content by: Charles P. Giammona (Chair of Committee) Roy . Harm, (Member) Kirk W. Brown (Member) Donald A. Maxwel...

Pinkowski, Brian Jude

2012-06-07T23:59:59.000Z

16

Bomb-Pulse Chlorine-36 At The Proposed Yucca Mountain Repository Horizon: An Investigation Of Previous Conflicting Results And Collection Of New Data  

SciTech Connect

Previous studies by scientists at Los Alamos National Laboratory (LANL) found elevated ratios of chlorine-36 to total chloride ({sup 36}Cl/Cl) in samples of rock collected from the Exploratory Studies Facility (ESF) and the Enhanced Characterization of the Repository Block (ECRB) at Yucca Mountain as the tunnels were excavated. The data were interpreted as an indication that fluids containing 'bomb-pulse' {sup 36}Cl reached the repository horizon in the {approx}50 years since the peak period of above-ground nuclear testing. Moreover, the data support the concept that so-called fast pathways for infiltration not only exist but are active, possibly through a combination of porous media, faults and/or other geologic features. Due to the significance of {sup 36}Cl data to conceptual models of unsaturated zone flow and transport, the United States Geological Survey (USGS) was requested by the Department of Energy (DOE) to design and implement a study to validate the LANL findings. The USGS chose to drill new boreholes at select locations across zones where bomb-pulse ratios had previously been identified. The drill cores were analyzed at Lawrence Livermore National Laboratory (LLNL) for {sup 36}Cl/Cl using both active and passive leaches, with the USGS/LLNL concluding that the active leach extracted too much rock-Cl and the passive leach did not show bomb-pulse ratios. Because consensus was not reached between the USGS/LLNL and LANL on several fundamental points, including the conceptual strategy for sampling, interpretation and use of tritium ({sup 3}H) data, and the importance and interpretation of blanks, in addition to the presence or absence of bomb-pulse {sup 36}Cl, an evaluation by an independent entity, the University of Nevada, Las Vegas (UNLV), using new samples was initiated. This report is the result of that study. The overall objectives of the UNLV study were to investigate the source or sources of the conflicting results from the previous validation study, and to obtain additional data to determine whether or not there are bomb-pulse isotopes at the repository horizon. To that en4 we have engaged in discussions with previous investigators, reviewed reports, and analyzed archived samples. We have also collected new samples of rock from the ESF, soil profiles from the surface of Yucca Mountain, and opportunistic samples of seep water from inside the south ramp of the ESF.

J. Cizdziel

2006-07-28T23:59:59.000Z

17

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

E-Print Network (OSTI)

the problems associated with the intermittent nature of solar energy. The aim is to collect and store solar this version : David LUNA, Jean-Pierre NADEAU, Yves JANNOT - Model and simulation of a solar kiln with energy.03.024 #12;Model and simulation of a solar kiln with energy storage D. Luna a , J.-P. Nadeau a,*, Y. Jannot b

Boyer, Edmond

18

Characterization of Plutonium in Maxey Flats Radioactive Trench Leachates  

Science Journals Connector (OSTI)

...leachates at the Maxey Flats radioactive waste disposal site exists as dissolved...leachates at the Maxey Flats radioactive waste disposal site exists as dissolved...leachates at the Maxey Flats radioactive waste disposal site exists as dissolved...

JESS M. CLEVELAND; TERRY F. REES

1981-06-26T23:59:59.000Z

19

Municipal landfill leachate treatment by SBBGR technology  

Science Journals Connector (OSTI)

The paper reports the results of a laboratory-scale investigation aimed at evaluating the performance of a periodic biofilter with granular biomass (SBBGR) for treating leachate coming from a mature municipal landfill. The results show that the SBBGR was able to remove roughly 80% of COD in leachate. The remaining 20% of COD were, therefore, presumably owing to the presence in the leachate of recalcitrant compounds. Ammonia removal efficiency was low because of the presence of high salinity and inhibitory compounds in the investigated leachate. The process was characterised by very low sludge production (lower than 0.02 kg TSS/kg CODremoved).

Claudio Di Iaconi; Guido Del Moro; Michele Pagano; Roberto Ramadori

2009-01-01T23:59:59.000Z

20

Behavior of Engineered Nanoparticles in Landfill Leachate  

Science Journals Connector (OSTI)

This research sought to understand the behavior of engineered nanoparticles in landfill leachate by examining the interactions between nanoparticles and leachate components. The primary foci of this paper are the effects of ZnO, TiO2, and Ag nanoparticles ...

Stephanie C. Bolyard; Debra R. Reinhart; Swadeshmukul Santra

2013-06-25T23:59:59.000Z

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


21

Information Repository  

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

3 Information Repository Documents 3 Information Repository Documents WIPP Annual Waste Minimization Report Transmittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report, dated November 14, 2013 Class 1 Permit Modifications and NMED Responses Class 1 Modification, August 29, 2013 WIPP Hazardous Waste Facility Permit EPA I.D. Number NM4890139088. (1. revise a course outline; 2. revise table and panel figures to include Panel 7; 3. update description related to Type B Packages; and 4. update TRUPACT-II and HalfPACT figures) JE Kieling, NMED dated October 13, 2013 Fee Assessment Class 1 Permit Modification WIPP Hazardous Waste Facility Permit EPA I.D. Number NM4890139088-TSDF (Revise a Course Outline; Revise Table and Panel Figures to Include Panel 7; Update Descriptions Related to Type B Packages; and Update TRUPACT-ll and HalfPACT Figures) JM Kieling, NMED dated September 23, 2013

22

Landfill Leachate Treatment by Reverse Osmosis  

Science Journals Connector (OSTI)

Leachate from landfill sites represents a highly polluted waste water. It containes biodegradable compounds but also inorganic salts and trace recalcitrant pollutants. The reverse osmosis process with or without ...

B. Weber; F. Holz

1991-01-01T23:59:59.000Z

23

Chlorofluorocarbons as tracers of landfill leachate in surface and groundwater  

Science Journals Connector (OSTI)

...considerably lower concentrations in landfill gas. CFCs and CCl4 in leachate may...all groundwater, leachate and landfill gas samples were taken on 6 April 2004...at the central site facility. Landfill gas was sampled by attaching a thick...

A. E. Foley; T. C. Atkinson; Y. Zhao

24

Repository performance confirmation.  

SciTech Connect

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.

Hansen, Francis D.

2011-09-01T23:59:59.000Z

25

Collection  

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

Collection Collection and Analysis of Expressed Sequence Tags Derived from Laser Capture Microdissected Switchgrass (Panicum virgatum L. Alamo) Vascular Tissues Avinash C. Srivastava & Karuppaiah Palanichelvam & Junying Ma & Jarrod Steele & Elison B. Blancaflor & Yuhong Tang # Springer Science+Business Media, LLC. 2010 Abstract Switchgrass is a perennial C4 grass that thrives in a wide range of North American habitats and is an emerging crop for the production of lignocellulosic biofuels. Lignin is an integral component of secondary plant cell walls that provides structural rigidity to the cell wall but it interferes with the conversion of cellulose to fermentable sugars by prevent- ing chemical access to cellulose. Thus, one strategy for improving production of cellulosic ethanol is the down- regulation of lignin in plants. To achieve this goal, it is important

26

Environmental Impacts of Repository  

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

~~"'"""""""""'l.. _ _ 4 Environmental Impacts of Repository Construction, Operation and Monitoring, and Closure 4-iii Environmental Impacts of Repository Construction, Operations, Monitoring, and Closure TABLE OF CONTENTS Section Page 4. Environmental Impacts of Repository Construction, Operations, Monitoring, and Closure ..............4-1 4.1 Preclosure Environmental Impacts of Construction, Operations, Monitoring, and Closure of a Repository ...............................................................................................................................4-3 4.1.1 Impacts to Land Use and Ownership .......................................................................................4-4

27

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

SciTech Connect

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

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

2011-09-15T23:59:59.000Z

28

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

SciTech Connect

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

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

2011-12-31T23:59:59.000Z

29

Leachate treatment system using constructed wetlands, Town of Fenton sanitary landfill, Broome County, New York. Final report  

SciTech Connect

Municipal sanitary landfills generate leachate that New York State regulations require to be collected and treated to avoid contaminating surface water and groundwater. One option for treating leachate is to haul it to municipal wastewater treatment facility. This option may be expensive, may require excessive energy for transportation, and may require pretreatment to protect the receiving facility`s processes. An alternative is on-site treatment and discharge. Personnel from the Town of Fenton, New York; Hawk Engineering, P.C.; Cornell University; and Ithaca College designed, built, and operated a pilot constructed wetland for treating leachate at the Town of Fenton`s municipal landfill. The system, consisting of two overland flow beds and two subsurface flow beds has been effective for 18 months in reducing levels of ammonia (averaging 85% removal by volatilization and denitrification) and total iron (averaging 95% removal by precipitation and sedimentation), two key constituents of the Fenton landfill`s leachate. The system effects these reductions with zero chemical and energy inputs and minimal maintenance. A third key constituent of the leachate, manganese, apparently passes through the beds with minimal removal. Details and wetland considerations are described.

Not Available

1993-11-01T23:59:59.000Z

30

Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2009  

SciTech Connect

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.

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

2010-07-08T23:59:59.000Z

31

Review Paper/ Biogeochemical Evolution of a Landfill Leachate  

E-Print Network (OSTI)

Review Paper/ Biogeochemical Evolution of a Landfill Leachate Plume, Norman, Oklahoma by I Abstract Leachate from municipal landfills can create groundwater contaminant plumes that may last in the configuration of redox zones downgradient from the Norman Landfill were studied for more than a decade

32

E-Print Network 3.0 - analyze repository capacity Sample Search...  

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

features of Yucca Moun- tain led to its selection as a potential repository site: Yucca Mountain now Source: U.S. Nuclear Waste Technical Review Board Collection: Fission...

33

Study of colloidal content and associated heavy metals in landfill leachate: a case study of El-Akader landfill site: Jordan  

Science Journals Connector (OSTI)

Landfill leachate samples were collected anaerobically at six locations at the El-Akader landfill site in North Jordan. The collected leachate samples were separated into size fractions with special attention to the distribution of colloids and associated heavy metals. The fraction sizes were 1.2 µm. The maximum concentrations of heavy metals in the analysed leachate samples were Cd 0.6 µg/l, Ni 25 µg/l, Zn 245 µg/l, Cu 15 µg/l and Pb 2.50 µg/l. In the dissolved particular matter the heavy metals concentration ranges were Cd 0.1â??1.1 µg/l, Ni 0.35â??1.5 µg/l, Zn 85â??105 µg/l, Cu 0â??0.95 µg/l and Pb 0.5â??2.5 µg/l.

Y. Abu-Rukah

2005-01-01T23:59:59.000Z

34

Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2008  

SciTech Connect

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

R. L. Weiss; D. W. Woolery

2009-09-03T23:59:59.000Z

35

Open OntologyOpen Ontology Repository:Repository  

E-Print Network (OSTI)

Nonfunctional requirements Use case descriptionsUse case descriptions Wiki page:Wiki page: http://ontolog.cim3.net/cgihttp://ontolog.cim11 Open OntologyOpen Ontology Repository:Repository: Architecture andArchitecture and Interfaces3.net/cgi-- bin/wiki.pl?OpenOntologyRepository_Requirementbin/wiki.pl?OpenOntology

Baclawski, Kenneth B.

36

Ion chromatographic analysis of oil shale leachates  

SciTech Connect

In the present work an investigation of the use of ion chromatography to determine environmentally significant anions present in oil shale leachates was undertaken. Nadkarni et al. have used ion chromatography to separate and quantify halogen, sulfur and nitrogen species in oil shales after combustion in a Parr bomb. Potts and Potas used ion chromatography to monitor inorganic ions in cooling tower wastewater from coal gasification. Wallace and coworkers have used ion chromatography to determine anions encountered in retort wastewaters. The ions of interest in this work were the ions of sulfur oxides including sulfite (SO{sub 3}{sup 2{minus}}), sulfate (SO{sub 4}{sup 2{minus}}), thiosulfate (S{sub 2}O{sub 3}{sup 2{minus}}), dithionite (S{sub 2}O{sub 4}{sup 2{minus}}), dithionate (S{sub 2}O{sub 6}{sup 2{minus}}), peroxyodisulfate (S{sub 2}O{sub 8}{sup 2{minus}}), and tetrathionate (S{sub 4}O{sub 6}{sup 2{minus}}), and thiocyanate (SCN{sup {minus}}), sulfide (S{sup 2{minus}}) hydrosulfide (HS{sup {minus}}), cyanide (CN{sup {minus}}), thiocyanate (SCN{sup {minus}}), and cyanate (OCN{sup {minus}}). A literature search was completed and a leaching procedure developed. 15 refs., 6 figs., 1 tab.

Butler, N.L.

1990-10-01T23:59:59.000Z

37

MONTICELLO NPL SITES  

Office of Legacy Management (LM)

MONTICELLO NPL SITES MONTICELLO NPL SITES FFA QUARTERLY REPORT: October 1 - December 31, 2007 DOE Site Manager: Jalena Maestas 1.0 MMTS Activities/Status Repository and Pond 4 * Monthly and quarterly inspection of the repository identified no problems that have not been addressed. (inspection checklists attached). * Monthly inspection of Pond 4 identified no unacceptable conditions. * Pond 4 leachate detection and removal systems continue to operate at normal levels (leachate pumping summary attached). * Repository leachate collection and removal system (LCRS) and leachate collection system (LDS) continue to operate at normal and acceptable levels (leachate pumping summary attached). * Portions of repository cover were planted with rabbitbrush seedlings to repair areas

38

Mutagenicity and genotoxicity of coal fly ash water leachate  

SciTech Connect

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.

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

2009-03-15T23:59:59.000Z

39

Selection of a method for disposing of leachate grout  

SciTech Connect

A major component of the selected remedy for the remediation of the Maxey Flats Disposal Site (MFDS) is the removal, solidification, and on-site disposal of an estimated 3000000 gal of trench leachate. The Record of Decision (ROD) and its predecessor, the Maxey Flats Feasibility Study Report, proposed as a representative process option that the trench leachate be solidified in the form of large (8 x 8 x 4 ft) concrete blocks and disposed of in trenches. The U.S. Environmental Protection Agency (EPA) had recent experience with this method when solidifying and disposing of {approximately}300000 gal of leachate that was stored in above-ground tanks at the MFDS. The EPA experience proved the capability of a U.S. Nuclear Regulatory Commission (NRC)-approved grout mix to satisfy the requirements of 10CFR61.55-56 for the Class-A liquid waste at the site, i.e., the leachate. However, a technical evaluation of the overall solidification/disposal process implemented by the EPA identified some steps that should be improved if this method is to be implemented safely and efficiently for the solidification and disposal of trench leachate as part of the remedial action. In the light of the EPA experience, the present study modified the option proposed in the ROD to make it more workable. This study also evaluated other methods, including three methods for above grade disposal.

Cockrell, R.G.

1994-12-31T23:59:59.000Z

40

Some chemical and mineralogical considerations important for understanding leachate chemistry  

SciTech Connect

Both the raw shale material and the retorting process parameters are influential in determining the subsequent behavior of the spent shale solids with respect to leaching and/or environmental weathering. The process parameters define the mineral reactions that occur to form the mineral assemblage in the spent shale, while the major and trace element residences and mobilities from the raw shale determine the extent of incorporation of these elements in the spent shale matrix and ultimately the composition of leachate generated by the spent shale solid: water interaction. In order to understand leachate compositions, it is necessary to determine this water: solid interaction, but the solid wastes being considered are a dependent function of the raw shale material and the process parameters. Thus, in order to understand the chemical principles operative in leachate generation, it is necessary to elucidate the interplay of the raw material and the process parameters in the formation of the waste and then the interaction of the waste form with water. The leachate and the solid waste are dependent variables, while the raw shale and the process parameters are independent variables. These considerations are illustrated by results of chemical characterization and experimental studies of field generated spent shales. Results from field generated materials are used to describe important considerations relative to the understanding of leachate chemistry.

Peterson, E.J.; Wagner, P.

1982-01-01T23:59:59.000Z

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


41

E-Print Network 3.0 - ash dump leachate Sample Search Results  

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

Volume 28, no. 1, Jan.-Feb. 1999.Copyright0 1999,ASA, CSSA, SSSA Summary: ). Leachate Analysis PH The pH values for all leachates from the ash- and sludge-amended soil columns...

42

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

E-Print Network (OSTI)

Subsurface characterization of groundwater contaminated by landfill leachate using microbial from groundwater monitoring wells located within and around an aquifer contaminated with landfill. In this landfill leachate application, the weighted SOM assembles the microbial community data from monitoring

Vermont, University of

43

Repository seals requirement study  

SciTech Connect

The Yucca Mountain Site Characterization Project, managed by the Civilian Radioactive Waste Management System (CRWMS) Management and Operating Contractor (M and O) is conducting investigations to support the Viability Assessment and the License Application for a high-level nuclear waste repository at Yucca Mountain, Nevada. The sealing subsystem is part of the Yucca Mountain Waste Isolation System. The Yucca Mountain Site Characterization Project is currently evaluating the role of the sealing subsystem (shaft, ramp and exploratory borehole seals) in achieving the overall performance objectives for the Waste Isolation System. This report documents the results of those evaluations. The objective of the study is to provide water or air flow performance based requirements for shafts, ramps, and exploratory boreholes located near the repository. Recommendations, as appropriate, are provided for developing plans, seals component testing, and other studies relating to sealing.

NONE

1997-11-03T23:59:59.000Z

44

Anaerobic Methane Oxidation in a Landfill-Leachate Plume  

E-Print Network (OSTI)

wells ranging in depth from 1.3 to 11 m that were oriented parallel to the flow path. The center of the leachate plume was characterized by (1) high alkalinity and elevated concentrations of total dissolved organic carbon, reduced iron, and methane...

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

2002-01-01T23:59:59.000Z

45

Characterization of plutonium in Maxey Flats radioactive trench leachates  

SciTech Connect

Plutonium in trench leachates at the Maxey Flats radioactive waste disposal site exists as dissolved species, primarily complexes of the tetravalent ion with strong organic ligands such as ethylenediaminetetraacetic acid. The complexes are not sorbed well by sediment and are only partly precipitated by ferric hydroxide. These results indicate the importance of isolating radioactive waste from organic matter. 3 tables.

Cleveland, J.M.; Rees, T.F.

1981-06-26T23:59:59.000Z

46

Anaerobic Methane Oxidation in a Landfill-Leachate Plume  

E-Print Network (OSTI)

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 Landfill, OK, provides an excellent natural laboratory for the study of anaerobicprocessesimpactinglandfill enrichment indicated that 80-90% of the original landfill methane was oxidized over the 210-m transect. First

Grossman, Ethan L.

47

MONTICELLO NPL SITES FFA QUARTERLY REPORT: October 1  

Office of Legacy Management (LM)

October 1 October 1 - December 31,2006 DOE Project Coordinator: Art KJeinrath 1.0 MMTS Activities Repository and Pond 4 * Monthly and quarterly inspection of the repository identified no problems other than shmb damage by voles (inspection checklists attached) * Monthly inspection ofPond 4 identified no unacceptable conditions. * Pond 4 leachate detection and removal systems operated at normal levels (leachate pumping summary attached). * Repository leachate collection and removal system (LCRS) and leachate collection system (LOS) operated at normal levels (leachate pumping summary attached). Former Millsite * As a follow-up to the 2004 audit, DOE inspector general requested information regarding restoration expenditures by DOE. * No other major activity to report

48

Growth and biomass of Populus irrigated with landfill leachate  

Science Journals Connector (OSTI)

Resource managers are challenged with waste disposal and leachate produced from its degradation. Poplar (Populus spp.) trees offer an opportunity for ecological leachate disposal as an irrigation source for managed tree systems. Our objective was to irrigate Populus trees with municipal solid waste landfill leachate or fertilized well water (control) (N, P, K) during the 2005 and 2006 growing seasons and test for differences in tree height, diameter, volume, and biomass of leaves, stems, branches, and roots. The trees were grown at the Oneida County Landfill located 6 km west of Rhinelander, Wisconsin, USA (45.6°N, 89.4°W). Eight clones belonging to four genomic groups were tested: NC13460, NC14018 [(Populus trichocarpa Torr. & Gray × Populus deltoides Bartr. ex Marsh) × P. deltoides ‘BC1’]; NC14104, NC14106, DM115 (P. deltoides × Populus maximowiczii A. Henry ‘DM’); DN5 (P. deltoides × Populus nigra L. ‘DN’); NM2, NM6 (P. nigra × P. maximowiczii ‘NM’). The survival rate for each of the irrigation treatments was 78%. The total aboveground biomass ranged from 0.51 to 2.50 Mg ha?1, with a mean of 1.57 Mg ha?1. The treatment × clone interaction was not significant for tree diameter, total volume, dry mass of the stump or basal roots, or root mass fraction (P > 0.05). However, the treatment × clone interaction was significant for height, total tree dry mass, aboveground dry mass, belowground dry mass, and dry mass of the leaves, stems + branches (woody), and lateral roots (P < 0.05). There was broad clonal variation within the BC1 and DM genomic groups, with genotypes performing differently for treatments. In contrast, the performance of the NM and DN genomic groups was relatively stable across treatments, with clonal response to irrigation being similar regardless of treatment. Nevertheless, selection at the clone level also was important. For example, NC14104 consistently performed better when irrigated with leachate compared with water, while NC14018 responded better to water than leachate. Overall, these data will serve as a basis for researchers and resource managers making decisions about future leachate remediation projects.

Jill A. Zalesny; Ronald S. Zalesny Jr.; David R. Coyle; Richard B. Hall

2007-01-01T23:59:59.000Z

49

Examining Repository Loading Options to Expand Yucca Mountain Repository Capacity  

SciTech Connect

Siting a high level nuclear waste repository entails high economic, social, and political costs. Given the difficulty in siting the Yucca Mountain repository and the already identified need for additional capacity, the concept of expanding the capacity of the Yucca Mountain repository is of significant interest to the nuclear industry and the Department of Energy (DOE). As the capacity of the repository is limited by the decay heat inventory of the spent nuclear fuel in relation to the thermal design limits, expanding the capacity requires appropriate schemes for decay heat and spent fuel loading management. The current Yucca Mountain repository is based on a single level, fixed drift spacing design for a fixed area or footprint. Studies performed to date investigating the capacity of Yucca Mountain often assume that the loading of spent fuel is uniform throughout the repository and use the concept of a linear loading or areal power density (APD). However, use of linear loading or APD can be problematic with the various cooling times involved. The temperature within the repository at any point in time is controlled by the integral of the heat deposited in the repository. The integral of the decay heat varies as a function of pre-loading cooling periods even for a fixed linear loading. A meaningful repository capacity analysis requires the use of a computer model that describes the time-dependent temperature distributions of the rock from the dissipation of the heat through the repository system. If variations from the current Yucca Mountain repository design were to be considered, expanding the capacity of the repository would be pursued in several ways including: (1) increase the footprint size; (2) implement multiple-levels in the repository for the given footprint; (3) allow the drift distance to vary within thermal limits; and, (4) allow non-uniform loading of wastes into the drifts within thermal limits. Options (1) and (2) have been investigated by other researchers. This paper investigates options (3) and (4) for possible expansion of the Yucca Mountain repository capacity. To support the work, a thermal analysis model was needed to describe the temperature changes in the rock around the waste packages against the thermal design limits as a function of spent fuel characteristics and composition. Under the high temperature operating mode (HTOM), the relevant thermal design limits are: (1) the rock temperature midway between adjacent drifts must remain below the local boiling point (96 deg. C); and (2) the rock temperature at drift walls must remain below 200 deg. C. As the work involves a large number of calculations, examining the compliance within thermal design limits, the capability to perform efficient mountain-scale heat-transfer analyses was necessary. A related topic of importance in this investigation was also the effect of uncertainty. As the modeling exercise relies on the use of computational models, uncertainties are unavoidable and understanding the uncertainty in the interpretation of the results is important. The concept of variable drift spacing and variable drift thermal loading was investigated with respect to possible capacity expansion of the Yucca Mountain repository. Also, a computer model was developed for efficient repository heat transfer calculations and sensitivity and uncertainty analyses were performed to identify key parameters and to estimate the uncertainty in the results and understand how the repository capacity estimation would be affected by the uncertainty. (authors)

Li, Jun; Nicholson, Mark; Proctor, W. Cyrus; Yim, Man-Sung; McNelis, David [Department of Nuclear Engineering, North Carolina State University (United States)

2007-07-01T23:59:59.000Z

50

Chemical, Electrochemical and Spectral Characterization of Water Leachates from Biomass  

Science Journals Connector (OSTI)

(10) During washing, a fraction of organic compounds and inorganic ions enter the water. ... After being allowed to air dry in the field, all samples were cut with a herb shredder and then sieved to 280–450 ?m. ... The light gray column represents the calculated value of the weight of K removed from a 12.5-g biomass sample, and the gray column represents the measured value of K in 1.0 L of leachate. ...

Lei Deng; Defu Che

2012-11-08T23:59:59.000Z

51

NREL's Field Data Repository Supports Accurate Home Energy Analysis (Fact Sheet), Building America: Technical Highlight, Building Technologies Program (BTP)  

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

Field Data Field Data Repository Supports Accurate Home Energy Analysis The Residential Buildings Research Group at the National Renewable Energy Laboratory (NREL) has developed 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 Field Data Repository currently includes data collected from historical programs where residential building characteristics (building geometry, insulation levels, equipment types, etc.), generally collected through energy audits, have been connected to measured energy use. With an emphasis on older homes, the repository contains datasets from Home Energy Rating System

52

Brine Migration Experimental Studies for Salt Repositories | Department of  

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

Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Experiments were used to examine water content in Permian salt samples (Salado Formation) collected from the WIPP site. The profile of water release and movement is recognized as a function of temperature from 30 to 275 oC using classical gravimetric methods to measure weight loss as a result of heating. The amount of water released from heating the salt was found to be correlated with the salts accessory mineral content (clay, other secondary minerals lost up to 3 wt % while pure halite salt lost less than 0.5 wt % water). Water released from salt at lower temperature was reversible and is attributed to clay hydration and dehydration processes. The analysis

53

Brine Migration Experimental Studies for Salt Repositories | Department of  

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

Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Experiments were used to examine water content in Permian salt samples (Salado Formation) collected from the WIPP site. The profile of water release and movement is recognized as a function of temperature from 30 to 275 oC using classical gravimetric methods to measure weight loss as a result of heating. The amount of water released from heating the salt was found to be correlated with the salts accessory mineral content (clay, other secondary minerals lost up to 3 wt % while pure halite salt lost less than 0.5 wt % water). Water released from salt at lower temperature was reversible and is attributed to clay hydration and dehydration processes. The analysis

54

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

E-Print Network (OSTI)

fractions of leachates, a cascade filtration protocol was applied directly in the field, under a nitrogen gas atmosphere to avoid metal oxidation. The results of analyses performed on the leachates suggest mobility and natural attenuation in a context of landfill risk assessment are discussed. hal-00605888

Paris-Sud XI, Université de

55

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 20­30% due to the low biodegradability of organic matter in the leach- ate from old landfills

56

Monitoring of Landfill Leachate Dispersion Using Reflectance Spectroscopy and Ground-Penetrating Radar  

Science Journals Connector (OSTI)

Monitoring of Landfill Leachate Dispersion Using Reflectance Spectroscopy and Ground-Penetrating Radar ... The generation and dispersion of leachate from landfills are slow, unsteady, nonuniform, and sometimes discontinuous depending on the degree of compaction of the fill, seasonal changes in the water supply to the system, and changes in the capping and contaminant walls (2). ...

T. Splajt; G. Ferrier; L. E. Frostick

2003-08-12T23:59:59.000Z

57

Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2010  

SciTech Connect

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.

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

2011-06-09T23:59:59.000Z

58

Geochemistry of trench leachates at low-level radioactive waste burial sites  

SciTech Connect

Trench leachates from the low-level radioactive waste burial sites at Maxey Flats, Kentucky and Barnwell, South Carolina were sampled and analyzed for dissolved inorganic, organic, and radionuclide constituents. Relative to local groundwaters, the trench leachates exhibit significant modifications in major ion and radionuclide compositions. The formation and composition of the leachates can be attributed to site-specific hydrological and geochemical factors. Leaching and microbial degradation of waste materials are considered to be the important geochemical processes controlling the leachate compositions. Elevated concentrations of Na, K, Ca, Mg, Cl, dissolved organic and inorganic carbon, and various anthropogenic radionuclides reflect leaching of waste materials. Anoxic conditions as characterized by depletion of dissolved oxygen and sulphate, and high contents of alkalinity and ammonia reflect microbial decomposition of organic waste materials. Because of relatively stagnant water accumulations, the extent of modification is much greater in the Maxey Flats leachates as compared with those from Barnwell. 8 references, 2 figures, 2 tables.

Dayal, R.; Pietrzak, R.F.; Clinton, J.

1984-01-01T23:59:59.000Z

59

Removal of organic and inorganic compounds from landfill leachate using reverse osmosis  

Science Journals Connector (OSTI)

The main objective of this work was to evaluate an effectiveness of removing organic and inorganic pollutants from landfill leachate in a long-term reverse osmosis (RO) study. Investigations were carried out...4 ...

I. A. Talalaj

2014-08-01T23:59:59.000Z

60

Overburden effects on waste compaction and leachate generation in municipal landfills  

E-Print Network (OSTI)

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

Mehevec, Adam Wade

2012-06-07T23:59:59.000Z

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


61

REPOSITORY ENGINEERED BARRIER SYSTEM DESIGN  

SciTech Connect

A Viability Assessment (VA) for the Yucca Mountain Project is being completed for delivery in September of 1998. A major element of the VA is the design of a high level waste repository on the Nevada Test Site. The repository is made up of surface and subsurface facilities. The engineered barrier includes the man-made elements of the system that act to retard the migration of radionuclides from a geologic repository. They act in conjunction with the geologic barriers present at Yucca Mountain. The engineered barrier system (EBS) consists of the Waste Package and the underground facility. The focus of this paper is the status of the design of the underground facility portion of the EBS. In addition to a robust waste package, the EBS components in the reference design include a number of features that impede naturally occurring infiltration from reaching and corroding the waste packages. In addition, and as a defense-in-depth strategy, a number of other optional features are being considered. They include drip shields above the waste packages to intercept dripping water and granular backfill around the waste packages to form a diffusion barrier. Plans are being made to test a number of the EBS materials and structures. The Viability Assessment document will discuss the various EBS options and alternative designs and lay out a plan for determining those to be included in the License Application to the Nuclear Regulatory Commission (NRC) scheduled for completion in 2002.

DANIEL G. MCKENZIE III PE, DR. KALYAN K. BHATTACHARYYA AND PAUL G. HARRINGTON

1998-07-29T23:59:59.000Z

62

TITLE  

Office of Legacy Management (LM)

. . · MONTICELLO NPL SITES FFA QUARTERLY REPORT: January 1- March 31, 2007 DOE Site Manager: Jalena Maestas 1.0 MMTS Activities/Status Repository and Pond 4 * Monthly and quarterly inspection of the repository identified no problems other than shrub damage by voles (inspection checklists attached). * Monthly inspection of Pond 4 identified no unacceptable conditions. * Pond 4 leachate detection and removal systems operated at normal levels (leachate pumping summary attached). * Repository leachate collection and removal system (LCRS) and leachate collection system (LDS) operated at normal levels (leachate pumping summary attached). * Equipment purchased to upgrade repository LCRS and LDS remote sensing and telemetry system. * Portions of repository cover were manually re-seeded with desirable shrubs to repair areas

63

Energy Systems Laboratory: Building a Model Repository Collection  

E-Print Network (OSTI)

approximately 120 staff members, including mechanical engineers, computer science graduates, lab technicians, support staff, and graduate and undergraduate students. The Lab focuses on energy-related research, energy efficiency, and emissions reduction, and has...

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

2008-06-05T23:59:59.000Z

64

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

SciTech Connect

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.

Valentine, G.A.

1996-09-01T23:59:59.000Z

65

Nitrogen management in landfill leachate: Application of SHARON, ANAMMOX and combined SHARON-ANAMMOX process  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer Significant research on ammonia removal from leachate by SHARON and ANAMMOX process. Black-Right-Pointing-Pointer Operational parameters, microbiology, biochemistry and application of the process. Black-Right-Pointing-Pointer SHARON-ANAMMOX process for leachate a new research and this paper gives wide facts. Black-Right-Pointing-Pointer Cost-effective process, alternative to existing technologies for leachate treatment. Black-Right-Pointing-Pointer Address the issues and operational conditions for application in leachate treatment. - Abstract: In today's context of waste management, landfilling of Municipal Solid Waste (MSW) is considered to be one of the standard practices worldwide. Leachate generated from municipal landfills has become a great threat to the surroundings as it contains high concentration of organics, ammonia and other toxic pollutants. Emphasis has to be placed on the removal of ammonia nitrogen in particular, derived from the nitrogen content of the MSW and it is a long term pollution problem in landfills which determines when the landfill can be considered stable. Several biological processes are available for the removal of ammonia but novel processes such as the Single Reactor System for High Activity Ammonia Removal over Nitrite (SHARON) and Anaerobic Ammonium Oxidation (ANAMMOX) process have great potential and several advantages over conventional processes. The combined SHARON-ANAMMOX process for municipal landfill leachate treatment is a new, innovative and significant approach that requires more research to identify and solve critical issues. This review addresses the operational parameters, microbiology, biochemistry and application of both the processes to remove ammonia from leachate.

Sri Shalini, S., E-mail: srishalini10@gmail.com [Centre for Environmental Studies, Anna University, Chennai (India); Joseph, Kurian, E-mail: kuttiani@gmail.com [Centre for Environmental Studies, Anna University, Chennai (India)

2012-12-15T23:59:59.000Z

66

Assessment of metal content and toxicity of leachates from teapots  

Science Journals Connector (OSTI)

Metallic teapots traditionally used in Morocco were investigated for release of toxic metals from the teapots and their toxicity, as determined by MetPAD, a bacterial toxicity test that is specific for heavy metal toxicity. Our data show that some teapots were non-toxic while a few others were highly toxic, as shown by MetPAD. Tea addition reduced somewhat heavy metal toxicity due possibly to the complexing ability of tea. Chemical analysis of teapot leachates showed that some contained zinc and copper. Teapot No. 5, which showed the highest toxicity, also displayed the highest Zn concentration (7.39 mg/l), confirming the toxicity data. Based on estimates of tea consumption in Morocco, we showed that the extra daily burden of Zn ranged from 1.75 to 4.2 mg/day, assuming the maximum zinc concentration of 7.4 mg/l, as found in our study. This represents 3.5–8% of the LOAEL for zinc of 50 mg/day and would not be important as compared to other sources of zinc intake.

Ali Boularbah; Gabriel Bitton; J.L Morel

1999-01-01T23:59:59.000Z

67

Toxicity of tire wear particle leachate to the marine macroalga, Ulva lactuca  

Science Journals Connector (OSTI)

Tire wear particles filed from the treads of end-of-life vehicle tires have been added to sea water to examine the release of Zn and the toxicity of the resulting leachate and dilutions thereof to the marine macroalga, Ulva lactuca. Zinc release appeared to be diffusion-controlled, with a conditional rate constant of 5.4 ?g[L(h)1/2]?1, and about 1.6% of total Zn was released after 120 h incubation. Exposure to increasing concentrations of leachate resulted in a non-linear reduction in the efficiency of photochemical energy conversion of U. lactuca and, with the exception of the undiluted leachate, increasing accumulation of Zn. Phototoxicity was significantly lower on exposure to equivalent concentrations of Zn added as Zn(NO3)2, suggesting that organic components of leachate are largely responsible for the overall toxicity to the alga. Given the ubiquity and abundance of TWP in urban coastal sediments, the generation, biogeochemistry and toxicity of tire leachate in the marine setting merit further attention.

Andrew Turner; Lynsey Rice

2010-01-01T23:59:59.000Z

68

Konrad Repository Facing its Construction  

SciTech Connect

According to the German Atomic Energy Act the Federation is responsible for the construction and operation of installations for the safekeeping and disposal of radioactive waste. This duty was assigned to the Federal Office for Radiation Protection (Bundesamt fuer Strahlenschutz - BfS). In 1982, the Federal Institute of Physics and Metrology (Physikalisch Technische Bundesanstalt - PTB) as the precursor of BfS applied for a license for the disposal of radioactive waste with negligible heat generation in the Konrad iron ore mine near Salzgitter at the Ministry for Environment of Lower Saxony. After 25 years of plan approval procedure and subsequent lawsuits the license is now valid and Konrad is waiting for construction. Facing this challenge BfS has established a project team to supervise the in-house and external activities to be done. It is intended to construct the Konrad repository within a preparation period of two years and a subsequent erection phase of four years. Thus, Konrad is planned to come into operation in 2013. In this paper the development of the plan approval procedure, the technical design of the planned repository, especially with regard to safety-related aspects, and the planning for the construction will be discussed. (authors)

Kunze, V. [Bundesamt fur Strahlenschutz (BfS), Salzgitter (Germany)

2008-07-01T23:59:59.000Z

69

Chemical pollution and toxicity of water samples from stream receiving leachate from controlled municipal solid waste (MSW) landfill  

Science Journals Connector (OSTI)

Abstract The present study was aimed to determine the impact of municipal waste landfill on the pollution level of surface waters, and to investigate whether the choice and number of physical and chemical parameters monitored are sufficient for determining the actual risk related to bioavailability and mobility of contaminants. In 2007–2012, water samples were collected from the stream flowing through the site at two sampling locations, i.e. before the stream?s entry to the landfill, and at the stream outlet from the landfill. The impact of leachate on the quality of stream water was observed in all samples. In 2007–2010, high values of TOC and conductivity in samples collected down the stream from the landfill were observed; the toxicity of these samples was much greater than that of samples collected up the stream from the landfill. In 2010–2012, a significant decrease of conductivity and TOC was observed, which may be related to the modernization of the landfill. Three tests were used to evaluate the toxicity of sampled water. As a novelty the application of Phytotoxkit F™ for determining water toxicity should be considered. Microtox® showed the lowest sensitivity of evaluating the toxicity of water samples, while Phytotoxkit F™ showed the highest. High mortality rates of Thamnocephalus platyurus in Thamnotoxkit F™ test can be caused by high conductivity, high concentration of TOC or the presence of compounds which are not accounted for in the water quality monitoring program.

A. Melnyk; K. Kukli?ska; L. Wolska; J. Namie?nik

2014-01-01T23:59:59.000Z

70

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

SciTech Connect

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.

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

1983-04-01T23:59:59.000Z

71

Polycyclic aromatic hydrocarbons (PAH) in top soil, leachate and groundwater from Ruseifa solid waste landfill, Jordan  

Science Journals Connector (OSTI)

The distribution profiles and pathways of polynuclear aromatic hydrocarbons in the surroundings of Ruseifa landfill area in Jordan were investigated for surface sediments, leachate, and groundwater. The total concentration of 16 polycyclic aromatic hydrocarbons (PAHs) in sediments ranged from 286 to 1704 ppm with an average value of 751 ppm. Meanwhile, concentrations of PAH in groundwater ranged between 7.1 and 12.6 ppm with an average value of 9.1 ppm. The PAH in leachate varied between 0.10 and 0.40 with an average value of 0.29 ppm. The overall PAH distribution profiles appeared to be similar for leachate and groundwater dominated by 2â??3 rings system molecules. While, the sediments profile was dominated by 4â??6 rings system molecules which indicated the loss of low molecular weight compounds of PAH and accumulation of higher molecular weight of PAH under prevailing semiarid and hot climatic conditions.

Anwar Jiries; Omar Rimawi; Jutta Lintelmann; Mufeed Batarseh

2005-01-01T23:59:59.000Z

72

The landfill leachate evapotranspiration in soilâ??plant system with reed Phragmites australis  

Science Journals Connector (OSTI)

Using of the reed – Phragmites australis – is an effective method of landfill leachate disposal. In presented two years' study the effectiveness of leachate evapotranspiration from systems with reed was investigated. Daily evapotranspiration was in the range from 1.01 mm/d to 3.15 mm/d in the first year of research and from 2.68 mm/d to 4.94 mm/d in the second year. The research showed that the application of sewage sludge into the soil caused the increase in the vapourisation efficiency. Preliminary results of implemented soil-plant system with reed on landfill in Zakurzewo, Poland, showed that about 1100 mł of leachate were evapotranspirated.

Andrzej Bialowiec; Irena Wojnowska-Baryla

2008-01-01T23:59:59.000Z

73

DSpace: An Open Source Dynamic Digital Repository  

E-Print Network (OSTI)

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

Smith, MacKenzie

74

Optimisation of sanitary landfill leachate treatment in a sequencing batch reactor  

E-Print Network (OSTI)

on artificial intelligence concepts. Nitrogen removal was optimized via the nitrite shortcut. Nitrification and N removal were usually higher than 98% and 90%, respectively, whereas COD (of the leachate) removal, in terms of phase length and external COD addition, to the varying loading conditions. Using the control

75

Monitored Geologic Repository Test Evaluation Plan  

SciTech Connect

The Monitored Geologic Repository test & evaluation program will specify tests, demonstrations, examinations, and analyses, and describe procedures to conduct and document testing necessary to verify meeting Monitored Geologic Repository requirements for a safe and effective geologic repository for radioactive waste. This test program will provide assurance that the repository is performing as designed, and that the barriers perform as expected; it will also develop supporting documentation to support the licensing process and to demonstrate compliance with codes, standards, and regulations. This comprehensive program addresses all aspects of verification from the development of test requirements to the performance of tests and reporting of the test results. The ''Monitored Geologic Repository Test & Evaluation Plan'' provides a detailed description of the test program approach necessary to achieve the above test program objectives. This test plan incorporates a set of test phases focused on ensuring repository safety and operational readiness and implements a project-wide integrated product management team approach to facilitate test program planning, analysis, and implementation. The following sections provide a description of the individual test phases, the methodology for test program planning and analyses, and the management approach for implementing these activities.

M.B. Skorska

2002-01-02T23:59:59.000Z

76

MONITORED GEOLOGIC REPOSITORY SYSTEMS REQUIREMENTS DOCUMENT  

SciTech Connect

This document establishes the Monitored Geologic Repository system requirements for the U.S. Department of Energy's (DOE's) Civilian Radioactive Waste Management System (CRWMS). These requirements are based on the ''Civilian Radioactive Waste Management System Requirements Document'' (CRD) (DOE 2004a). The ''Monitored Geologic Repository Systems Requirements Document'' (MGR-RD) is developed in accordance with LP-3.3 SQ-OCRWM, ''Preparation, Review, and Approval of Office of Repository Development Requirements Document''. As illustrated in Figure 1, the MGR-RD forms part of the DOE Office of Civilian Radioactive Waste Management Technical Requirements Baseline. Revision 0 of this document identifies requirements for the current phase of repository design that is focused on developing a preliminary design for the repository and will be included in the license application submitted to the U.S. Nuclear Regulatory Commission for a repository at Yucca Mountain in support of receiving a construction authorization and subsequent operating license. As additional information becomes available, more detailed requirements will be identified in subsequent revisions to this document.

V. Trebules

2006-06-02T23:59:59.000Z

77

A critique of the Department of Energy's environmental programme for the proposed high-level nuclear waste repository at Yucca Mountain, Nevada, USA  

Science Journals Connector (OSTI)

Legislative standards, regulatory provisions, and US Department of Energy (DOE) policies have defined the environmental programme to study the planned high-level nuclear waste repository site at Yucca Mountain, Nevada. The DOE has limited environmental data collection for purposes of monitoring and mitigating impacts of proposed characterisation activities and repository development. Most of the plans are procedural and do not provide for the gathering of baseline data prior to site characterisation activities. The absence of baseline data prior to site characterisation activities reduces the chances of developing a comprehensive and integrated environmental programme to detect and remedy disturbed areas critical to the performance of the repository as well as to assess repository performance properly. The lack of long-term ecological studies means also that interactions between the geohydrologic setting of the repository and the biosphere will not be understood fully.

J. Lemons; D. J. Schaeffer; E. Saboski

1992-01-01T23:59:59.000Z

78

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

SciTech Connect

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.

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

2013-07-01T23:59:59.000Z

79

How does landfill leachate affect the chemical processes in a lake system downgradient from a landfill site?  

Science Journals Connector (OSTI)

A field study on the geochemical properties of a chemically-stressed limnic environment was performed in Lake Silbersee, which receives leachate water of high inorganic loading from an upgradient landfill site. T...

Thomas Striebel; Wolfgang Schäfer; Stefan Peiffer

1991-01-01T23:59:59.000Z

80

Hydrogeological studies on the mechanical behavior of landfill gases and leachate of the Nanjido Landfill in Seoul, Korea  

Science Journals Connector (OSTI)

?The Nanjido Landfill is the largest uncontrolled landfill in Korea and it causes various kinds of environmental problems. Landfill gases and leachate are recognized as the most serious environmental problems ass...

K. K. Lee; Y. Y. Kim; H. W. Chang; S. Y. Chung

1997-06-01T23:59:59.000Z

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


81

EIDR :: Experimental Information and Data Repository  

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

EIDR :: Experimental Information and Data Repository EIDR :: Experimental Information and Data Repository QUICK LINKS: About EIDR | EIDR FAQS | VIEW gene expression data | VIEW phenotype microarray data > Browse data by ... mouse over the below to display the menus experimental condition organism organism, experimental condition organism, type of laboratory analyses type of laboratory analyses Status of data import 2007-02-10 EIDR Overview EIDR is an information database for the ESPP project. It contains information about data generated by project participants, as well as links to data stored either in Biofiles or in the Experimental Data Repository. EIDR references data files that have been uploaded to LBNL using Biofiles, custom Web interfaces, or ftp. Information about the data includes design information about biomass production experiments, information about the lab analyses that generated the data, and links to more detailed information, displays, or analyses. You can browse for data using the menus in the Browse data by ... table to the left.

82

License for the Konrad Deep Geological Repository  

SciTech Connect

Deep geological disposal of long-lived radioactive waste is currently considered a major challenge. Until present, only three deep geological disposal facilities have worldwide been operated: the Asse experimental repository (1967-1978) and the Morsleben repository (1971-1998) in Germany as well as the Waste Isolation Pilot Plant (WIPP) in the USA (1999 to present). Recently, the licensing procedure for the fourth such facility, the German Konrad repository, ended with a positive ''Planfeststellung'' (plan approval). With its plan approval decision, the licensing authority, the Ministry of the Environment of the state of Lower Saxony, approved the single license needed pursuant to German law to construct, operate, and later close down this facility.

Biurrun, E.; Hartje, B.

2003-02-24T23:59:59.000Z

83

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

Energy Savers (EERE)

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...

84

Reference Design Description for a Geologic Repository  

SciTech Connect

One of the current major national environmental problems is the safe disposal of large quantities of spent nuclear fuel and high-level radioactive waste materials, which are rapidly accumulating throughout the country. These radioactive byproducts are generated as the result of national defense activities and from the generation of electricity by commercial nuclear power plants. At present, spent nuclear fuel is accumulating at over 70 power plant sites distributed throughout 33 states. The safe disposal of these high-level radioactive materials at a central disposal facility is a high national priority. This Reference Design Description explains the current design for a potential geologic repository that may be located at Yucca Mountain in Nevada for the disposal of spent nuclear fuel and high-level radioactive waste materials. This document describes a possible design for the three fundamental parts of a repository: a surface facility, subsurface repository, and waste packaging. It also presents the current conceptual design of the key engineering systems for the final four phases of repository processes: operations, monitoring, closure, and postclosure. In accordance with current law, this design does not include an interim storage option. In addition, this Reference Design Description reviews the expected long-term performance of the potential repository. It describes the natural barrier system which, together with the engineered systems, achieves the repository objectives. This design will protect the public and the environment by allowing the safe disposal of radioactive waste received from government-owned custodial spent fuel sites, high-level radioactive waste sites, and commercial power reactor sites. All design elements meet or exceed applicable regulations governing the disposal of high-level radioactive waste. The design will provide safe disposal of waste materials for at least a 10,000 year period. During this time interval, natural radioactive decay of the waste materials will result in fission products that pose a minimal radiological hazard to the public afterward. For example, after 100 years, the relative hazard from the waste fission products will have diminished approximately 90 percent. After 1,000 years, the hazard will have diminished 99 percent, and after 10,000 years it will have diminished 99.9 percent. The resulting radiological hazard after 10,000 years is minimal, being of the same order of magnitude as that posed by 0.2 percent uranium ore, which is equivalent to that which was used to originally produce the nuclear fuel. Because developing such a repository is extremely complex, the design will move forward in three stages: Site Recommendation, License Application, and Construction. This document presents the design as it will be submitted in the Site Recommendation Consideration Report; the design will be updated as the design process moves forward. As more cost-effective solutions, technical advancements, or changes to requirements occur, the design may evolve. The U.S. Department of Energy's (DOE) Office of Civilian Radioactive Waste Management is developing a system that includes this potential repository. This waste management system integrates acceptance, transportation, storage, and disposal of spent nuclear fuel and high-level radioactive waste. Acceptance and transportation will be handled by regional servicing contractors under contract to the DOE. The U.S. Nuclear Regulatory Commission will conduct an in-depth and thorough licensing review to determine the acceptability of the proposed waste management system. Eight sections of this document follow. Section 2 discusses the design requirements for the proposed repository. Section 3 describes the physical layout of the proposed repository. Section 4 describes the evolutionary phases of the development of the proposed repository. Section 5 describes the receipt of waste. Section 6 details the various systems that will package the waste and move it below ground, as well as safety monitoring and closure. Section 7 describes the syst

NA

2000-10-07T23:59:59.000Z

85

FINDING AID FOR THE MACDONALD COLLECTION Alan N. Queen  

E-Print Network (OSTI)

FINDING AID FOR THE MACDONALD COLLECTION Alan N. Queen Binghamton University, State University) 777-6500 DESCRIPTIVE SUMMARY Title THE MACDONALD COLLECTION ID Extent 8.75 linear ft. Repository in 2012. INTRODCTION Dr. Jeremiah MacDonald (1859-1918) Just before his death in 1918, Jeremiah MacDonald

Suzuki, Masatsugu

86

Soil attenuation of leachates from low-rank coal combustion wastes: a literature survey. [116 references  

SciTech Connect

In parallel with pursuing the goal of increased utilization of low-rank solid fuels, the US Department of Energy is investigating various aspects associated with the disposal of coal-combustion solid wastes. Concern has been expressed relative to the potential hazards presented by leachates from fly ash, bottom ash and scrubber wastes. This is of particular interest in some regions where disposal areas overlap aquifer recharge regions. The western regions of the United States are characterized by relatively dry alkaline soils which may effect substantial attenuation of contaminants in the leachates thereby reducing the pollution potential. A project has been initiated to study the contaminant uptake of western soils. This effort consists of two phases: (1) preparation of a state-of-the-art document on soil attenuation; and (2) laboratory experimental studies to characterize attenuation of a western soil. The state-of-the-art document, represented herein, presents the results of studies on the characteristics of selected wastes, reviews the suggested models which account for the uptake, discusses the specialized columnar laboratory studies on the interaction of leachates and soils, and gives an overview of characteristics of Texas and Wyoming soils. 116 references, 10 figures, 29 tables.

Gauntt, R. O.; DeOtte, R. E.; Slowey, J. F.; McFarland, A. R.

1984-01-01T23:59:59.000Z

87

The Yucca Mountain Project repository sealing program  

SciTech Connect

Yucca Mountain is being characterized for the development of a high-level nuclear waste repository. The repository is planned to be located in the unsaturated zone in fractured, welded tuff. Sealing of the repository is one element of the Yucca Mountain Project. This paper presents a description of the current sealing design options, design requirements, and the design constraints. Design options for the shafts include anchor-to-bedrock seals, shaft fill, and settlement plugs; in the underground facility, they include drift seals, drainage channels, sumps, and bulkheads. Design requirements are those quantitative requirements imposed on the sealing design options to achieve a desired level of performance. For example, a design requirement could be a restriction on the hydraulic conductivity of a design option. Constraints are restrictions placed on the repository design by the sealing design. An example of a constraint could be establishing the drainage pattern to direct flow from emplacement drifts to nonemplacement drifts. As (1) additional hydrogeologic data are obtained through site characterization, (2) approaches to allocating performance to various subsystems within the Yucca Mountain Project are refined, and (3) the exploratory shafts and the associated testing results are developed, the design requirements and constraints may be modified and used in developing the License Application Design.

Fernandez, J.A.; Hinkebein, T.E

1989-12-01T23:59:59.000Z

88

Nuclear Waste Repository Plan Approved by Senate  

Science Journals Connector (OSTI)

Bill calls for selection of permanent repository site by 1989, building of a retrievable waste facility, cash payments states with storage sites ... After considerable debate, the Senate has approved a plan aimed at getting the federal government's effort to find a long-term storage site for spent nuclear fuel and highlevel nuclear wastes off dead center and out of the political crossfire. ...

JANICE LONG

1987-12-07T23:59:59.000Z

89

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

SciTech Connect

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.

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)

2014-02-15T23:59:59.000Z

90

Repository Applications: Potential Benefits of Using Depleted Uranium (DU)  

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

Repository Applications Repository Applications Repository Applications: Potential Benefits of Using Depleted Uranium (DU) in a Geological Repository The United States is investigating the Yucca Mountain (YM) site in Nevada for the disposal of radioactive spent nuclear fuel (SNF)—the primary waste from nuclear power plants. The SNF would be packaged and then emplaced 200 to 300 m underground in parallel disposal tunnels. The repository isolates the SNF from the biosphere until the radionuclides decay to safe levels. DU may improve the performance of geological repositories for disposal of SNF via three mechanisms: Radiation shielding for waste packages to protect workers Lowering the potential for long-term nuclear criticality in the repository Reducing the potential for releases of radionuclides from the SNF

91

Might underground waste repositories blow up?  

SciTech Connect

Some writers have presented possible scenarios in which a subcritical underground deposit of plutonium or other fissile material might be changed into a critical configuration. The underground criticalities that occurred in Gabon some 1.7 billion years ago in deposits of natural uranium is cited. Other scientists assert that it is virtually impossible that such a configuration could develop in an underground repository. The author presents the pros and cons of these views. 5 refs.

Hippel, F. von [Princeton Univ., NJ (United States)

1996-03-01T23:59:59.000Z

92

Benchmark problems for repository siting models  

SciTech Connect

This report describes benchmark problems to test computer codes used in siting nuclear waste repositories. Analytical solutions, field problems, and hypothetical problems are included. Problems are included for the following types of codes: ground-water flow in saturated porous media, heat transport in saturated media, ground-water flow in saturated fractured media, heat and solute transport in saturated porous media, solute transport in saturated porous media, solute transport in saturated fractured media, and solute transport in unsaturated porous media.

Ross, B.; Mercer, J.W.; Thomas, S.D.; Lester, B.H.

1982-12-01T23:59:59.000Z

93

Salt repository project closeout status report  

SciTech Connect

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.

NONE

1988-06-01T23:59:59.000Z

94

Collecting apparatus  

DOE Patents (OSTI)

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

Duncan, Charles P. (Walnut Creek, CA)

1983-01-01T23:59:59.000Z

95

Viability Assessment of a Repository at Yucca Mountain | Department of  

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

Viability Assessment of a Repository at Yucca Mountain Viability Assessment of a Repository at Yucca Mountain Viability Assessment of a Repository at Yucca Mountain Summary 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. The overview describes why the Unites States is considering Yucca Mountain and how a monitored geologic repository would work in the mountain. It presents a repository design, an assessment of its expected performance, and an evaluation of the possible effects on people living near Yucca Mountain. Also presented is the work remaining to be completed prior to a license application, along with the estimated cost of building and operating a

96

Climate Collections  

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

Regional/Global > Climate Collections Regional/Global > Climate Collections Climate Collections Overview Climate encompasses the statistics of temperature, humidity, atmospheric pressure, wind, rainfall, atmospheric particle count, and numerous other meteorological elements in a given region over long periods of time. Climate can be contrasted to weather, which is the present condition of these same elements over periods up to two weeks. The climate collections project includes data sets containing measured and modeled values for variables such as temperature, precipitation, humidity, radiation, wind velocity, and cloud cover and include station measurements as well as gridded mean values. The ORNL DAAC Climate Collections Data archive includes 10 data products from the following categories:

97

Drift Natural Convection and Seepage at the Yucca Mountain Repository.  

E-Print Network (OSTI)

??The decay heat from radioactive waste that is to be disposed in the once proposed geologic repository at Yucca Mountain (YM) will significantly influence the… (more)

Halecky, Nicholaus Eugene

2010-01-01T23:59:59.000Z

98

Area recommendation report for the crystalline repository project: An evaluation. [Crystalline Repository Project  

SciTech Connect

An evaluation is given of DOE's recommendation of the Elk River complex in North Carolina for siting the second repository. Twelve recommendations are made including a strong suggestion that the Cherokee Tribe appeal both through political and legal avenues for inclusion as an affected area primarily due to projected impacts upon economy and public health as a consequence of the potential for reduced tourism.

Beck, J E; Lowe, H; Yurkovich, S P

1986-03-28T23:59:59.000Z

99

Monitored Geologic Repository Project Description Document  

SciTech Connect

The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the ''Monitored Geologic Repository Requirements Document'' (MGR RD) (CRWMS M&O 2000b) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) engineering design basis in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The engineering design basis documented in the PDD is to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the engineering design basis from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the engineering design basis captured in the SDDs and the design requirements captured in U.S. Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M&O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 2-1, the MGR Architecture (Section 4.1),the Engineering Design Bases (Section 5), and the Controlled Project Assumptions (Section 6).

P. Curry

2000-06-01T23:59:59.000Z

100

Monitored Geologic Repository Project Description Document  

SciTech Connect

The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the ''Monitored Geologic Repository Requirements Document'' (MGR RD) (YMP 2000a) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) technical requirements in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The technical requirements documented in the PDD are to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the technical requirements from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the technical requirements captured in the SDDs and the design requirements captured in US Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M and O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 1-1, the MGR Architecture (Section 4.1), the Technical Requirements (Section 5), and the Controlled Project Assumptions (Section 6).

P. M. Curry

2001-01-30T23:59:59.000Z

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


101

The Collective.  

E-Print Network (OSTI)

?? This thesis project investigates different ways of collective living. It offers a different perspective towards the human-environment relationship and the ways in which we… (more)

Mehrin, Nazanin

2013-01-01T23:59:59.000Z

102

Cigeo, the French Geological Repository Project - 13022  

SciTech Connect

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)

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

2013-07-01T23:59:59.000Z

103

Zircaloy cladding rupture during repository storage  

SciTech Connect

In this paper creep, a potential degradation mechanism of Zircaloy cladding after repository disposal of spent nuclear fuel, is investigated. The deformation and fracture map methodology is used to predict maximum allowable initial storage temperatures to achieve a 1000-yr life without rupture as a function of spent-fuel history. Maximum allowable temperatures are 340{degrees}C (613 K) for typically stresses rods (70 to 100 MPa) and 300{degrees}C (573 K) for highly stressed rods (140 to 160 MPa).

Santanam, L.; Raghavan, S.; Chin, B.A. (Auburn Univ., Materials Engineering Dept., Auburn, AL (US))

1992-03-01T23:59:59.000Z

104

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

Office of Environmental Management (EM)

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

105

A Framework for Describing Web Repositories Frank McCown  

E-Print Network (OSTI)

, 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

Nelson, Michael L.

106

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

SciTech Connect

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)

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

2013-07-01T23:59:59.000Z

107

The National Repository at Yucca Mountain, Russ Dyer  

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

Repository at Repository at Yucca Mountain Presented to: EM High Level Waste Corporate Board Presented by: Russ Dyer Chief Scientist Office of Civilian Radioactive Waste Management July 24, 2008 Idaho National Laboratory 2 SBBB-GeneralBriefing_070808Rev1.ppt Solving a national problem now * On June 3, 2008, the U.S. Department of Energy submitted an application to the U.S. Nuclear Regulatory Commission for a license to construct a repository at Yucca Mountain 3 SBBB-GeneralBriefing_070808Rev1.ppt Repository license application * The LA seeks authorization to construct the nation's first geologic repository * It is a culmination of more than 25 years of scientific research and engineering * The LA describes DOE's plan to safely isolate spent nuclear fuel and high-level radioactive

108

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

SciTech Connect

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.

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

2011-09-20T23:59:59.000Z

109

Repository Subsurface Preliminary Fire Hazard Analysis  

SciTech Connect

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

Richard C. Logan

2001-07-30T23:59:59.000Z

110

Monitored Geologic Repository Project Description Document  

SciTech Connect

The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the Yucca Mountain Site Characterization Project Requirements Document (YMP RD) (YMP 2001a) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) technical requirements in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The technical requirements documented in the PDD are to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the technical requirements from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the technical requirements captured in the SDDs and the design requirements captured in US Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M&O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 1-1, the MGR Architecture (Section 4.1), the Technical Requirements (Section 5), and the Controlled Project Assumptions (Section 6).

P. Curry

2001-06-26T23:59:59.000Z

111

Repository surface design site layout analysis  

SciTech Connect

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

Montalvo, H.R.

1998-02-27T23:59:59.000Z

112

Adding OAI-ORE Support to Repository Platforms  

E-Print Network (OSTI)

to DSpace considerably simplifies the task of maintaining TDL?s federated ETD colection. However, the aplications of this project extend beyond its initial use case. The ability to easily harvest content from one repository to another provides...

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

2009-05-17T23:59:59.000Z

113

A Repository for Beyond-the-Standard-Model Tools  

SciTech Connect

To aid phenomenological studies of Beyond-the-Standard-Model (BSM) physics scenarios, a web repository for BSM calculational tools has been created. We here present brief overviews of the relevant codes, ordered by topic as well as by alphabet.

Skands, P.; /Fermilab; Richardson, P.; Allanach, B.C.; Baer, H.; Belanger, G.; El Kacimi, M.; Ellwanger, U.; Freitas, A.; Ghodbane, N.; Goujdami, D.; Hahn, T.; Heinemeyer,; Kneur, J.-L.; Landsberg, G.; Lee, J.S.; Muhlleitner, M.; Ohl, T.; Perez, E.; Peskin, M.; Pilaftsis, A.; Plehn, T.

2005-05-01T23:59:59.000Z

114

Drift Natural Convection and Seepage at the Yucca Mountain Repository  

E-Print Network (OSTI)

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

Halecky, Nicholaus Eugene

2010-01-01T23:59:59.000Z

115

Waste package/repository impact study: Final report  

SciTech Connect

The Waste Package/Repository Impact Study was conducted to evaluate the feasibility of using the current reference salt waste package in the salt repository conceptual design. All elements of the repository that may impact waste package parameters, i.e., (size, weight, heat load) were evaluated. The repository elements considered included waste hoist feasibility, transporter and emplacement machine feasibility, subsurface entry dimensions, feasibility of emplacement configuration, and temperature limits. The evaluations are discussed in detail with supplemental technical data included in Appendices to this report, as appropriate. Results and conclusions of the evaluations are discussed in light of the acceptability of the current reference waste package as the basis for salt conceptual design. Finally, recommendations are made relative to the salt project position on the application of the reference waste package as a basis for future design activities. 31 refs., 11 figs., 11 tabs.

Not Available

1985-09-01T23:59:59.000Z

116

Automated Validation of Trusted Digital Repository Assessment Criteria  

E-Print Network (OSTI)

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 ...

Smith, MacKenzie

117

An analysis of repository waste-handling operations  

SciTech Connect

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

Dennis, A.W.

1990-09-01T23:59:59.000Z

118

Improving Repository Performance by Using a Fill  

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

a Fill a Fill Improving Repository Performance by Using a Fill The use of fills, semi-independent of the specific fill material, can improve package performance. The first barrier to prevent releases from the spent nuclear fuel is the waste package itself. The longer the waste package remains intact, the lower the ultimate releases from the spent nuclear fuel. In a typical waste package over half of the interior space is empty space. There are coolant channels in the spent fuel and square fuel assemblies can not fully fill a round waste package. After the package is buried, it will begin to corrode and the walls will thin. Rock falls may cause early failure of the waste package. However, if the package is full, it is more difficult to crush a full package and fail the exterior wall. The behavior of a waste package over time is similar to a soda can. Empty cans are easy to crush. Full, sealed cans are difficult to crush because the fluid inside supports the can.

119

REPOSITORY SURFACE FACILITIES PRIMARY SYSTEM CRANE DATA  

SciTech Connect

The purpose of this calculation is to compile crane design data for the mechanical primary structures, systems, and components (SSCs) required for the repository Waste Handling Building (WHB) and Carrier Preparation Building (CPB). The work presented in this document has been prepared in accordance with Office of Civilian Radioactive Waste Management approved program document AP-3.12Q, Calculations. This calculation has been developed to supplement information previously prepared using the development plan for ''WHB/WTB Space Program Analysis for Site Recommendation'' (Reference 5), which concentrates on the primary, primary support, facility support, and miscellaneous building support areas located in the WHB and Waste Treatment Building (WTB). The development plan was completed in accordance with AP-2.13Q, ''Technical Product Development Planning''. The work in this calculation is a continuance of the work described in the previous development plan; therefore, in accordance with AP-2.21Q, ''Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities'', a new Technical Work Plan is not required.

K. Schwartztrauber

2005-03-14T23:59:59.000Z

120

Nucleosynthetic osmium isotope anomalies in acid leachates of the Murchison meteorite  

E-Print Network (OSTI)

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.

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

2008-12-15T23:59:59.000Z

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


121

Determination of long-lived actinides in soil leachates by inductively coupled plasma: Mass spectrometry  

SciTech Connect

Inductively coupled plasma -- mass spectrometry (ICP-MS) was used to concurrently determine multiple long-lived (t{sub 1/2} > 10{sup 4} y) actinide isotopes in soil samples. Ultrasonic nebulization was found to maximize instrument sensitivity. Instrument detection limits for actinides in solution ranged from 50 mBq L{sup {minus}1} ({sup 239}Pu) to 2 {mu}Bq L{sup {minus}1} ({sup 235}U) Hydride adducts of {sup 232}Th and {sup 238}U interfered with the determinations of {sup 233}U and {sup 239} Pu; thus, extraction chromatography was, used to eliminate the sample matrix, concentrate the analytes, and separate uranium from the other actinides. Alpha spectrometric determinations of {sup 230}Th, {sup 239}Pu, and the {sup 234}U/{sup 238}U activity ratio in soil leachates compared well with ICP-MS determinations; however, there were some small systematic differences (ca. 10%) between ICP-MS and a-spectrometric determinations of {sup 234}U and {sup 238}U activities.

Crain, J.S.; Smith, L.L.; Yaeger, J.S.; Alvarado, J.A.

1994-06-01T23:59:59.000Z

122

Case study of landfill leachate recirculation using small-diameter vertical wells  

Science Journals Connector (OSTI)

Abstract A case study of landfill liquids addition using small diameter (5 cm) vertical wells is reported. More than 25,000 m3 of leachate was added via 134 vertical wells installed 3 m, 12 m, and 18 m deep over five years in a landfill in Florida, US. Liquids addition performance (flow rate per unit screen length per unit liquid head) ranged from 5.6 × 10?8 to 3.6 × 10?6 m3 s?1 per m screen length per m liquid head. The estimated radial hydraulic conductivity ranged from 3.5 × 10?6 to 4.2 × 10?4 m s?1. The extent of lateral moisture movement ranged from 8 to 10 m based on the responses of moisture sensors installed around vertical well clusters, and surface seeps were found to limit the achievable liquids addition rates, despite the use of concrete collars under a pressurized liquids addition scenario. The average moisture content before (51 samples) and after (272 samples) the recirculation experiments were 23% (wet weight basis) and 45% (wet weight basis), respectively, and biochemical methane potential measurements of excavated waste indicated significant (p < 0.025) decomposition.

Pradeep Jain; Jae Hac Ko; Dinesh Kumar; Jon Powell; Hwidong Kim; Lizmarie Maldonado; Timothy Townsend; Debra R. Reinhart

2014-01-01T23:59:59.000Z

123

Proceedings of the scientific visit on crystalline rock repository development.  

SciTech Connect

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.

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

2013-02-01T23:59:59.000Z

124

Transportation analysis for the concept of regional repositories  

SciTech Connect

Over the past several years, planning associated with the National Waste Terminal Storage (NWTS) program assumed the use of one or two large, centrally located repository facilities. Recently, an alternative approach has been proposed which consists of the use of multiple, smaller regional repositories. In this report, several regional concepts were studied and the transportation requirements for the shipment of spent fuel to the regional repositories were estimated. In general, the transportation requirements decrease as the number of repositories increase. However, as far as transportation is concerned, the point of diminishing returns is reached at approximately one repository in each of three to four regions. Additional savings beyond this point are small. A series of sensitivity studies is also included to demonstrate the impact on the total transportation requirements of varying cask capacity, rail speed, or truck speed. Since most of the projected fuel shipments are to be made by rail, varying the capacity of the rail cask or varying average rail transport speed will have a major effect on overall transportation requirements.

Joy, D.S.; Hudson, B.J.

1980-06-01T23:59:59.000Z

125

Environmental Assessment for Actinide Chemistry and Repository Science  

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

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

126

Repository Reference Disposal Concepts and Thermal Load Management Analysis  

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

Repository Reference Disposal Concepts and Thermal Load Management Repository Reference Disposal Concepts and Thermal Load Management Analysis Repository Reference Disposal Concepts and Thermal Load Management Analysis A disposal concept consists of three parts: waste inventory (7 waste types examined), geologic setting (e.g., clay/shale, salt, crystalline, other sedimentary), and the engineering concept of operations (range of generic operational concepts examined). Two major categories for waste package emplacement modes are identified: 1) "open" where extended ventilation can remove heat for many years following waste emplacement underground; and 2) "enclosed" modes for clay/shale and salt media where waste packages are emplaced in direct or close contact with natural or engineered materials which may have temperature limits that constrain thermal

127

Long-term Repository Benefits of Using Cermet Waste Packages  

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

Long-Term Benefits Long-Term Benefits Long-term Repository Benefits of Using Cermet Waste Packages A cermet waste package may improve the long-term performance of the YM repository by two mechanisms: reducing (1) the potential for nuclear criticality in the repository and (2) the long-term release rate of radionuclides from the waste package. In the natural environment, the centers of uranium ore deposits have remained intact for very long time periods while the outer edges of the ore deposit have degraded. A cermet waste package may operate in the same way. The sacrificial, slow degradation of the waste package and the DU oxide protects the SNF uranium dioxide in the interior of the package long after the package has failed. Page 2 of 4 Follow the link below to learn more about Cermets:

128

Final Supplemental Environmental Impact Statement for a Geologic Repository  

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

Supplemental Environmental Impact Statement for a Geologic Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada - Nevada Rail Transportation CorridorDOE/EIS-0250F-S2andFinal Envir Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada - Nevada Rail Transportation CorridorDOE/EIS-0250F-S2andFinal Envir This part of the Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada -- Nevada Rail Transportation Corridor (DOE/EIS-0250F-S2) (Nevada Rail Corridor SEIS)

129

Repository Reference Disposal Concepts and Thermal Load Management Analysis  

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

Repository Reference Disposal Concepts and Thermal Load Management Repository Reference Disposal Concepts and Thermal Load Management Analysis Repository Reference Disposal Concepts and Thermal Load Management Analysis A disposal concept consists of three parts: waste inventory (7 waste types examined), geologic setting (e.g., clay/shale, salt, crystalline, other sedimentary), and the engineering concept of operations (range of generic operational concepts examined). Two major categories for waste package emplacement modes are identified: 1) "open" where extended ventilation can remove heat for many years following waste emplacement underground; and 2) "enclosed" modes for clay/shale and salt media where waste packages are emplaced in direct or close contact with natural or engineered materials which may have temperature limits that constrain thermal

130

Final Supplemental Environmental Impact Statement for a Geologic Repository  

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

- Nevada Rail - Nevada Rail Transportation Corridor DOE/EIS-0250F-S2 and Final Env Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada -- Nevada Rail Transportation Corridor DOE/EIS-0250F-S2 and Final Env The Summary of the Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada -- Nevada Rail Transportation Corridor DOE/EIS-0250F-S2 and Final Environmental Impact Statement for a Rail Alignment for the Construction and Operation of a Railroad in Nevada to a Geologic Repository at Yucca Mountain, Nye County,

131

Improving Repository Performance by Using DU Dioxide Fill  

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

DU Dioxide Fill DU Dioxide Fill Improving Repository Performance by Using DU Dioxide Fill Fills may improve repository performance by acting as sacrificial materials, which delay the degradation of SNF uranium dioxide. Because fill and SNF have the same chemical form of uranium (uranium dioxide), the DU dioxide in a repository is the only fill which has the same behavior as that of the SNF. In the natural environment, some uranium ore deposits have remained intact for very long periods of time. The outer parts of the ore deposit degrade while the inner parts of the deposit are protected. The same approach is proposed herein for protecting SNF. The application could use half or more of the DU inventory in the United States. Behavior of Uranium and Potential Behavior of a Waste Package with SNF and Fill

132

Evaluation of Incident Risks in a Repository for Radioactive Waste  

SciTech Connect

A probabilistic safety assessment of the operation phase of a repository for radioactive waste requires the knowledge of incident risks. These are evaluated from generic observations. The present method accounts for the uncertainty (1) of whether an incident occurs, (2) of the incident rate, (3) of the duration of generic observation, and (4) of the duration of operation phase of the repository. It yields a mean risk and its standard deviation from a minimum of generic data, comprising only the number of observed incidents and the duration of the observation, as more comprehensive generic data are seldom available. It was shown that incidents sharing a common generic observation must be either merged together to a total incident or the generic observation must be split up in sub-observations, one for each such incident. The method was tested on the example of the German Konrad repository for low-level waste in a deep geological formation. (authors)

Grundler, D.; Mariae, D.; Muller, W.; Boetsch, W. [Institut fur Sicherheitstechnologie (ISTec), Koln (Germany); Thiel, J. [Bundesamt fur Strahlenschutz (BfS), Salzgitter (Germany)

2008-07-01T23:59:59.000Z

133

The usage of open educational resources in MAOR repository  

Science Journals Connector (OSTI)

In this paper, an innovative view of open online learning materials repositories will be presented through the example of MAOR, Israel's national repository that is linked to MERLOT. Web-usage mining techniques are utilised to explore three aspects: (a) distribution level of learning object (LO) that was contributed; (b) tools available to the community and its contribution to object quality; (c) transfer from public to personal workspaces. The use of MAOR repository has become substantial and continues to rise every year to both local and global audience. MAOR members contributed more than 3,300 LO and may access to approximately 30,000 in MERLOT. Furthermore, as part of the learning community they share knowledge by adding comments regarding the object and their experiences and benefit from additional information contributed by users in MERLOT. In addition, the potential of the personal workspaces was identified even though it is a new feature in MAOR.

Eli Shmueli; Anat Cohen

2012-01-01T23:59:59.000Z

134

Interaction of Plutonium with Bacteria in the Repository Environment  

SciTech Connect

Microorganisms in the nuclear waste repository environment may interact with plutonium through (1) sorption, (2) intracellular accumulation, and (3) transformation speciation. These interactions may retard or enhance the mobility of Pu by precipitation reactions, biocolloid formation, or production of more soluble species. Current and planned radioactive waste repository environments, such as deep subsurface halite and granite formations, are considered extreme relative to life processes in the near-surface terrestrial environment. There is a paucity of information on the biotransformation of radionuclides by microorganisms present in such extreme environments. In order to gain a better understanding of the interaction of plutonium with microorganisms present in the waste repository sites we investigated a pure culture (Halomonas sp.) and a mixed culture of bacteria (Haloarcula sinaiiensis, Marinobacter hydrocarbonoclasticus, Altermonas sp., and a {gamma}-proteobacterium) isolated from the Waste Isolation Pilot Plant (WIPP) site and an Acetobacterium sp. from alkaline groundwater at the Grimsel Test Site in Switzerland.

Gillow, J. B.; Francis, A. J.; Lucero, D. A.; Papenguth, H. W.

2000-07-01T23:59:59.000Z

135

Implementation of the Brazilian National Repository - RBMN Project - 13008  

SciTech Connect

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)

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

2013-07-01T23:59:59.000Z

136

Siting America's geologic repository for high-level Nuclear Waste: Implications for environmental Policy  

Science Journals Connector (OSTI)

Siting a geologic repository for isolating highlevel nuclear waste up to 10,000 years is ... before attempted in the United States. The Nuclear Waste Policy Act of 1982 exempted repository siting from ... require...

John Lemons; Charles Malone

137

Design and implementation of the Web-enabled NIST design repository  

Science Journals Connector (OSTI)

This article describes the design and development of a design repository software system. This system is a prototype implementation intended to demonstrate the role of design repositories as part of a vision for the next generation of product development ...

Simon Szykman; Ram D. Sriram

2006-02-01T23:59:59.000Z

138

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

E-Print Network (OSTI)

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, ...

Smith, MacKenzie

2002-01-01T23:59:59.000Z

139

The Proposed Yucca Mountain Repository From A Corrosion Perspective  

SciTech Connect

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.

J.H. Payer

2005-03-10T23:59:59.000Z

140

Parameters and variables appearing in repository-siting models  

SciTech Connect

Included in this report is a summary of data characterizing the parameters and variables appearing in repository siting models. These data cover the processes of saturates flow, unsaturated flow, surface water flow, geochemistry, heat transport, solute transport, and geomechanical response. Definitions and ranges of values are provided for equation parameters, source terms, dependent variables, boundary conditions, and initial conditions for the equations that are solved in the repository siting models. The data were compiled to help guide the selection of values of parameters and variables to be used in benchmark problems.

Mercer, J.W.; Thomas, S.D.; Ross, B.

1982-12-01T23:59:59.000Z

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


141

E-Print Network 3.0 - ash leachate generation Sample Search Results  

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

Research and Technology Council (WTERT) Collection: Renewable Energy 4 Leaching of Dioxins from Municipal Waste Combustor Residues Summary: ......

142

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

SciTech Connect

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

Hazen, Terry

2002-08-26T23:59:59.000Z

143

Early Restoration Plan Repositories STATE LIBRARY ADDRESS CITY ZIP  

E-Print Network (OSTI)

Calcasieu Parish Public Library Central Branch 301 W. Claude St. Lake Charles 70605 #12;STATE LIBRARYEarly Restoration Plan Repositories STATE LIBRARY ADDRESS CITY ZIP AL Dauphin Island Sea Laboratory. Walton 32548 FL Panama City Beach Public Library 125000 Hutchison Blvd Panama City Beach 32407 FL

144

Advanced fuel cycles and impacts On The Yucca Mountain Repository  

SciTech Connect

One of the goals identified for advanced fuel cycles, such as that proposed by the Global Nuclear Energy Partnership, is to reduce the volume of wastes that would ultimately have to be disposed in a geologic repository. Besides reducing volume, techniques that recycle the vast majority of actinides along with the removal of key fission products also reduce the inventory of radionuclides that must ultimately be disposed and the thermal output of the wastes. Advanced recycling techniques may also generate waste forms having different characteristics than those that have been considered for disposal in a repository at Yucca Mountain to-date. These all have a potential impact on several aspects of a repository, such as the proposed repository at Yucca Mountain, including surface and subsurface facility design, pre-closure and post-closure safety analyses, and ultimately licensing. These changes would all have to be performed in accordance with the requirements at 10 CFR 63 and approved by the U.S. Nuclear Regulatory Commission in a license amendment prior to the disposal of any wastes from an advanced fuel cycle. (authors)

Nutt, W.M.; Peters, M.T. [Argonne National Laboratory, Argonne, IL (United States); Swift, P.N. [Sandia National Laboratories, New Mexico, Albuquerque, NM (United States)

2007-07-01T23:59:59.000Z

145

Effect of repository underground ventilation on emplacement drift temperature control  

SciTech Connect

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

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

1996-02-01T23:59:59.000Z

146

Grey/Gray Matter: The Role of Institutional Repositories  

E-Print Network (OSTI)

and the Academy 3:2 (2003), pp. 327-336. 7. Crow, Raym. "The Case for Institutional Repositories: A SPARC Position Paper." ARL Bimonthly Report 223 (August 2002). 8. google.com 9. DSpace@MIT http://dspace.mit.edu 12. IDEALS http...

Mercer, Holly

2011-04-15T23:59:59.000Z

147

Impact of Pyrophoric Events on Long-Term Repository Performance  

SciTech Connect

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.

Richard Gregg

2005-09-01T23:59:59.000Z

148

Performance assessment implementation plan for the geologic repository program  

SciTech Connect

Performance assessment is a major constituent of the program being conducted in the Civilian Radioactive Waste Management (CRWM) Program of the US Department of Energy (DOE) to develop a geologic repository. Performance assessment is the set of activities needed for quantitative evaluations of repository-system performance to access compliance with regulations and to support the development of the geologic repository. To define the strategy for these evaluations, the DOE has developed this performance assessment strategy plan. This document discusses the need for such a strategy, the objectives and scope of the strategy plan, the relationship of the plan to other program plans. Additionally, it defines performance assessment and describes the roles of performance assessment in this program, discusses concepts and general strategies needed for performance assessment, outlines the content of the Safety Analysis Report, summarizes the requirements for the repository Environmental Impact Statement, discusses the requirements that apply to the site-suitability analyses and describes the site characterization. 10 figs., 7 tabs.

NONE

1990-01-01T23:59:59.000Z

149

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

E-Print Network (OSTI)

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

Southampton, University of

150

Deep Repositories: Out of Sight, Out of Terrorists' Reach  

Science Journals Connector (OSTI)

...civilian nuclear power plants will be loaded...heat of the nuclear material...relentless attack by moisture...terrorist attacks have highlighted...The risks we face from terrorism and nuclear proliferation are...abandon nuclear power, the repositories...and Global Security. If the fire...built this plant, we thought...

Richard Stone

2004-01-09T23:59:59.000Z

151

Environmental effects on corrosion in the Tuff repository  

SciTech Connect

Cortest Columbus is investigating the long-term performance of container materials used for high-level waste packages as part of the information needed by the Nuclear Regulatory Commission to assess the Department of Energy`s application to construct a geologic repository for high-level radioactive waste. The scope of work consists of employing short-term techniques, to examine a wide range of possible failure modes. Long-term tests are being used to verify and further examine specific failure modes identified as important by the short-term studies. The original focus of the program was on the salt repository but the emphasis was shifted to the Tuff repository. This report summarizes the results of a literature survey performed under Task 1 of the program. The survey focuses on the influence of environmental variables on the corrosion behavior of candidate container materials for the Tuff repository. Environmental variables considered include: radiation, thermal and microbial effects. 80 refs., 44 figs., 44 tabs.

Beavers, J.A.; Thompson, N.G. [Cortest Columbus, Inc., OH (USA)

1990-02-01T23:59:59.000Z

152

Licensing A Geologic Repository At Yucca Mountain, Nevada  

SciTech Connect

After completing more than twenty years of intensive scientific and engineering investigations at the Yucca Mountain site in Nevada, the U.S. Department of Energy (DOE) has determined that the site is suitable for development of a geologic repository for disposal of the Nation's spent nuclear fuel and high-level radioactive waste. Following this determination, the site was recommended to the President for repository development. The President approved the recommendation and forwarded it to the U.S. Congress for site designation. The Governor of Nevada vetoed the recommendation with a notice of disapproval to the U.S. Congress. Congress subsequently over-rode the Governor's veto with a joint resolution which the President signed into law. With site designation in effect, DOE is now focusing its work on the development of a license application for repository construction. This paper will summarize the work that had been done to support site recommendation, work that is currently being done for license application, and the necessary next steps that may be required to allow repository operations to begin in 2010.

Dyer, R. J.

2003-02-24T23:59:59.000Z

153

Cancer Usurps Skeletal Muscle as an Energy Repository  

Science Journals Connector (OSTI)

...Biology Cancer Usurps Skeletal Muscle as an Energy Repository Yi Luo 1 Junya Yoneda 2 Hitoshi...supply glutamine to cancer cells as an energy source through the release of HMGB1...muscle physiology. Cancer cells produce energy through aerobic glycolysis, but contributions...

Yi Luo; Junya Yoneda; Hitoshi Ohmori; Takamitsu Sasaki; Kazutaka Shimbo; Sachise Eto; Yumiko Kato; Hiroshi Miyano; Tsuyoshi Kobayashi; Tomonori Sasahira; Yoshitomo Chihara; Hiroki Kuniyasu

2014-01-01T23:59:59.000Z

154

Oxidation-induced geochemical changes in trench leachates from the Maxey Flats low-level radioactive waste disposal site  

SciTech Connect

A knowledge of extra-trench processes related to oxidation-induced geochemical changes that are likely to occur when iron-rich, anoxic trench waters encounter an oxidizing environment along a redox gradient is essential for modeling radionuclide transport at low-level waste (LLW) disposal sites. The results of laboratory oxidation experiments on several trench leachates from the Maxey Flats site show that, upon oxidation, a series of geochemical changes were initiated that resulted in a drastically different solute geochemistry, involving oxidation of ferrous iron and subsequent precipitation of ferric oxyhydroxide, changes in alkalinity and acidity, a drastic increase in redox potential (Eh), and generally relatively little change in the concentrations of /sup 60/Co, /sup 137/Cs, and /sup 85/Sr in solution. The observations made in this study have important geochemical implications for the modeling of LLW sites in that the source term as an input parameter cannot be assumed to be constant, both spatially and temporally. The acid-generating potential and buffering capacity of an anoxic source term are important geochemical controls that maintain a balance between acidity and alkalinity and largely determine the nature and extent of oxidation-induced geochemical changes likely to occur along a redox gradient. The presence of organic chelating agents can alter the source term geochemistry to such an extent that authigenic ferric oxyhydroxide, which represents a geochemical discontinuity at the redox interface along leachate migration paths, proves to be a relatively ineffective sink for radionuclides.

Dayal, R.; Pietrzak, R.F.; Clinton, J.H.

1986-02-01T23:59:59.000Z

155

A Summary of Properties Used to Evaluate INEEL Calcine Disposal in the Yucca Mountain Repository  

SciTech Connect

To support evaluations of the direct disposal of Idaho National Engineering and Environmental Laboratory calcines to the repository at Yucca Mountain, an evaluation of the performance of the calcine in the repository environment must be performed. This type of evaluation demonstrates, through computer modeling and analysis, the impact the calcine would have on the ability of the repository to perform its function of containment of materials during the repository lifetime. This report discusses parameters that were used in the scoping evaluation conducted in FY 2003. It provides nominal values for the parameters, with explanation of the source of the values, and how the values were modified for use in repository analysis activities.

Dahl, C.A.

2003-07-14T23:59:59.000Z

156

Nevada potential repository preliminary transportation strategy Study 2. Volume 1  

SciTech Connect

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).

NONE

1996-02-01T23:59:59.000Z

157

Effects of Leachate from Crumb Rubber and Zinc in Green Roofs on the Survival, Growth, and Resistance Characteristics of Salmonella enterica subsp. enterica Serovar Typhimurium  

Science Journals Connector (OSTI)

...Leachate from Crumb Rubber and Zinc in Green Roofs on the Survival, Growth, and Resistance...Resources, Dover, Delaware, USA. The use of green roofs is a growing practice worldwide...into artificial medium for plant growth in green roofs and similar engineered environments...

Mollee Crampton; Allayna Ryan; Cori Eckert; Katherine H. Baker; Diane S. Herson

2014-02-28T23:59:59.000Z

158

DOE Hydrogen Analysis Repository: Biogas Resources Characterization  

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

Biogas Resources Characterization Biogas Resources Characterization Project Summary Full Title: Biogas Resources Characterization Project ID: 259 Principal Investigator: Ali Jalalzadeh-Azar Brief Description: This project intends to develop a cost-analysis tool based on the H2A Production model, collect global information system (GIS) / cost data, and perform techno-economic analyses of upgrading biogas and utilizing the resulting bio-methane. Keywords: Biogas; Bio-methane; Landfill; Dairy farm; Sewage treatment plant; Fuel cell Purpose Fuel cells operating on bio-methane or on hydrogen derived from bio-methane can mitigate energy and environmental issues and provide an opportunity for their commercialization. This project can provide valuable insights and information to the stakeholders-utilities, municipalities, and policy

159

Sorption of 237Np by UO2 under Repository Conditions  

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

237 Np by UO 2 under Repository Conditions M. Jonathan Haire E. V. Zakharova T. V. Kazakovskaya Oak Ridge National Laboratory Institute of Physical Chemistry Institute of Experimental Physics Oak Ridge, Tennessee 37831-6166 Moscow, Russia, 117915 Sarov, Russia, 607190 Phone: (865) 574-7141 Phone: 7 095 335 1742 Phone: 7 42796 73369 e-mail: hairemj@ornl.gov e-mail: zakharova@ipc.rssi.ru e-mail: kaz@astra.vniief.ru Abstract - The primary radioisotope contributor to the calculated long-term radiation dose to the public at the Yucca Mountain spent nuclear fuel (SNF) repository site boundary is neptunium-237 ( 237 Np). Russian experiments have shown that Np(V) and Np(IV) are sorbed onto UO 2 . If Np were sorbed by UO 2 in spent fuel rather than being transported to the site

160

Final Supplemental Environmental Impact Statement for a Geologic Repository  

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

Nevada Rail Nevada Rail Transportation Corridor DOE/EIS-0250F-S2 and Final En Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada - Nevada Rail Transportation Corridor DOE/EIS-0250F-S2 and Final En Proposed Action: To determine a rail alignment within a rail corridor in which to construct and operate a railroad to transport spent nuclear fuel, high-level radioactive waste, and other materials from an existing railroad in Nevada to a repository at Yucca Mountain, Nye County, Nevada. The Proposed Action includes the construction of railroad construction and operations support facilities. This Rail Alignment EIS analyzes two alternatives that would implement the Proposed Action: the Caliente rail

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


161

and could possibly serve as a repository for  

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

and could possibly serve as a repository for and could possibly serve as a repository for captured CO 2 emissions. The formation is covered by layers of low permeability rock and possesses several properties that are conducive to CO 2 storage, such as the appropriate depth, thickness, porosity, and permeability. Prior to drilling the test well, MRCSP conducted a seismic survey at the site and obtained necessary permits for the injection test from the U.S. Environmental Protection Agency (EPA) and the Kentucky Division of Oil and Gas. Following the permitting process, the researchers injected clean brine in order to determine formation properties like the maximum injection rate and then injected approximately 1,000 metric tons of CO 2 in two, 500-meter-ton steps. The injection rate, pressure, temperature,

162

Asse salt mine nuclear waste repository simulation experiments  

SciTech Connect

The field tests underway in Asse, Federal Republic of Germany are dicected toward the development of test plans, techniques and equipment to be used in Exploratory Shafts or At Depth Test Facilities confirmation tests. These simulated repository tests will also provide information which address the following issues: brine migration (liquid and vapor); radiation effects of gamma rays; gas generation caused by radiation and corrosion; accelerated corrosion and leaching; altered properties of salt (the effects of heat, radiation and brine); and the effects of heat and radiation on test assemblies, instruments, and various materials exposed to repository conditions. This paper is a status of the first 82 days of operation of the Asse Brine Migration Tests, which were initiated on May 25, 1983. 6 references.

Coyle, A.J.

1983-01-01T23:59:59.000Z

163

Monitored Geologic Repository Operations Monitoring and Control System Description Document  

SciTech Connect

The Monitored Geologic Repository Operations Monitoring and Control System provides supervisory control, monitoring, and selected remote control of primary and secondary repository operations. Primary repository operations consist of both surface and subsurface activities relating to high-level waste receipt, preparation, and emplacement. Secondary repository operations consist of support operations for waste handling and treatment, utilities, subsurface construction, and other selected ancillary activities. Remote control of the subsurface emplacement operations, as well as, repository performance confirmation operations are the direct responsibility of the system. In addition, the system monitors parameters such as radiological data, air quality data, fire detection status, meteorological conditions, unauthorized access, and abnormal operating conditions, to ensure a safe workplace for personnel. Parameters are displayed in a real-time manner to human operators regarding surface and subsurface conditions. The system performs supervisory monitoring and control for both important to safety and non-safety systems. The system provides repository operational information, alarm capability, and human operator response messages during emergency response situations. The system also includes logic control to place equipment, systems, and utilities in a safe operational mode or complete shutdown during emergency response situations. The system initiates alarms and provides operational data to enable appropriate actions at the local level in support of emergency response, radiological protection response, evacuation, and underground rescue. The system provides data communications, data processing, managerial reports, data storage, and data analysis. This system's primary surface and subsurface operator consoles, for both supervisory and remote control activities, will be located in a Central Control Center (CCC) inside one of the surface facility buildings. The system consists of instrument and control equipment and components necessary to provide human operators with sufficient information to monitor and control the operation of the repository in an efficient and safe manner. The system consists of operator consoles and workstations, multiple video display terminals, communications and interfacing equipment, and instrument and control software with customized configuration to meet the needs of the Monitored Geologic Repository (MGR). Process and logic controllers and the associated input/output units of each system interfaced with this system will be configured into Remote Terminal Units (RTU) and located close to the systems to be monitored and controlled. The RTUs are configured to remain operational should communication with CCC operations be lost. The system provides closed circuit television to selectively view systems, operations, and equipment areas and to aid in the operation of mechanical systems. Control and monitoring of site utility systems will be located in the CCC. Site utilities include heating, ventilation, and air conditioning equipment; plant compressed air; plant water; firewater; electrical systems; and inert gases, such as nitrogen, if required. This system interfaces with surface and subsurface systems that either generate output data or require remote control input. The system interfaces with the Site Communications System for bulk storage of operational data, on-site and off-site communication, and a plant-wide public announcement system. The system interfaces with the Safeguards and Security System to provide operational status and emergency alarm indications. The system interfaces with the Site Operation System to provide site wide acquisition of data for analysis and reports, historical information for trends, utility information for plant operation, and to receive operating plans and procedures.

E.F. Loros

2000-06-29T23:59:59.000Z

164

HYDRIDE-RELATED DEGRADATION OF SNF CLADDING UNDER REPOSITORY CONDITIONS  

SciTech Connect

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

K. McCoy

2000-12-12T23:59:59.000Z

165

Current Status of The Romanian National Deep Geological Repository Program  

SciTech Connect

Construction of a deep geological repository is a very demanding and costly task. By now, countries that have Candu reactors, have not processed the spent fuel passing to the interim storage as a preliminary step of final disposal within the nuclear fuel cycle back-end. Romania, in comparison to other nations, represents a rather small territory, with high population density, wherein the geological formation areas with radioactive waste storage potential are limited and restricted not only from the point of view of the selection criteria due to the rocks natural characteristics, but also from the point of view of their involvement in social and economical activities. In the framework of the national R and D Programs, series of 'Map investigations' have been made regarding the selection and preliminary characterization of the host geological formation for the nation's spent fuel deep geological repository. The fact that Romania has many deposits of natural gas, oil, ore and geothermal water, and intensively utilizes soil and also is very forested, cause some of the apparent acceptable sites to be rejected in the subsequent analysis. Currently, according to the Law on the spent fuel and radioactive waste management, including disposal, The National Agency of Radioactive Waste is responsible and coordinates the national strategy in the field and, subsequently, further actions will be decided. The Romanian National Strategy, approved in 2004, projects the operation of a deep geological repository to begin in 2055. (authors)

Radu, M.; Nicolae, R.; Nicolae, D. [Center of Technology and Engineering for Nuclear Objectives (CITON), ILFOV County (Romania)

2008-07-01T23:59:59.000Z

166

Repository Safety Strategy: Strategy for Protecting Public Health and Safety after Closure of a Yucca Mountain Repository, Rev. 1  

SciTech Connect

The updated Strategy to Protect Public Health and Safety explains the roles that the natural and engineered systems are expected to play in achieving the objectives of a potential repository system at Yucca Mountain. These objectives are to contain the radionuclides within the waste packages for thousands of years, and to ensure that annual doses to a person living near the site will be acceptably low. This strategy maintains the key assumption of the Site Characterization Plan (DOE 1988) strategy that the potential repository level (horizon) will remain unsaturated. Thus, the strategy continues to rely on the natural attributes of the unsaturated zone for primary protection by providing a setting where waste packages assisted by other engineered barriers are expected to contain wastes for thousands of years. As in the Site Characterization Plan (DOE 1988) strategy, the natural system from the walls of the underground openings (drifts) to the human environment is expected to provide additional defense by reducing the concentrations of any radionuclides released from the waste packages. The updated Strategy to Protect Public Health and Safety is the framework for the integration of site information, repository design and assessment of postclosure performance to develop a safety case for the viability assessment and a subsequent license application. Current site information and a reference design are used to develop a quantitative assessment of performance to be compared with a performance measure. Four key attributes of an unsaturated repository system that are critical to meeting the objectives: (1) Limited water contacting the waste packages; (2) Long waste package lifetime; (3) Slow rate of release of radionuclides from the waste form; and (4) Concentration reduction during transport through engineered and natural barriers.

DOE

1998-01-01T23:59:59.000Z

167

Proceedings of 3rd US/German Workshop on Salt Repository Research, Design,  

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

Proceedings of 3rd US/German Workshop on Salt Repository Research, Proceedings of 3rd US/German Workshop on Salt Repository Research, Design, and Operation Proceedings of 3rd US/German Workshop on Salt Repository Research, Design, and Operation The 3rd U.S./German Workshop on Salt Repository Research, Design and Operation was held in Albuquerque and Carlsbad, New Mexico on October 8-11, 2012. Approximately 60 salt research scientists from Germany and the United States met to discuss repository science state of the art. Workshop topics included: 1) Safety case for heat-generating waste disposal in salt; 2) Benchmark modeling in preparation for thermomechanical field-scale tests; and 3) Reconsolidation of granular salt. Collaboration being pursued by U.S. and German salt repository researchers is presented in the report.

168

EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and  

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

EIS-0250: Geologic Repository for the Disposal of Spent Nuclear EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada Summary 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 radioactive waste. The EIS evaluates not only impacts from constructing, operating, monitoring, and closing a repository, but also from transporting the materials from 72 commercial and 4 DOE sites to the Yucca Mountain repository site in Nye County, Nevada. Public Comment Opportunities

169

Scenarios constructed for nominal flow in the presence of a repository at Yucca Mountain and vicinity  

SciTech Connect

Scenario development for the system performance assessment of the Yucca Mountain Site Characterization Project defines a scenario as a well-posed problem connecting an initiating event with radionuclide release to the accessible environment by a logical and physically possible combination or sequence of features, events, and processes. Drawing on the advice and assistance of the Project`s principal investigators (PIs), a collection of release scenarios initiated by the nominal ground-water flow occurring in the vicinity of the potential Yucca Mountain high-level-waste repository is developed and described in pictorial form. This collection of scenarios is intended to provide a framework to assist PIs in recognizing essential field and calculational analyses, to assist performance assessment in providing guidance to site characterization, and to continue the effort to exhaustively identify all features, events, and processes important to releases. It represents a step in the iterative process of identifying what details of the potential site are important for safe disposal. 67 refs.

Barr, G.E.; Hunter, R.L.; Dunn, E. [Sandia National Labs., Albuquerque, NM (United States); Flint, A. [Geological Survey, Mercury, NV (United States)

1995-03-01T23:59:59.000Z

170

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

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

171

Anticipated Degradation Modes of Metallic Engineered Barriers for High-Level Nuclear Waste Repositories  

Science Journals Connector (OSTI)

Unsaturated repositories: They are located above the water table (such as the initially designed Yucca Mountain, United States). The EBS does not...5

Martín A. Rodríguez

2014-03-01T23:59:59.000Z

172

1 INTRODUCTION In order to demonstrate the feasibility of a radioactive waste repository in claystone  

E-Print Network (OSTI)

1 INTRODUCTION In order to demonstrate the feasibility of a radioactive waste repository in claystone formations, the French national radioactive waste management agency (ANDRA) started in 2000

Boyer, Edmond

173

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

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

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

174

Microbial activity of trench leachates from shallow-land, low-level radioactive waste disposal sites.  

Science Journals Connector (OSTI)

...samples collected from disposal sites at Maxey Flats, Ky., and West...trenches at the disposal sites of Maxey Flats, Ky., West Valley...trench water at the Maxey Flats low-level radioactive waste disposal site, p. 747-761...

A J Francis; S Dobbs; B J Nine

1980-07-01T23:59:59.000Z

175

Generic Repository Concepts and Thermal Analysis for Advanced Fuel Cycles  

SciTech Connect

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.

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

2011-01-01T23:59:59.000Z

176

MONITORED GEOLOGIC REPOSITORY LIFE CYCLE COST ESTIMATE ASSUMPTIONS DOCUMENT  

SciTech Connect

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

R.E. Sweeney

2001-02-08T23:59:59.000Z

177

Building of multilevel stakeholder consensus in radioactive waste repository siting  

SciTech Connect

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)

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

2007-07-01T23:59:59.000Z

178

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

SciTech Connect

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.

Barr, G.E.; Borns, D.J. [Sandia National Labs., Albuquerque, NM (United States); Fridrich, C. [Geological Survey, Lakewood, CO (United States)

1996-10-01T23:59:59.000Z

179

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

SciTech Connect

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)

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

2013-07-01T23:59:59.000Z

180

Factors limiting microbial growth and activity at a proposed high-level nuclear repository, yucca mountain, nevada.  

Science Journals Connector (OSTI)

...High-Level Nuclear Repository, Yucca Mountain, Nevada TL Kieft WP Kovacik Jr...part of the characterization of Yucca Mountain, Nev., as a potential repository...from nine sites along a tunnel in Yucca Mountain. Microbial abundance was generally...

T L Kieft; W P Kovacik; D B Ringelberg; D C White; D L Haldeman; P S Amy; L E Hersman

1997-08-01T23:59:59.000Z

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


181

Prepared in cooperation with the Inyo County, California, Yucca Mountain Repository Assessment Office  

E-Print Network (OSTI)

Prepared in cooperation with the Inyo County, California, Yucca Mountain Repository Assessment County, California, Yucca Mountain Repository Assessment Office #12;U.S. Department of the Interior KEN Office Geologic Map of the southern Funeral Mountains including nearby Groundwater Discharge Sites

Fleskes, Joe

182

Investigations to site a radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4  

E-Print Network (OSTI)

Investigations to site a radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4 Radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4 s the UK radioactive waste legacy comprises difficult material which is complex, of mixed origin

183

Normalized Access to Ontology Repositories Kim Viljanen, Jouni Tuominen, Eetu Makela and Eero Hyvonen  

E-Print Network (OSTI)

the best matching concepts for her needs. 1http://bioportal.bioontology.org/ 2http://onki.fi 3http://ontolog.cimNormalized Access to Ontology Repositories Kim Viljanen, Jouni Tuominen, Eetu M¨akel¨a and Eero Hyv http://www.seco.tkk.fi/, firstname.lastname@aalto.fi Abstract--Ontology repositories, such as NCBO

Hyvönen, Eero

184

CVS-Vintage: A Dataset of 14 CVS Repositories of Java Software  

E-Print Network (OSTI)

CVS-Vintage: A Dataset of 14 CVS Repositories of Java Software Martin Monperrus and Matias Martinez INRIA Technical Report, 2012. Abstract This paper presents a dataset of 14 CVS repositories of Java applications. This dataset aims at supporting the replication of early papers in the field of software

Paris-Sud XI, Université de

185

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

E-Print Network (OSTI)

framework of the study The concept for long term storage of high-level radioactive waste in France under this repository concept with the aim to ensure its long-term safety and its reversibility. In particular, the repository concept requires a minimum containment time of 1000 years. The long-term safety assessment

Paris-Sud XI, Université de

186

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

187

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

E-Print Network (OSTI)

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

Heflin, Jeff

188

Dessicant materials screening for backfill in a salt repository  

SciTech Connect

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.

Simpson, D.R.

1980-10-01T23:59:59.000Z

189

Salt Repository Project waste emplacement mode decision paper: Revison 1  

SciTech Connect

This paper provides a recommendation as to the mode of waste emplacement to be used as the current basis for site characterization activity for the Deaf Smith County, Texas, high level nuclear waste repository site. It also presents a plan for implementing the recommendation so as to provide a high level of confidence in the project's success. Since evaluations of high-level waste disposal in geologic repositories began in the 1950s, most studies emplacement in salt formations employed the vertical orientation for emplacing waste packages in boreholes in the floor of the underground facility. This orientation was used in trials at Project Salt Vault in the 1960s. The Waste Isolation Pilot Plant (WIPP) has recently settled on a combination of vertical and horizontal modes for various waste types. This paper analyzes the information available and develops a project position upon which to base current site characterization activities. The position recommended is that the SRP should continue to use the vertical waste emplacement mode as the reference design and to carry the horizontal mode as a ''passive'' alternative. This position was developed based upon the conclusions of a decision analysis, risk assessment, and cost/schedule impact assessment. 52 refs., 6 figs., 1 tab.

Not Available

1987-08-01T23:59:59.000Z

190

Immersion studies on candidate container alloys for the Tuff Repository  

SciTech Connect

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.

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

1991-05-01T23:59:59.000Z

191

EM Gains Insight from Germany on Salt-Based Repositories | Department of  

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

Gains Insight from Germany on Salt-Based Repositories Gains Insight from Germany on Salt-Based Repositories EM Gains Insight from Germany on Salt-Based Repositories December 14, 2011 - 12:00pm Addthis Participants in the workshops in Germany toured Asse II, one of Germany’s two salt-based repositories, to gain insights into that facility’s technical challenges and proposed solutions. Pictured, left to right, are an Asse II employee, Bernhard Kienzler of the Karlsruhe Institute of Technology, CBFO Chief Scientist Roger Nelson, CBFO International Programs Manager Dr. Abraham Van Luik, and Andrew Wolfsberg, Acting Deputy Division Leader for Earth and Environmental Sciences at Los Alamos National Laboratory. Participants in the workshops in Germany toured Asse II, one of Germany's two salt-based repositories, to gain insights into that facility's

192

Ca Isotope Effects in Orgueil Leachates and the Implications for the Carrier Phases of 54Cr Anomalies  

Science Journals Connector (OSTI)

Primitive meteorites contain small 40Ca excesses, in addition to rare anomalies in 48Ca. Refractory inclusions from Vigarano and Allende have larger 40Ca and resolvable 48Ca anomalies. These results imply that Ca isotopic heterogeneities were still present in the early solar system at both the mineral and whole-rock scale. The absence of correlated Ca isotope anomalies in leachates from the CI1 chondrite Orgueil containing large 54Cr anomalies has implications on the origin of the Cr anomalies. 54Cr has to be produced either in massive stars during s-process nucleosynthesis without accompanying 48Ca or in particular zones in the rare Type Ia supernovae. In the latter case, 54Cr has been produced in a zone predominantly enriched in Cr and 54Cr and not mixed with other zones, or 54Cr has been produced together with other neutron-rich nuclides and there has been subsequent decoupling of this material in the star, in the solar system, or in the laboratory.

Frederic Moynier; Justin I. Simon; Frank A. Podosek; Bradley S. Meyer; Joyce Brannon; Donald J. DePaolo

2010-01-01T23:59:59.000Z

193

Collecting Fluorescent Minerals  

Science Journals Connector (OSTI)

Good fluorescent mineral collections are the result of constant study and diligent search for superior material. As in the development of mineral collections generally, purchase and trade provide rewarding ave...

Manuel Robbins

1983-01-01T23:59:59.000Z

194

Final Systems Development Report for the Clark County Socioeconomic Impact Assessment of the Proposed High-Level Nuclear Waste Repository at Yucca Mountain, NV  

SciTech Connect

The Systems Development Report represents the third major step in the Clark County Socioeconomic Impact Assessment of the Proposed High-Level Nuclear Waste Repository at Yucca Mound Nevada. The first of these steps was to forge a Research Design that would serve as a guide for the overall research process. The second step was the construction of the Base Case, the purpose of which was to describe existing conditions in Clark County in the specified analytic areas of Economic-Demographic/Fiscal, Emergency Planning and Management, Transportation and Sociocultural analysis. The base case description will serve as a basis for assessing changes in these topic areas that might result from the Yucca Mountain project. These changes will be assessed by analyzing conditions with and without repository development in the county. Prior to performing such assessments, however, the snapshot type of data found in the base case must be operationalized or systematized to allow for more dynamic data utilization. In other words, a data system that can be used to analyze the consequences of the introduction of different variables (or variable values) in the Clark County context must be constructed. Such a system must be capable of being updated through subsequent data collection and monitoring efforts to both provide a rolling base case and supply information necessary to construct trend analyses. For example, during the Impact Assessment phase of the study process, the without repository analysis is accomplished by analyzing growth for the county given existing conditions and likely trends. These data are then compared to the with Yucca Mountain project conditions anticipated for the county. Similarly, once the emergency planning management and response needs associated with the repository are described, these needs will be juxtaposed against existing (and various future) capacity(ies) in order to determine the nature and magnitude of impacts in this analytic area. Analogous tasks will be performed for the other analytic areas detailed in the Base Case and outlined below.

NONE

1992-06-18T23:59:59.000Z

195

Natural vegetation at the proposed Reference Repository Location in southeastern Washington  

SciTech Connect

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.

Rickard, W.H.

1988-02-01T23:59:59.000Z

196

Vegetation Collections Project Page  

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

Vegetation Collections Vegetation Collections Vegetation Collections Overview Vegetation regulates the flow of numerous biogeochemical cycles, most critically those of water, carbon, and nitrogen; it is also of great importance in local and global energy balances. Vegetation collections data include: Biomass Biome Characteristics Litter Chemistry and Decomposition Geoecology Nutrient Concentration, Profiles, and Turnover Global Fire Emissions, Vegetation, and Leaf Area Index (LAI) Ecosystem Structure and Function Phenoregions Carbon Flux Vegetation Resources The following resources related to Vegetation Collections are maintained by the ORNL DAAC: Global Leaf Area Index Data Net Primary Production Project Get Vegetation Data Find and order data sets: See list of data sets and download data

197

A Summary of INEEL Calcine Properties Used to Evaluate Direct Calcine Disposal in the Yucca Mountain Repository  

SciTech Connect

To support evaluations of the direct disposal of Idaho National Engineering and Environmental Laboratory calcines to the repository at Yucca Mountain, an evaluation of the performance of the calcine in the repository environment must be performed. This type of evaluation demonstrates, through computer modeling and analysis, the impact the calcine would have on the ability of the repository to perform its function of containment of materials during the repository lifetime. This report discusses parameters that were used in the scoping evaluation conducted in FY 2003. It provides nominal values for the parameters, with explanation of the source of the values, and how the values were modified for use in repository analysis activities.

C. A. Dahl

2003-07-01T23:59:59.000Z

198

Generic repository design concepts and thermal analysis (FY11).  

SciTech Connect

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.

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

2011-08-01T23:59:59.000Z

199

DOE Geothermal Data Repository - Tethering Data to Information: Preprint  

SciTech Connect

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).

Weers, J.; Anderson, A.

2014-02-01T23:59:59.000Z

200

Schematic designs for penetration seals for a reference repository in bedded salt  

SciTech Connect

The isolation of radioactive wastes in geologic repositories requires that man-made penetrations such as shafts, tunnels, or boreholes are adequately sealed. This report describes schematic seal designs for a repository in bedded salt referenced to the straitigraphy of southeastern New Mexico. The designs are presented for extensive peer review and will be updated as site-specific conceptual designs when a site for a repository in salt has been selected. The principal material used in the seal system is crushed salt obtained from excavating the repository. It is anticipated that crushed salt will consolidate as the repository rooms creep close to the degree that mechanical and hydrologic properties will eventually match those of undisturbed, intact salt. For southeastern New Mexico salt, analyses indicate that this process will require approximately 1000 years for a seal located at the base of one of the repository shafts (where there is little increase in temperature due to waste emplacement) and approximately 400 years for a seal located in an access tunnel within the repository. Bulkheads composed of contrete or salt bricks are also included in the seal system as components which will have low permeability during the period required for salt consolidation.

Kelsall, P.C.; Case, J.B.; Meyer, D.; Coons, W.E.

1982-11-01T23:59:59.000Z

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


201

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

SciTech Connect

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

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

2013-07-01T23:59:59.000Z

202

Utility Data Collection Service  

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

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

203

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

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

a Contract to USA Repository a Contract to USA Repository Services for Management and Operating Contractor Support for the Yucca Mountain Project U.S. Department of Energy Awards a Contract to USA Repository Services for Management and Operating Contractor Support for the Yucca Mountain Project October 30, 2008 - 4:14pm Addthis Washington, D.C. -- The U.S. Department of Energy (DOE) today awarded a $2.5 billion management and operating (M&O) contract to USA Repository Services (USA-RS), a wholly-owned subsidiary of the URS Corporation. USA-RS will be supported by principal subcontractors: Shaw Environmental and Infrastructure, Inc., and AREVA Federal Services, Inc. "If we are to meet growing energy demand and slow the growth of greenhouse gas emissions, nuclear power must be a larger part of our energy mix; it is

204

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

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

U.S. Department of Energy Awards a Contract to USA Repository U.S. Department of Energy Awards a Contract to USA Repository Services for Management and Operating Contractor Support for the Yucca Mountain Project U.S. Department of Energy Awards a Contract to USA Repository Services for Management and Operating Contractor Support for the Yucca Mountain Project October 30, 2008 - 4:14pm Addthis Washington, D.C. -- The U.S. Department of Energy (DOE) today awarded a $2.5 billion management and operating (M&O) contract to USA Repository Services (USA-RS), a wholly-owned subsidiary of the URS Corporation. USA-RS will be supported by principal subcontractors: Shaw Environmental and Infrastructure, Inc., and AREVA Federal Services, Inc. "If we are to meet growing energy demand and slow the growth of greenhouse gas emissions, nuclear power must be a larger part of our energy mix; it is

205

This fact sheet describes the repository design activities the U.S. Department o  

Office of Legacy Management (LM)

repository design activities the U.S. Department of Energy is conducting at the Monticello repository design activities the U.S. Department of Energy is conducting at the Monticello Mill Tailings Site in Monticello, Utah. These activities are being performed in accordance with Federal and State environ- mental laws. Background The purpose of the Monticello cleanup projects is to minimize the risks to the public and the environment from exposure to mill tailings and the radon gas they produce. The Monticello Mill Tailings Site cleanup remedy was se- lected in the Record of Decision in August 1990 and recon- firmed in December 1994. It includes permanent disposal of mill tailings and contaminated materials in a repository to be constructed on U.S. Department of Energy (DOE)- owned land south of the millsite in Monticello, Utah. The repository will hold approximately 2.6 to 3.0 million cubic

206

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

Office of Environmental Management (EM)

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

207

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

E-Print Network (OSTI)

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 regarding these sculptures...

Pedersen, Hillary

2010-12-31T23:59:59.000Z

208

Performance Assessment Modeling for Savannah River Glass HLW Disposal in a Potential Repository at Yucca Mountain  

Science Journals Connector (OSTI)

Performance assessment (PA) simulates the long-term performance of a conceptual geological repository for nuclear waste or the performance of a subsystem such as the engineered barrier system (drifts, waste pa...

W. J. O’Connell; W. L. Bourcier; J. Gansemer…

1998-01-01T23:59:59.000Z

209

Preservation of the Texas Agricultural Experiment Station Bulletin in the Digital Repository  

E-Print Network (OSTI)

digital repository, through a case study of a project at Texas A&M University Libraries to digitize Texas Agricultural Experiment Station Bulletins. It is hoped that a dispersed network of similar agricultural materials in all the various land grant...

McGeachin, Robert B.

2010-04-23T23:59:59.000Z

210

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

SciTech Connect

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

Paul Wilson

2009-11-02T23:59:59.000Z

211

Risk-informing decisions about high-level nuclear waste repositories  

E-Print Network (OSTI)

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. ...

Ghosh, Suchandra Tina, 1973-

2004-01-01T23:59:59.000Z

212

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

E-Print Network (OSTI)

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. ...

Driscoll, Michael J.

1988-01-01T23:59:59.000Z

213

Morsleben Nuclear Waste Repository Probabilistic Safety Assessment of the Long-Term Safety  

Science Journals Connector (OSTI)

The probabilistic safety assessment for a radioactive waste repository in a former salt mine is presented. Even with a simplified model, the number of parameters is high. Uncertainties in the parameter values ...

Georg Resele; Matthias Niemeyer…

2004-01-01T23:59:59.000Z

214

Shale Rocks as Nuclear Waste Repositories: Hydrothermal Reactions with Glass, Ceramic and Spent Fuel Waste Forms  

Science Journals Connector (OSTI)

The objectives of various contributions from this laboratory have been to simulate “worst case” situations, given a proposed choice of waste form, repository rock, and waste loading/waste age. The “worst case”...

W. Phelps Freeborn; Michael Zolensky…

1980-01-01T23:59:59.000Z

215

Planned Emplacement of Magnesium Oxide in the WIPP Repository 1.0 Overview  

E-Print Network (OSTI)

Planned Emplacement of Magnesium Oxide in the WIPP Repository 1.0 Overview In December 2002 received approval to dispose of AMWTF's supercompacted waste provided magnesium oxide (MgO), the approved

216

Adapting Dry Cask Storage for Aging at a Geologic Repository  

SciTech Connect

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.

C. Sanders; D. Kimball

2005-08-02T23:59:59.000Z

217

Rock mass modification around a nuclear waste repository in welded tuff  

SciTech Connect

This report presents the results of numerical analyses to estimate the extent of rock mass modification resulting from the presence of a High Level Waste (HLW) repository. Changes in rock mass considered are stresses and joint deformations resulting from disposal room excavation and thermal efffects induced by the heat generated by nuclear waste. rock properties and site conditions are taken from the Site Characterization Plan Conceptual Design Report for the potential repository site at Yucca Mountain, Nevada. Analyses were conducted using boundary element and distinct element methods. Room-scale models and repository-scale models were investigated for up to 500 years after waste emplacement. Results of room-scale analyses based on the thermoelastic boundary element model indicate that a zone of modified rock develops around the disposal rooms for both vertical and horizontal waste emplacement. This zone is estimated to extend a distance of roughly two room diameters from the room surface. Results from the repository-scale model, which are based on the thermoelastic boundary element model and the distinct element model, indicate a zone with modified rock mass properties starting approximately 100 m above and below the repository, with a thickness of approximately 200 m above and 150 m below the repository. Slip-prone subhorizontal features are shown to have a substantial effect on rock mass response. The estimates of rock mass modification reflect uncertainties and simplifying assumptions in the models. 32 refs., 57 figs., 1 tab.

Mack, M.G.; Brandshaug, T.; Brady, B.H.

1989-08-01T23:59:59.000Z

218

Two-stage repository development at Yucca Mountain: an engineering feasibility study  

SciTech Connect

The Nuclear Waste Policy Act of 1982 requires that the first repository for disposal of high-level radioactive waste be ready to receive waste by January 31, 1998. The preliminary designs of candidates for the first repository include a single waste-handling building constructed in one stage. After considering possible approaches to repository construction, the Department of Energy has proposed in its draft Mission Plan to construct the first repository in two steps to increase confidence in meeting the 1998 deadline. Therefore, the Department of Energy has requested the preparation of this engineering study to verify the validity of the two-stage approach to repository construction. This approach involves concurrent construction of two waste-handling buildings. The first would be completed in time to accept the equivalent of 400 MTU/y of waste by January 31, 1998. It would operate for 5 y, during which time construction of a full-capacity, 3000-MTU/y waste-handling building would be completed. The design includes six accesses to the underground facility: four vertical shafts and two ramps. The principal conclusion derived from this study is that two-stage repository construction can allow receipt and disposal of the 400 MTU/y of waste by January 31, 1998. Four alternate concepts have been explored to determine whether savings in costs could be accomplished. All four alternate concepts appear technically feasible and are potentially more cost effective than the reference approach.

MacDougall, H.R. (comp.)

1985-12-01T23:59:59.000Z

219

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

SciTech Connect

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.

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

1985-11-01T23:59:59.000Z

220

Water, Vapor, and Salt Dynamics in a Hot Repository  

SciTech Connect

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

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

2007-07-01T23:59:59.000Z

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


221

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

E-Print Network (OSTI)

SALAUN, Franck GIROT, RĂ©my CHIERAGATTI - Toward a better understanding of tool wear effect through understanding of tool wear effect through a comparison between experiments and SPH numerical modelling of machining hard materials M. Calamaz a , J. Limido b , M. Nouari c,*, C. Espinosa b , D. Coupard a , M

Paris-Sud XI, Université de

222

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

E-Print Network (OSTI)

to this article : DOI : 10.1016/j.wear.2012.12.026 URL : http://dx.doi.org/10.1016/j.wear.2012.12.026 To cite, Alfazazi A study on PDC drill bits quality. (2013) Wear, vol. 298-299 . pp. 32-41. ISSN 0043-1648Any-oatao@listes-diff.inp- toulouse.fr hal-00919880,version1-17Dec2013 Author manuscript, published in "Wear vol. 298-299 (2013) pp

Paris-Sud XI, Université de

223

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

E-Print Network (OSTI)

Filho 3000 Campus Universitário Lagoa Nova Br-59078 Natal Brazil E-mail: reidson@ct.ufrn.br Abstract functional level, but (amongst other things) using less materials or fewer energy in the manufacturing process, favouring the use of higher renewable resources, optimising design for limiting maintenance

Paris-Sud XI, Université de

224

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

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phenomenon, provoking lamp arc instability, known as Acoustic Resonance (AR) [1-2]. Nowadays, commonly used in an HPS Lamp. (2013) IEEE Transactions on Industry Applications, vol. 49 (n° 3). pp. 1154-1160. ISSN 0093 Lamp A. Toumi, L. Chhun, S. Bhosle, G. Zissis and P. Maussion Université de Toulouse; UPS-INPT; LAPLACE

Mailhes, Corinne

225

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

E-Print Network (OSTI)

of the synthetic uranium-doped analogues The uranium-doped synthetic apatites were synthetized by a high t Synthetic analogues of poor-silicated natural apatites have been doped with uranium. These minerals have temperature solid­solid reactive sintering [6,7]. The uranium has been introduced by reacting crushed natural

Mailhes, Corinne

226

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

E-Print Network (OSTI)

fields: flow boiling heat transfer is common in power plants (energy production or conversion. Introduction Two-phase thermal systems are broadly used in various industrial applications and engineering, two-phase thermal management systems are considered as extremely beneficiai for space applications

Boyer, Edmond

227

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

E-Print Network (OSTI)

-oatao@listes-diff.inp-toulouse.fr hal-00912372,version1- #12;Dynamique de bulles traversant l'interface s´eparant deux liquides Romain of air bubbles through an initially flat horizontal interface separating two Newtonian liquids. We use) and a Cahn-Hilliard model coupled with the Navier-Stokes equations. Key words: Bubbles / triphasic flow

Boyer, Edmond

228

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

E-Print Network (OSTI)

determined the contribution of the bioanode to the COD removal. Electrochemical COD removal was proportional to HRT. Electrochemical COD removal obeyed a Michaelis­Menten law with the COD outlet. Keywords/SCE, without any addition of nutriment or substrate. The bioanodes were charac- terized in 3-electrode set

Paris-Sud XI, Université de

229

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

E-Print Network (OSTI)

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

Mailhes, Corinne

230

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

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by ADEME. This paper presents a description of the hydrodynamic into a CFB according to experimental mea mathematical models are able to predict the complex gas-solid behavior in the CFB and highlight the large

Mailhes, Corinne

231

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

E-Print Network (OSTI)

-Helmholtz instability in the presence of variable viscosity for mudflow resuspension in estuaries. (2014) Environmental in the presence of variable viscosity for mudflow resuspension in estuaries Alice Harang, Olivier Thual, Pierre pronounced. In all cases, we show that the thickness of the mixing layer (and thus resuspension) is increased

Mailhes, Corinne

232

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

E-Print Network (OSTI)

-induced vibration. Key words: vortex shedding, wakes, wake­structure interactions 1. Introduction Flow for their ubiquity in nature and their serious implications in wind and ocean engineering. Email address. The focus in the field has been on bodies with circular cross-sections, a canonical bluff body with an axial

Mailhes, Corinne

233

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

E-Print Network (OSTI)

shedding, wakes, wake­structure interactions 1. Introduction Flow-induced vibration (FIV) of bluff bodies in nature and their serious implications in wind and ocean engineering. Email address for correspondence and fundamental studies. The focus in the field has been on bodies with circular cross-sections, a canonical bluff

Boyer, Edmond

234

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

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the melting profile of vegetable oils blends used in food industry. The present work uses a computational reaction (CI) for different formulations using palm oil (PO), sunflower oil (SFO) and palm kernel oil (PKO melting-related properties of vegetable oils (VOs) can be found in the literature. Most of them use non

Mailhes, Corinne

235

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

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] have first achieved the direct reduction of TiO2 into Ti in a molten chloride salt com- posed of CaCl2 salts (LiCl or CaCl2), for different purposes: high purity Si production [2], spent nuclear fuel in chloride salts [1,11­13]. In molten CaCl2, its reduction pathway has been proposed [14] and several

Mailhes, Corinne

236

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

E-Print Network (OSTI)

this version : Maud RIO, Tatiana REYES, Lionel ROUCOULES - A framework for ecodesign: an interface between LCA (2010)" #12;A FRAMEWORK FOR ECODESIGN: AN INTERFACE BETWEEN LCA AND DESIGN PROCESS Maud RIO1 , Tatiana Keywords: product design, eco-design, LCA, CAX modelling Abstract Integrating environmental aspects

Boyer, Edmond

237

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

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as witnessed by the arrivalof thesecondgeneration of thin film solarcells, whichprovide drastic improvements

Paris-Sud XI, Université de

238

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depleted, SOI, TID. I. INTRODUCTION I NCREASING needs for high-TID tolerant electronic sys- tems have been revealed the need for enhanced radiation tolerance of electronic systems, both for use in future nuclear facilities and for the new security systems to be implemented in existing nuclear power plants, spent-fuel

Mailhes, Corinne

239

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interesting materials processings which can enhance the corrosion and wear resistance of ZE41 alloy. LSMT has magnesium alloy for corrosion resistance and microhardness improvement - Optics and Lasers in Engineering magnesium alloy for corrosion resistance and microhardness improvement Walid Khalfaoui a , Eric Valerio a

240

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and Ibrahim, 2006), oxide layers obtained by micro-arc oxidation (Shrestha et al., 2006) or anodic films's instruments, especially by outgassing. The anodic film is grown by electrochemical oxidation of the metal

Mailhes, Corinne

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241

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-Sabatier, F 31062 Toulouse cedex 4, France Abstract Oxides based on a-alumina and containing various amounts mixed-oxalates. Selective reduction of the oxides in a H2±CH4 atmosphere produces nano- metric Fe¯uence of the Fe content and the reduction temperature on the composition and micro/ nanostructure

Boyer, Edmond

242

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-deposited version published in: http://sam.ensam.eu Handle ID: .http://hdl.handle.net/10985/7514 To cite and more specially the fatigue damage mechanisms observed (with material treated and no treated) under Kitagawa type diagram, which in this case explains the relationship between the influence of the heat

Paris-Sud XI, Université de

243

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-deposited version published in: http://sam.ensam.eu Handle ID: .http://hdl.handle.net/10985/7598 To cite depending on workpiece required quality, material hardness and cutting conditions. In this way, in order have a negative effect on dimensional produced work piece accuracy. Lobe stability diagram is a chart

Boyer, Edmond

244

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of Isothermal or Non-isothermal Adsorption in a Pellet: Application to Adsorption Heat Pumps. Chinese Journal of Isothermal or Non-isothermal Adsorption in a Pellet: Application to Adsorption Heat Pumps Ludovic Montastruc1 of sorption is controlled entirely by heat transfer. If the adsorption process is to be used as a heat pump

Mailhes, Corinne

245

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- alysts for the reduction of nitric oxide at low temperature with carbon monoxide as reducing agent [1 Adsorption of nitric oxide and temperature programmed desorption on nonstoichiometric nickel- copper-oatao@listes-diff.inp-toulouse.fr #12;Adsorption of nitric oxide and temperature programmed desorption on nonstoichiometric nickel

Mailhes, Corinne

246

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and Ecotechnologies Division - Wasoe and Raw Materials & Recycling Uni~ 3 Avenue Qaude Guillemin, BP36009, Orléans in revised form 7 November 2013 Accepted 17 November 2013 Available online 1 December 2013 Keywords: Concrete

Paris-Sud XI, Université de

247

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prepared by combustion synthesis and characterized in detail in a companion paper. Depending, octahedral Fe3+ ions, Fe3+ clusters, and MgFe2O4-like nanoparticles. Upon reduction during heating at 5 °C of carbon, involve the catalytic decomposition of a carbonaceous gas (hydrocarbon or carbon monoxide

Paris-Sud XI, Université de

248

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. This is the scope of the paper. For the design specifications of a low speed marine propulsion machine are widely used in electrical marine propulsion for reasons such as reliability, smooth torque specifications of a marine propulsion F. Scuiller is with the Research Institute of Naval Academy, BCRM Brest

249

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@ecole-navale.fr, http://www.ecole-navale.fr Abstract: - Multi-phase motors are widely used in marine propulsion application, multi-phase PM motor, multi-machine, design. 1 Introduction Electric marine propulsion widely are then compared to examine numerically which improvements can be practically obtained. Key-Words: - marine

Paris-Sud XI, Université de

250

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et al., 1999; Flahaut et al., 2003), electric arc discharge (Journet et al., 1997), or laser ablation, such as amorphous or graphitic. Finally, specific physico-chemical, mechanical, thermal or electrical properties can

Mailhes, Corinne

251

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and the quantity of products. 1. Introduction In addition to the laser evaporation and electric arc discharge

Boyer, Edmond

252

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, The Netherlands Keywords: PEM fuel cell Gas diffusion layer Two-phase flow Pore network model Degradation Performance loss of proton exchange membrane fuel cell due to hydrophobicity loss in gas diffusion layer membrane fuel cell due to hydrophobicity loss in gas diffusion layer: Analysis by multiscale approach

Paris-Sud XI, Université de

253

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specification. In the next phase of research, investigation will be conducted to integrate sustainability with the challenge of designing sustainable products and manufacturing processes. Many sustainable development) design-for-X principles and design for sustainability, c) end-of-life studies, and d) energy efficiency

Boyer, Edmond

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phase of research, investigation will be conducted to integrate sustainability information model is confronted with the challenge of designing sustainable products and manufacturing processes. The ones who and design for sustainability [16-25]; c) end-of-life studies [26-31]; and d) energy efficiency monitoring

Paris-Sud XI, Université de

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of research, investigation will be conducted to integrate sustainability information model and existing through economic growth (Baldwin 05). Industry is confronted with the challenge of designing sustainable for sustainability, c) end-of-life studies, and d) energy efficiency monitoring and studies. But it remains a lack

Paris-Sud XI, Université de

256

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Science and Technology, 2011, vol. 71, n° 3, pp. 289-296. ISSN 0266-3538 Any correspondence concerning influence on experimental results is also underlined. 1. Introduction Woven composites are advanced materials that are commonly used in aerospace applications. Their use is interesting owing

Mailhes, Corinne

257

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. This is an author-deposited version published in : http://oatao.univ-toulouse.fr/ Eprints ID : 11643 To link , Mn2 and Mn3 cations, respectively, during the oxides synth- esis in air at low temperature. Upon

Paris-Sud XI, Université de

258

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. This is an author-deposited version published in : http://oatao.univ-toulouse.fr/ Eprints ID : 11643 To link, during the oxides synth- esis in air at low temperature. Upon heating in Ar, these nonstoichiometric

259

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of 10­15 wt% of nanoclays.[7,8] This tortuosity effect can be advantageously combined with a nucleation

Boyer, Edmond

260

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-deposited version published in: http://sam.ensam.eu Handle ID: .http://hdl.handle.net/10985/8454 To cite t The present work deals with the numerical calculation of the Stokes-type drag undergone by a cylindrical is zero for Newtonian and dilatant fluids. But in the bounded one, the Stokes-type regime is recovered

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261

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/or to the electric machine [7-10]. Specific configurations of three-phase and multi-phase drives have been-Tolerant Operation of an Open-End Winding Five-Phase PMSM Drive with Inverter Faults - - 2013 Any correspondence-Tolerant Operation of an Open-End Winding Five-Phase PMSM Drive with Inverter Faults Fabien Meinguet, Ngac-Ky Nguyen

Paris-Sud XI, Université de

262

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ďż˝ Diversity (human) ďż˝ Identity ďż˝ Relation ďż˝ Personhood ďż˝ Philosophy (analytical) ďż˝ Transhumanism 1

Paris-Sud XI, Université de

263

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of the electromagnetic interference between the macrocell and femtocell tier, as well as between femtocells will play

264

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in porous media. (2013) International Journal of Heat and Mass Transfer, vol. 63 . pp. 401-413. ISSN 0017 with solids (plates, rod bundles, . . .). For such devices, fine scale simulations are still unachievable-oatao@listes-diff.inp-toulouse.fr hal-00952032,version1-26Feb2014 Author manuscript, published in "International Journal of Heat

Boyer, Edmond

265

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in porous media. (2013) International Journal of Heat and Mass Transfer, vol. 63 . pp. 401-413. ISSN 0017 connected with regions densely occupied with solids (plates, rod bundles, . . .). For such devices, fine. A two-scale analysis highlights energy transfers between macro- scopic and sub-filter kinetic energies

Mailhes, Corinne

266

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b IMFT-UMR 5502, allée du Professeur Camille Soula, 31400 Toulouse, France Keywords: Gas turbines Turbulent non-perfectly premixed combustion Large eddy simulation Reduced chemistry Thermo-acoustic of mean and RMS fields of temperature, species, velocities as well as mixture fraction pdfs and unsteady

Paris-Sud XI, Université de

267

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Soula, 31400 Toulouse, France Keywords: Gas turbines Turbulent non-perfectly premixed combustion Large eddy simulation Reduced chemistry Thermo-acoustic instabilities a b s t r a c t This paper investigates of temperature, species, velocities as well as mixture fraction pdfs and unsteady activity for two regimes

Mailhes, Corinne

268

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generated during biorefinery of sunflower whole plant in a twin-screw extruder Philippe Evon a,b,*, Virginie of sunflower (Helianthus annuus L) whole plant in a co-rotating (Clextral BC 45, France) twin-screw extruder thermal insulation fiberboards from cake generated during biorefinery of sunflower whole plant in a twin-screw

Boyer, Edmond

269

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to poly(lactic acid) by twin-screw extrusion. The influence of extruder screw speed and of total feeding screw speeds, residence time in the extruder and blend viscosity were reduced. However, such conditions.01.026 To cite this version : Gamon, guillaume and Evon, Philippe and Rigal, Luc Twin-screw extrusion impact

Boyer, Edmond

270

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masterbatches using a twin-screw extruder was first applied to produce several formulations, which were

Paris-Sud XI, Université de

271

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Relevance of lab-scale conical twin-screw extruder for thermoplastic STARCH/PLA blends rheology study. (2010th Annual Meeting, Banff : Canada (2010)" #12;RELEVANCE OF LAB-SCALE CONICAL TWIN-SCREW EXTRUDER be realised in a twin screw extruder (Martin et al. 2003). Twin-screw extruders range widely from lab-scale (g

Paris-Sud XI, Université de

272

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this version : Evon, Philippe and Colas, Dorothée and Pontalier, Pierre-Yves and Rigal, Luc The twin-screw-oatao@listes-diff.inp-toulouse.fr #12;The twin-screw extrusion technology, an original solution for the extraction of proteins from Keywords: Twin-screw extrusion, Protein extraction, Sunflower, Alfalfa. Twin-screw extrusion has been used

Mailhes, Corinne

273

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draining forested watersheds. Due to several ecological factors, such as light limitation by the riparian streams is generally heterotrophic [16, 67]. Leaf litter, which represents an important fraction the palatability of leaf detritus, thus providing a more suitable food source for shredders which further

Mailhes, Corinne

274

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and Mattielli, Nadine and Le Roux, Gaël and Fagel, Nathalie Atmospheric lead and heavy metal pollution records-oatao@listes-diff.inp-toulouse.fr hal-00987398,version1- #12;Atmospheric lead and heavy metal pollution records from a Belgian peat bog mark in Europe's soils in the form of heavy metals. The fallout of these anthropogenic aerosols mix

Paris-Sud XI, Université de

275

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growth rate [1,2] and the most common base material for photovoltaic cell is Solar-AES analysis: the recovered Si purity was assumed to be higher than 99.99%. 1. Introduction Photovoltaic

Mailhes, Corinne

276

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-Helmholtz instability in the presence of variable viscosity for mudflow resuspension in estuaries. (2014) Environmental-Helmholtz instability in the presence of variable viscosity for mudflow resuspension in estuaries Alice Harang, Olivier, we show that the thickness of the mixing layer (and thus resuspension) is increased by high viscosity

Paris-Sud XI, Université de

277

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of renewable energies [2]. Considering these advantages, although, recently there was a fast growth in solar renewable energies which less than 1% of that is from solar energy [3], [4]. Therefore, solar energy Solar (FTS) technology is a new generation of concentrat- ed solar plants to use the thermal energy

Paris-Sud XI, Université de

278

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that included lakes, ponds, pools and bogs, but most of the chapter focussed upon the larger bodies of water frameworks and the conservation planning and D. Boix (lEI) Institute of Aquatic Ecology, University of Girona, 17071 Girona, Catalonia, Spain e-mail: dani.boix@udg.edu J. Biggs Pond Conservation, Oxford, UK R

Paris-Sud XI, Université de

279

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catalysis at the anode. To develop a hydrogen evolution cathode that can work at neutral pH remains a major ( 2010) Combining phosphate species and stainless steel cathode to enhance hydrogen evolution-oatao@inp-toulouse.fr #12;Combining phosphate species and stainless steel cathode to enhance hydrogen evolution in microbial

Mailhes, Corinne

280

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potentiel pour les applications de r´ecup´eration de chaleur `a basse temp´erature, car ils permettent d of water working fluid. ORCs have been largely studied for their relatively high efficiency [9] at such unfavorable conditions. ORC technology has been applied in geothermal [11] and biomass [4] fired power plants

Boyer, Edmond

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281

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) Electrical behaviour, characteristics and properties of anodic aluminium oxide films coloured by nickel;Electrical behaviour, characteristics and properties of anodic aluminium oxide films coloured by nickel anodic films on 1050 aluminium sub- strate were coloured by AC electrodeposition of nickel. Several

Mailhes, Corinne

282

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anodic polarization in cryolite-alumina melt. (2014) Corrosion Science, vol. 79 . pp. 159-168. ISSN 0010-oatao@listes-diff.inp-toulouse.fr #12;Layer growth mechanisms on metallic electrodes under anodic polarization in cryolite-alumina melt salts B. Polarization C. High-temperature corrosion a b s t r a c t The anodic behavior of Fe, Ni, Co

Mailhes, Corinne

283

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Ordered anodic aluminium oxide (AAO) films were first prepared by anodising in a phosphoric acid. Keywords: anodic aluminium film; anodising; porous template; chemical characterisation; thermal stability to the possibility of experimentally observing the porosity inside the anodic film using microscopic techniques

Mailhes, Corinne

284

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. Influence of anodizing process on fatigue life of a machined aluminium alloy. Procedia Engineering, 2010 of Anodizing Process on Fatigue Life of Machined Aluminium Alloy M. Shahzad * - M. Chaussumier - R. Chieragatti March 2010 Abstract In order to investigate the coupled effects of machining and anodizing processes

Mailhes, Corinne

285

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7175 T7351 by anodizing in sulphuric acid electrolyte. Surface and Coatings Technology, 2010, vol. 205 expansion of porous films prepared on AA7175 T7351 by anodizing in sulphuric acid electrolyte Yann Goueffon online 14 October 2010 Keywords: Coefficient of Thermal Expansion Anodic film Cracking Thin film

Mailhes, Corinne

286

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. A fatigue multi-site cracks model using coalescence, short and long crack growth laws, for anodized aluminum, for anodized aluminum alloys M. Chaussumiera, *, M. Shahzadb , C. Mabrub , R. Chieragattib , F. RezaĂŻ that decrease of the fatigue life of aluminium alloys treated with anodization can be explained

Mailhes, Corinne

287

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of Sealed AA2024 T3 Anodized in Sulfuric Acid Electrolytes: Influence of Tartaric Acid. Journal) C521-C529" DOI : 10.1149/1.2969277 #12;FESEM and EIS Study of Sealed AA2024 T3 Anodized in Sulfuric of tartaric acid on anodic film morphology and on corrosion resistance of hydrothermally sealed anodized AA

Paris-Sud XI, Université de

288

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

Boyer, Edmond

289

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of the stratospheric balloons. These balloons are the only vehicles which can stay aloft in the stratosphere

Mailhes, Corinne

290

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containers for their safe storage for long-term periods spanning over thousand years. One of the nucleids silicate, as a permanent medium for the long-term confinement of caesium. A simple loading by mixing caesium issued from recycled nuclear waste. Keywords: Sintering; Leaching process; Nuclear applications 1

Boyer, Edmond

291

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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

Mailhes, Corinne

292

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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

Boyer, Edmond

293

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

Mailhes, Corinne

294

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

Mailhes, Corinne

295

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

Paris-Sud XI, Université de

296

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

Mailhes, Corinne

297

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this version : Shirvany, Reza and Chabert, Marie and Tourneret, Jean-Yves Ship and Oil-Spill Detection Using-oatao@listes.diff.inp-toulouse.fr #12;Ship and Oil-Spill Detection Using the Degree of Polarization in Linear and Hybrid/Compact Dual Member, IEEE Abstract--Monitoring and detection of ships and oil spills using synthetic aperture radar

Mailhes, Corinne

298

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the use of electrochemical batteries. Luckily, environmental energy harvesting provides a solution small and too difficult to capture, solar light is only available outside the aircraft in daylight

Boyer, Edmond

299

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: spectroscopic, chromatographic or thermal detection of stabilizer and its by-products [2,3]. The measurement of phosphites and sulfurs by supposing that stabilizer soluble part disappear by reaction and evaporation ageing. The use of OIT measurement for quantifying stabilizer is also discussed. Kinetic analysis showed

Boyer, Edmond

300

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compounds. Con- cerning the CO2 rich phase, it was observed that the glycerol solubility in CO2, interest in biphasic systems, which couple supercrit- ical CO2 and a conventional liquid solvent have been equilibrium of the CO2/glycerol system: Experimental data by in situ FT-IR spectroscopy and thermodynamic

Mailhes, Corinne

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301

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Durand Fine powders of BaTiO3 are synthesized by hydrothermal processing at 250 °C for 7 h. Two different- zation process. Keywords barium titanate, dielectric properties, hydrothermal synthesis, ceramic, thick

Paris-Sud XI, Université de

302

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of a reduced order model for the control of self-sustained instabilities in cavity flows. (2013) Communication.4208/cicp.300112.100812a Development and Application of a Reduced Order Model for the Control of Self-Sustained by a self-sustained mechanism in which the shear layer impinges on the downstream edge of the cavity

Mailhes, Corinne

303

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.Bouchet@univ-amu.fr, Gilles.Bouchet@univ-provence.fr and climent@imft.fr Abstract Self-sustained oscillations in the sinuous. They belong to the category of flows that can develop self-sustained oscillations. This is the case when a jet

Mailhes, Corinne

304

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an understanding of the mechanism that limits levels for these self sustained vibrations. The concept is exploited/disc interface is responsible for self-sustained vibra- tions in the audible frequency range, known as squeal

Boyer, Edmond

305

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noise,15 and result in the highly undesirable vortex ring state.7 For wind turbines, these helical of helical tip and root vortices in a wind turbine wake. (2013) Physics of Fluids, vol. 25 . pp. 1-16. ISSN vortices in a wind turbine wake Michael Sherry,1,a) Andr´as Nemes,1 David Lo Jacono,1,2 Hugh M. Blackburn,1

Boyer, Edmond

306

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Economic and environmental impacts of the energy source for the utility production system in the HDA of the energy source for the utility production system in the HDA process A. Ouattara a , L. Pibouleau b , C Assessment a b s t r a c t The well-known benchmark process for hydrodealkylation of toluene (HDA) to produce

Paris-Sud XI, Université de

307

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material, or possibility to reeve electric or control cables on core material. Only a few studies have so on materials manufactured with cross-linked fibers. The specific mechanical behavior obtained is discussed

Mailhes, Corinne

308

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

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discharge machining (EDM) on the AISI316L SS white layer microstructure and corrosion resistance of austenitic stainless steels is strongly influenced by the quality of finished surface. EDM machining induces manufactured by high energy density processes like electron beam, laser or electric discharge machining (EDM

Paris-Sud XI, Université de

309

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

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Biodiesel, Transesterification, NIR spectroscopy, Gas chromatography, Ethanol #12;3 1. Introduction Due house effect, alternative fuels for diesel engines have been widely studied during the last decades. Biodiesel, as a renewable alternative diesel fuel, can be derived from vegetable oils, animal fats

Mailhes, Corinne

310

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

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MĂ©tiers ParisTech, 2 bd du Ronceray, Angers, France a r t i c l e i n f o Article history: Received 12 of the increase in the price of energy and because of environ- mental challenges; let us cite for example in conventional oil and gas reserves implies a high level of invest- ments for tertiary recovery techniques [7

311

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

Paris-Sud XI, Université de

312

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of the twentieth century. Group C relate to polychlorinated dioxins and furans (Table 1 and Figure 1 as industrial chemicals C. Polychlorinated dioxins and furans A family of 75 compounds formed as by

Paris-Sud XI, Université de

313

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scale study of chlorination-induced transport property changes of a seawater reverse osmosis membrane of a seawater reverse osmosis membrane Axel Ettori a,b,c , Emmanuelle Gaudichet-Maurin c , Pierre Aimar a, BP 76, 78603 Maisons-Laffitte cedex, France H I G H L I G H T S A 4" spiral wound reverse osmosis

Paris-Sud XI, Université de

314

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of coordinated field studies to capture interactions and feedback in the local landscape/land-use system. Our level depended to a great extent on interactions between farm household behaviours and the spatial Modelling and simulating change in reforesting mountain landscapes using a social-ecological framework

Boyer, Edmond

315

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contaminant's bioavailability and surface water contamination risk. We present a novel method of pesticide concentration. This method can be applied to a wide range of organic contaminants and catchments), the objectives of this study were (1) to check which of the environmental factors (discharge, pH, concentrations

Mailhes, Corinne

316

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is then suspected to be the result of numerous interactions between contaminants themselves and environmental are then briefly exposed to a complex mixture of contaminants. The aim of the present study is to investigate the higher contamination of the spring flood water, mainly explained by a peak of metolachlor. Genotoxicity

Mailhes, Corinne

317

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element contamination in the arms of the Danube Delta (Romania/Ukraine): Current state of knowledge and future needs. (2013) Journal of Environmental Management, 125 . pp. 169-178. ISSN 0301-4797 Any-oatao@listes-diff.inp-toulouse.fr #12;Trace element contamination in the arms of the Danube Delta (Romania/Ukraine): Current state

Mailhes, Corinne

318

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

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A multi-scale method to assess pesticide contamination risks in agricultural watersheds. (2014) Ecological pesticide contamination risks in agricultural watersheds Francis Macarya, , Soizic Morinb , Jean-Luc Probstc scaling Water contamination risk a b s t r a c t The protection of water is now a major priority

Mailhes, Corinne

319

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questions remain concerning the environmental impacts of these wastes in this kind of application or subterranean water. Consequently, draining waters may constitute an important reservoir for contaminants. This work is related to the evaluation of the environmental impact of meat and bone meal ashes in the cement

Mailhes, Corinne

320

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and thermal processes integrated in ProSimPlusĂ? as a well-adapted process simulator for energy efficiency. The applicability of the proposed meth- odology in ProSimPlusĂ? is shown through a simple scheme of Natural Gas third of global energy consumption. A common feature of industrial processes is reliance on fossil fuels

Paris-Sud XI, Université de

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


321

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

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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 in industrial processes are treated separately: power is purchased from an off-site energy provider and heating

Mailhes, Corinne

322

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

E-Print Network (OSTI)

of the stability of the laminar recirculation bubble for incompressible flow. It has been shown for low Reynolds stability of this solution is then investigates and we assess the influence of Mach number on the critical

Boyer, Edmond

323

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

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phases, in addition to interface properties as contact angles and surface tensions (Baussaron et al phenomenology have been studied, such as bubble creation and transport. As direct numerical methods for tracking. As an example, the stabilizing effect of gas injection on the flow pattern is studied numerically. 1

Mailhes, Corinne

324

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

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and thermo- electrochemical cells. In the field of water splitting to produce hydrogen they have been used family co-catalyse an unusual, very high energy efficiency water oxidation process. As fuel cell of fuel cells operating in the optimum temperature region above 100 C. Beyond electrochemical

Boyer, Edmond

325

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

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of renewable energy including the development of microbial fuel cells (MFCs) and hydrogen production, through 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

Mailhes, Corinne

326

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

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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

Mailhes, Corinne

327

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

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and present-day atmospheric pollution in SW France: a story of lichens. (2013) Environmental Pollution, vol manuscript, published in "Environmental Pollution vol. 172 (2013) pp. 139-148" DOI : 10.1016/j.envpol.2012

Boyer, Edmond

328

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

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of toner ink adsorption at bubble surfaces. (2006) TAPPI Journal, vol. 5 (n° 4). pp. 10-16. ISSN 0734-oatao@listes-diff.inp-toulouse.fr hal-00906399,version1-19Nov2013 Author manuscript, published in "Tappi Journal vol. 5 (2006) 10

Paris-Sud XI, Université de

329

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

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a new and original Mono inverter Multi parallel Permanent Magnet Synchronous Motor (PMSM) system inverter [3]-[7] With such systems, flexibility and safe operation are increased and the field of the power Bidart, Damien and Pietrzak-David, Maria and Maussion, Pascal and Fadel, Maurice Mono inverter multi

Paris-Sud XI, Université de

330

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

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to the electrochemical corrosion of typical valve metals, such as aluminium and titanium, a correla- tion was shown conveniently distinguished according to the sign of the viscosity B coefficient appearing in the Jones at molar concentra- tion c and gw is the viscosity of pure water. The coefficient A, which is positive

Mailhes, Corinne

331

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

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the valve opening sequence, and the drastic evolution of the two-phase flow regime as the flow evolves from injector, s b = date of the slope beginning, s CD = drag coefficient c = injection slope, s-1 D = pipe = drag force by mass unit, N · kg-1 Iu = inlet turbulence intensity k = number of phase L = valve path

Mailhes, Corinne

332

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

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are the fast transients in a complex geometry, including in particular the valve opening sequence injector, s b = date of the slope beginning, s CD = drag coefficient c = injection slope, s-1 D = pipe = drag force by mass unit, N · kg-1 Iu = inlet turbulence intensity k = number of phase L = valve path

Boyer, Edmond

333

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

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, and because floodplains are one of the most threatened ecosystems, we propose a statistical strategy conservation. Conversely, two clusters with low Q median values included 11 waterbodies where restoration is called for. The results picked out high connectivity levels and low abundance of aquatic vegetation

Paris-Sud XI, Université de

334

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

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of the most important factors endangering native biodiver- sity in aquatic ecosystems (Rahel and Olden 2008), and is now considered to be the third biggest cause of biodiversity decline in aquatic ecosystems (Sala et al to colonize. The restoration of river quality could increase the number of refuges for native species, thus

Mailhes, Corinne

335

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

E-Print Network (OSTI)

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

Boyer, Edmond

336

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

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population density in most mangrove areas combined with the availability of other timber and fuelwood sources characteristic of East Africa, according to SECA (1986). If most of the mangrove specialists agree

Paris-Sud XI, Université de

337

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

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behavior concerning dynamic loads and a variety of damage mechanisms, that are hard to classify this document: NIEMANN, Hanno, MORLIER, Joseph, SHAHDIN, Amir, GOURINAT, Yves. Damage localization using experimental modal parameters and topology optimization. In : Mechanical systems and signal processing, 2010

Mailhes, Corinne

338

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

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point measurements and modeling for the ternary type-I mixtures, water + ethanol + 1-butanol, water + ethanol + 2-butanol, and the type-II mixture, water + 1-butanol + 2-butanol. Results reveal that the flash

Mailhes, Corinne

339

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

E-Print Network (OSTI)

and fatigue or corrosion resistance, the cutting forces values should be known as precisely as possible of the elementary edge in the reference plane rP . However, when turning in the tool nose or with round inserts. For this study, a new elementary cutting operation, called "oriented cutting", has been tested

Paris-Sud XI, Université de

340

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-Louis and Simon, Patrice and Barsoum, Michel W. and Gogotsi, Yury. MXene: a promising transition metal carbide

Paris-Sud XI, Université de

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


341

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

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and industrial gas turbine. At an industrial scale, the Electron Beam Physical Vapour Deposition (EB and durability under cyclic oxidation. Surface and Coatings Technology, vol. 205 (n° 5). pp. 1256-1251. ISSN 0257 Rumpling A new promising and versatile process based on the sol­gel transformation has been developed

Mailhes, Corinne

342

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

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- based gas turbines. Nb-silicide-based composites are potential alloy candidates because they present of Technology, S-10044, Stockholm 70, Sweden Abstract In the present work, the NbeB binary system. Thermodynamic and thermochemical properties; E. Phase diagram, prediction 1. Introduction The development of new

Paris-Sud XI, Université de

343

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for small scale reactors, we are studying the link between local packing, local flows and chemical responses several applications in chemical industry. They are used in reaction, separation and purification processes. Small size catalytic fixed bed reactors are commonly used to assess the performances

Paris-Sud XI, Université de

344

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

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-event transient (SET). I. INTRODUCTION MEGAJOULE-CLASS laser facilities are devoted to the study of nuclear fusion] and in France (Laser Megajoule, LMJ) [2], and they will need plasma diagnostics to perform high neutron yield ex Experimental Reactor (ITER) [4], and in future projects such as the High Power laser Energy Re- search (Hi

Mailhes, Corinne

345

UESC Data Collection Update  

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

UESC Data UESC Data Collection Evan Fuka Energetics, Incorporated 2 | Federal Energy Management Program eere.energy.gov * Overview of Data Collection * What is Needed * How to Submit Data * Why it is Important to You Presentation Overview 3 | Federal Energy Management Program eere.energy.gov * Data on UESC projects has been collected since 1995 * Over $2.3 billion has been invested in federal facilities upgrades and retrofits through the UESC funding mechanism * Information on almost 2,000 UESC projects has been voluntarily submitted and tracked on a continuous basis UESC Data Collection Facts 4 | Federal Energy Management Program eere.energy.gov * Average annual project investment: $123 Million * Utilities engaging in UESC: approximately 40 * UESC Utilities active in FUPWG: approximately 20

346

Soils Collections Project Page  

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

Soil Collections Soil Collections Soil Collections Overview Soil covers a major portion of the Earth's surface, and is an important natural resource that either directly or indirectly supports most of the planet's life. Soil is a mixture of mineral and organic materials plus air and water. The contents of soil vary by location and are constantly changing. The ORNL DAAC Soil Collections archive contains data on the physical and chemical properties of soils, including: soil carbon and nitrogen soil water-holding capacity soil respiration soil texture Most data sets are globally gridded, while a few are of a regional nature. Get Soils Data Find and order data sets: See list of data sets and download data Browse Soils Data Holdings by selected attributes Retrieve Soils data by FTP browse

347

Sparse matrix test collections  

SciTech Connect

This workshop will discuss plans for coordinating and developing sets of test matrices for the comparison and testing of sparse linear algebra software. We will talk of plans for the next release (Release 2) of the Harwell-Boeing Collection and recent work on improving the accessibility of this Collection and others through the World Wide Web. There will only be three talks of about 15 to 20 minutes followed by a discussion from the floor.

Duff, I.

1996-12-31T23:59:59.000Z

348

A Method to Evaluate Additional Waste Forms to Optimize Performance of the HLW Repository  

SciTech Connect

The DOE high-level waste (HLW) disposal system is based on decisions made in the 1970s. The de facto Yucca Mountain WAC for HLW, contained in the Waste Acceptance System Requirements Document (WASRD), and the DOE-EM Waste Acceptance Product Specification for Vitrified High Level Waste Forms (WAPS) tentatively describes waste forms to be interred in the repository, and limits them to borosilicate glass (BSG). It is known that many developed waste forms are as durable as or better than environmental assessment or “EA”-glass. Among them are the salt-ceramic and metallic waste forms developed at ANL-W. Also, iron phosphate glasses developed at University of Missouri show promise in stabilizing the most refractory materials in Hanford HLW. However, for any of this science to contribute, the current Total System Performance Assessment model must be able to evaluate the additional waste form to determine potential impacts on repository performance. The results can then support the technical bases required in the repository license application. A methodology is proposed to use existing analysis models to evaluate potential additional waste forms for disposal without gathering costly material specific degradation data. The concept is to analyze the potential impacts of waste form chemical makeup on repository performance assuming instantaneous waste matrix dissolution. This assumption obviates the need for material specific degradation models and is based on the relatively modest fractional contribution DOE HLW makes to the repository radionuclide and hazardous metals inventory. The existing analysis models, with appropriate data modifications, are used to evaluate geochemical interactions and material transport through the repository. This methodology would support early screening of proposed waste forms through simplified evaluation of disposal performance, and would provide preliminary guidance for repository license amendment in the future.

D. Gombert; L. Lauerhass

2006-02-01T23:59:59.000Z

349

Constructing a Risk Controversy: The Case of a Proposed High-Level Nuclear Waste Repository on the Skull Valley Goshute.  

E-Print Network (OSTI)

?? This thesis is a qualitative case study of a risk controversy generated by a proposal to construct a high-level nuclear waste repository on the… (more)

Jones, Taunya J.

2005-01-01T23:59:59.000Z

350

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

E-Print Network (OSTI)

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

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

2002-01-01T23:59:59.000Z

351

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

E-Print Network (OSTI)

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

Rutqvist, Jonny

2008-01-01T23:59:59.000Z

352

Use of a United States mid-Pacific Island territory for a Pacific Island Repository System (PIRS): Extended summary  

SciTech Connect

The concept of using a mid-ocean island for a geologic high-level waste repository was investigated. The technical advantages include geographical isolation and near-infinite ocean dilution as a backup to repository geological waste isolation. The institutional advantages are reduced siting problems and the potential of creating an international waste repository. Establishment of international waste repository would allow cost sharing, aid US nonproliferation goals, and assure proper disposal of spent fuel from developing countries. The major uncertainties in this concept are rock conditions at waste disposal depths and costs. 13 refs., 2 tabs.

Forsberg, C.W.

1987-08-01T23:59:59.000Z

353

Landfill; leachates, landfill gases  

Science Journals Connector (OSTI)

is a method of refuse disposal on land without creating nuisance to public health or safety by using the principles of engineering to confine refuse to the smallest practicable area, to reduce it to the sma...

Ming H. Wong

1999-01-01T23:59:59.000Z

354

Background - Revenue Collection  

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

Revenue Collection Revenue Collection The Internal Revenue Service (IRS) collects Federal fuel taxes from large oil companies or large oil distribution firms with storage facilities prior to distribution of the fuels to customers. The Federal fuel taxes are imposed when the fuel is first removed from bulk storage and sold. Although these taxes are "passed on" to the individual purchaser, data at the individual purchaser level are simply not available. Additional Federal heavy vehicle non-fuel-based fees include (1) the retail sales excise tax on tractors and trailers, (2) the tax on heavy vehicle tire sales, and (3) the heavy vehicle-use tax. Truck registration was once used as a proxy for truck taxes, but was rejected because it did not accurately reflect on-highway usage in a particular State. In fact, the State where the heavy vehicle and/or tires are purchased is not necessarily the State in which these purchases will be used.

355

Utility Data Collection Service  

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

Data Collection Service Data Collection Service Federal-Utility Partnership Working Group 4 May 2006 Paul Kelley, Chief of Operations, 78 th CES, Robins AFB David Dykes, Industrial Segment Mgr, Federal, GPC Topics  Background  Commodities Metered  Data Collection  Cost  Results Background  Robins AFB (RAFB) needed to:  Control electricity usage and considered Demand Control  Track and bill base tenants for energy usage  Metering Project Originated in 1993  $$ requirements limited interest  Developed criteria for available $$  Energy Policy Act 2005:  All facilities sub-metered by 2012  $$ no longer restricts metering project Metering Criteria prior to EPACT 2005  All New Construction - (per Air Force Instructions)

356

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

SciTech Connect

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.

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

2003-11-15T23:59:59.000Z

357

A description and status of the Yucca Mountain Project repository sealing program  

SciTech Connect

Yucca Mountain is being characterized to determine its suitability as a site for a high-level nuclear waste repository. The repository would be located in the unsaturated zone in fractured, welded tuff. Sealing of the repository is one element of the Yucca Mountain Project (YMP). This paper presents a description of the repository sealing program including the sealing design options, design requirements, design constraints, and the identification of the proposed sealing materials and field tests. Design options for the shafts include anchor-to-bedrock seals, shaft fill, and settlement plugs; in the underground facility options include drift seals, drainage channels, sumps, and bulkheads. Design requirements are those quantitative requirements imposed on the sealing design options to achieve a desired level of performance. Constraints are restrictions placed on the repository design by the sealing design. As (1) additional hydrogeologic data are obtained through site characterization, (2) approaches to allocating performance to various subsystems within the YMP are refined, and (3) the exploratory shafts and the associated testing results are developed, the design requirements and constraints may be modified and used in developing the License Application Design. 1 ref., 1 fig.

Fernandez, J.A.; Hinkebein, T.E.

1989-10-01T23:59:59.000Z

358

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

SciTech Connect

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

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

1980-12-01T23:59:59.000Z

359

Conceptual model for regional radionuclide transport from a basalt repository site. Final draft, technical memorandum  

SciTech Connect

This technical memorandum was prepared to: (1) describe a typical basalt radionuclide repository site, (2) describe geologic and hydrologic processes associated with regional radionuclide transport in basalts, (3) define the parameters required to model regional radionuclide transport from a basalt repository site, and (4) develop a ''conceptual model'' of radionuclide transport from a basalt repository site. In a general hydrological sense, basalts may be described as layered sequences of aquifers and aquitards. The Columbia River Basalt, centered near the semi-arid Pasco Basin, is considered by many to be typical basalt repository host rock. Detailed description of the flow system including flow velocities with high-low hydraulic conductivity sequences are not possible with existing data. However, according to theory, waste-transport routes are ultimately towards the Columbia River and the lengths of flow paths from the repository to the biosphere may be relatively short. There are many physical, chemical, thermal, and nuclear processes with associated parameters that together determine the possible pattern of radionuclide migration in basalts and surrounding formations. Brief process descriptions and associated parameter lists are provided. Emphasis has been placed on the use of the distribution coefficient in simulating ion exchange. The use of the distribution coefficient approach is limited because it takes into account only relatively fast mass transfer processes. In general, knowledge of hydrogeochemical processes is primitive.

Walton, W.C.; Voorhees, M.L.; Prickett, T.A.

1980-05-23T23:59:59.000Z

360

Special Collections, General Collections, and Hybrid Conservation Laboratories  

E-Print Network (OSTI)

repairs, others limit themselves to full special-collections treatments and advanced bookbinding work, while still others might incorporate both general collections and special collections workflows in the same hybrid space. In this chapter...

Baker, Whitney

2012-01-01T23:59:59.000Z

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


361

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

362

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

363

Information Collection Management Program  

Directives, Delegations, and Requirements

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.

2006-10-11T23:59:59.000Z

364

Sustainability Bulletin Clothing Collection  

E-Print Network (OSTI)

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

Kidd, William S. F.

365

Simultaneous speciation of arsenic, selenium, and chromium: species stability, sample preservation, and analysis of ash and soil leachates  

Science Journals Connector (OSTI)

The ash and soil samples collected from the wildfire impacted areas in California were subjected to the FLT procedure described by Hageman and a simulated lung fluid (SLF) leach test similar to that described by....

Ruth E. Wolf; Suzette A. Morman…

2011-11-01T23:59:59.000Z

366

Report on Modeling Coupled Processes in the Near Field of a Clay Repository  

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

on Modeling Coupled Processes in the Near Field of a Clay on Modeling Coupled Processes in the Near Field of a Clay Repository Report on Modeling Coupled Processes in the Near Field of a Clay Repository Clay/shale has been considered as potential host rock for geological disposal of high-level radioactive waste throughout the world. Coupled thermal, hydrological, mechanical, and chemical (THMC) processes have a significant impact on the long-term safety of a clay repository. This report documents results from three R&D activities: (1) implementation and validation of constitutive relationships, (2) development of a discrete fracture network (DFN) model for investigating coupled processes in the excavation damaged zone, and (3) development of a THM model for the Full-Scale Emplacement Experiment tests at Mont Terri, Switzerland, for the

367

Coupled Model for Heat and Water Transport in a High Level Waste Repository  

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

Coupled Model for Heat and Water Transport in a High Level Waste Coupled Model for Heat and Water Transport in a High Level Waste Repository in Salt Coupled Model for Heat and Water Transport in a High Level Waste Repository in Salt This report summarizes efforts to simulate coupled thermal-hydrological-chemical (THC) processes occurring within a generic hypothetical high-level waste (HLW) repository in bedded salt; chemical processes of the system allow precipitation and dissolution of salt with elevated temperatures that drive water and water vapor flow around hot waste packages. Characterizing salt backfill processes is an important objective of the exercise. An evidence-based algorithm for mineral dehydration is also applied in the modeling. The Finite Element Heat and Mass transfer code (FEHM) is used to simulate coupled thermal,

368

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

SciTech Connect

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

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

1980-05-30T23:59:59.000Z

369

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

SciTech Connect

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.

Abe Van Luik

2009-07-17T23:59:59.000Z

370

Environmental review and regulation for siting a nuclear waste repository at Yucca Mountain, Nevada  

Science Journals Connector (OSTI)

The U.S. Department of Energy (DOE) has proposed that the first geologic repository for high-level nuclear waste in the United States be sited at Yucca Mountain, Nevada. Repository sitting was exempted by the Nuclear Waste Policy Act from the requirements for an environmental impact statement under the National Environmental Policy Act (NEPA) and, additionally, the DOE was prohibited by law from acquiring new empirical information for environmental assessment. Thus, no systematic, interdisciplinary evaluation of impacts based on site-specific data will occur before the Yucca Mountain environment is irreparably altered by site characterization. Exemption of siting activities for the nation's first geologic repository for high-level nuclear wastes from NEPA review is further evidence of the eclipse of NEPA in decision making, a trend that may foretell how controversial, technologically complex projects will be carried out in the future.

Charles R. Malone

1989-01-01T23:59:59.000Z

371

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

SciTech Connect

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.

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

2007-01-01T23:59:59.000Z

372

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

SciTech Connect

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.

Stahl, D. [Framatome Cogema Fuels, Las Vegas, NV (United States); Svinicki, K. [USDOE Office of Civilian Radioactive Waste Management, Washington, DC (United States)

1996-07-01T23:59:59.000Z

373

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

E-Print Network (OSTI)

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.

Bourgeat, Alain; Smai, Farid

2010-01-01T23:59:59.000Z

374

Radiological Aspects of Deep-Burn Fusion-Fission Hybrid Waste in a Repository  

SciTech Connect

The quantity, radioactivity, and isotopic characteristics of the spent fission fuel from a hybrid fusion-fission system capable of extremely high burnups are described. The waste generally has higher activity per unit mass of heavy metal, but much lower activity per unit energy generated. The very long-term radioactivity is dominated by fission products. Simple scaling calculations suggest that the dose from a repository containing such waste would be dominated by {sup 129}I, {sup 135}Cs, and {sup 242}Pu. Use of such a system for generating energy would greatly reduce the need for repository capacity.

Shaw, H F; Blink, J A; Farmer, J C; Karmer, K J; Latkowski, J F; Zhao, P

2008-11-25T23:59:59.000Z

375

Collective network routing  

DOE Patents (OSTI)

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.

Hoenicke, Dirk

2014-12-02T23:59:59.000Z

376

Kraith Collected Issue 6  

E-Print Network (OSTI)

fans, there will be no new Kraith stories. For more information on how we feel about fanzines in general, please turn to "Editors are Ghouls and Cannibals". Kraith Collected continues, with this issue, it's long established policy of publishing a... new volume at least two years later than we promised. Enjoy. (~ "- Carol Lynn December 18, 1980 EDITING: Carol Lynn, Deborah Goldstein TYPING: T'Pat, Deborah Goldstein, Carol Lynn, Michelle Barney LAYOUT: Carol Lynn, Deborah Goldstein, Fred...

Lichtenberg, Jacqueline; Multiple Contributors

1980-01-01T23:59:59.000Z

377

Early Restoration Plan (Phase III FERP)Repositories STATE LIBRARY ADDRESS CITY ZIP  

E-Print Network (OSTI)

Public Library Central Branch 301 W. Claude St. Lake Charles 70605 29. LA Iberia Parish Library 445 EEarly Restoration Plan (Phase III FERP)Repositories STATE LIBRARY ADDRESS CITY ZIP 1. AL Dauphin. Mobile 36606 6. AL City of Bayou La Batre Public Library 12747 Padgett Switch Road Irvington 36544 7. FL

378

Design of a WSRC Repository with an EndUser Emphasis Technical Report for  

E-Print Network (OSTI)

River Company (WSRC) Savannah River Site (SRS) Aiken, SC 29808 January 14, 1994 John A. Miller Walter DDesign of a WSRC Repository with an End­User Emphasis Technical Report for Westinghouse Savannah, there will be multi­ ple operational databases as well as several special purpose databases. Forward looking organi

Miller, John A.

379

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

SciTech Connect

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.

Scott, J.A.

1983-03-01T23:59:59.000Z

380

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

E-Print Network (OSTI)

Knowledge Network: An Information Repository with Services for Managing Concurrent Engineering, leizero}@ie.utoronto.ca Abstract Our effort is to construct a Knowledge Aided Design (KAD) system, which design engineers. The KAD system centers on a knowledge network that stores design knowledge and provides

Fox, Mark S.

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


381

Geochemistry of Salado Formation brines recovered from the Waste Isolation Pilot Plant (WIPP) repository  

SciTech Connect

Intergranular brines recovered from the repository horizon of the Waste Isolation Pilot Plant (WIPP) have major- and trace-element compositions that reflect seawater evaporation and diagenetic processes. Brines obtained from repository drill holes are heterogenous with respect to composition, but their compositional fields are distinct from those obtained from fluid inclusions in WIPP halite. The heterogeneity of brine compositions within the drill-hole population indicates a lack of mixing and fluid homogenization within the salt at the repository level. Compositional differences between intergranular (drill hole) and intragranular (fluid inclusions) brines is attributed to isolation of the latter from diagenetic fluids that were produced from dehydration reactions involving gypsum and clay minerals. Modeling of brine-rock equilibria indicates that equilibration with evaporite minerals controls the concentrations of major elements in the brine. Drill-hole brines are in equilibrium with the observed repository minerals halite, anhydrite, magnesite, polyhalite and quartz. The equilibrium model supports the derivation of drill-hole brines from near-field fluid, rather than large-scale vertical migration of fluids from the overlying Rustler or underlying Castile Formations. 13 refs., 6 figs., 6 tabs.

Abitz, R.; Myers, J.; Drez, P.; Deal, D.

1990-01-01T23:59:59.000Z

382

Research and Application of Intelligent Quality Control System Based on FMEA Repository  

Science Journals Connector (OSTI)

Although statistical process control (SPC) provides statistical techniques and graphical displays control charts to enable the quality of process to be monitored and special causes of process variability to be eliminated, this technology has been not ... Keywords: Manufacturing Process, Intelligent Quality Control, Statistical Process Control, FMEA Repository, Process Continuing Improvement

Xiuxu Zhao; Yu-bao Ma; Rui Cai; Xiao-li Bai; Lin-yan Ning

2009-07-01T23:59:59.000Z

383

VIVDR -Vortex-induced vibration data repository An overview of available riser datasets  

E-Print Network (OSTI)

VIVDR - Vortex-induced vibration data repository An overview of available riser datasets http://oe.mit.edu/VIV H. Mukundan and M. Triantafyllou 20 April 2008 #12;NDP 38m long riser model datasets #12;33 q Rig q Tension applied through spring-supported clump weights NDP 38m long riser model datasets

384

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

E-Print Network (OSTI)

, motivated by the smart power grid domain. Our repository model allows users to securely store and share later, or revoking this permission alto- gether. An electricity consumer with a smart power grid utility Foundation even mandate this. Cloud platforms that provide the benefit of on-demand storage collocated

Prasanna, Viktor K.

385

Distributed XML Repositories: Top-down Design and Transparent Query Processing  

E-Print Network (OSTI)

Distributed XML Repositories: Top-down Design and Transparent Query Processing Michael Gertz Jan over the Web. However, design and query processing models for distributed XML data have not yet been studied in detail. The goal of this paper is to study the design and management of distributed XML

Gertz, Michael

386

ExPort: Detecting and Visualizing API Usages in Large Source Code Repositories  

E-Print Network (OSTI)

ExPort: Detecting and Visualizing API Usages in Large Source Code Repositories Evan Moritz1, Mario a technique for automatically mining and visualizing API usage examples. In contrast to previous approaches, our technique is capable of finding examples of API usage that occur across several functions

Poshyvanyk, Denys

387

MAPO: Mining API Usages from Open Source Repositories Department of Computer Science  

E-Print Network (OSTI)

MAPO: Mining API Usages from Open Source Repositories Tao Xie Department of Computer Science North by invoking their APIs. Those APIs, however, are often com- plex and not well documented, posing barriers for developers to use them in new client code. To get familiar with how those APIs are used, developers may

Xie, Tao

388

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

SciTech Connect

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.

K.G. Mon; F. Hua

2005-04-12T23:59:59.000Z

389

May 2014 Wright State University Pascal Hitzler Cross-repository information discovery  

E-Print Network (OSTI)

May 2014 ­ Wright State University ­ Pascal Hitzler Cross-repository information discovery in the earth sciences Adila Krisnadhi Wright State University Robert Arko LDEO, Columbia University Suzanne Wright State University Timothy Finin University of Maryland, Baltimore County Pascal Hitzler Wright

Hitzler, Pascal

390

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

SciTech Connect

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.

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

1982-06-01T23:59:59.000Z

391

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

SciTech Connect

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.

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

1982-06-01T23:59:59.000Z

392

Chapter 9 GIS Data Collection 117 GIS Data Collection  

E-Print Network (OSTI)

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

Wright, Dawn Jeannine

393

Contacts for Information Collection Management | Department of...  

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

Information Collection Management Contacts for Information Collection Management Information Collection Program, and Information Quality Guidelines Christina Rouleau, IM-23 Records...

394

Binghamton University Libraries Special Collections  

E-Print Network (OSTI)

Yaqui Copper Company Yerba Maté Tea Company (American-Brazilian Trading Company) Green died January 16Binghamton University Libraries Special Collections The George E. Green Letter Collection, 1900-1916 Finding Aid created 2010 Macarry Pobanz, Student Assistant, Special Collections #12;The George E. Green

Suzuki, Masatsugu

395

Numerical Modeling of Gas Migration at a Proposed Repository for Low and Intermediate Level Nuclear Wastes at Oberbauenstock, Switzerland  

E-Print Network (OSTI)

repository rate, based on average cavern length of 466·m.total length of the storage caverns is approximately 4660 m.With 10 caverns in parallel, average cavern length is 466 m,

Pruess editor, K.

2010-01-01T23:59:59.000Z

396

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

Science Journals Connector (OSTI)

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, a detailed performance assessment (PA) for the YM repository was completed in 2008 and supported a license application by the DOE to the U.S. Nuclear Regulatory Commission (NRC) for the construction of the YM repository. The following aspects of the 2008 YM PA are described in this presentation: (i) conceptual structure and computational organization, (ii) uncertainty and sensitivity analysis techniques in use, (iii) uncertainty and sensitivity analysis for physical processes, and (iv) uncertainty and sensitivity analysis for expected dose to the reasonably maximally exposed individual (RMEI) specified the NRC’s regulations for the YM repository.

Jon C. Helton; Clifford W. Hansen; Cédric J. Sallaberry

2012-01-01T23:59:59.000Z

397

The importance of zeolites in the potential high-level radioactive waste repository at Yucca Mountain, Nevada  

SciTech Connect

Zeolitic rocks play an important role in retarding the migration of radionuclides that occur in solution as simple cations (Cs, Sr, Ba). However, the interaction of zeolites with complex transuranic species in solution provides little if any advantage over other common silicate minerals. The most important consequences of zeolite occurrences near a high-level radioactive waste repository environment are likely to be their response to thermal loading and their impact on site hydrology. Partial zeolite dehydration during the early thermal pulse from the repository and rehydration as the repository slowly cools can have an important impact on the water budget of a repository in unsaturated rocks, provided that the long-term heating does not result in zeolite destabilization.

Vaniman, D.T.; Bish, D.L.

1993-07-01T23:59:59.000Z

398

Potential role of ABC-assisted repositories in U.S. plutonium and high-level waste disposition  

SciTech Connect

This paper characterizes the issues involving deep geologic disposal of LWR spent fuel rods, then presents results of an investigation to quantify the potential role of Accelerator-Based Conversion (ABC) in an integrated national nuclear materials and high level waste disposition strategy. The investigation used the deep geological repository envisioned for Yucca Mt., Nevada as a baseline and considered complementary roles for integrated ABC transmutation systems. The results indicate that although a U.S. geologic waste repository will continue to be required, waste partitioning and accelerator transmutation of plutonium, the minor actinides, and selected long-lived fission products can result in the following substantial benefits: plutonium burndown to near zero levels, a dramatic reduction of the long term hazard associated with geologic repositories, an ability to place several-fold more high level nuclear waste in a single repository, electricity sales to compensate for capital and operating costs.

Berwald, David; Favale, Anthony; Myers, Timothy; McDaniel, Jerry [Grumman Aerospace Corporation, Bethpage New York 11714 (United States); Bechtel Corporation, 50 Beal St., San Francisco, California 94105 (United States)

1995-09-15T23:59:59.000Z

399

DOE Hydrogen Analysis Repository: HyDRA: Hydrogen Demand and Resource  

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

HyDRA: Hydrogen Demand and Resource Analysis Tool HyDRA: Hydrogen Demand and Resource Analysis Tool Project Summary Full Title: HyDRA: Hydrogen Demand and Resource Analysis Tool Project ID: 220 Principal Investigator: Johanna Levene Brief Description: HyDRA has evolved from a basic display of spatial data to a repository of over 100 datasets with dynamic data, querying, and interoperability with other models and spatial data repositories and over 350 registered users. Keywords: Hydrogen infrastructure; wind; solar; biomass; coal; natural gas Purpose Facilitate regional and geographical analyses of resources, demand, and infrastructure relevant to the implementation of hydrogen production, delivery, and dispensing. Performer Principal Investigator: Johanna Levene Organization: National Renewable Energy Laboratory (NREL)

400

Approval of Existent Waste Packages and New Package Designs in Preparation for the Konrad Repository  

SciTech Connect

Low and intermediate level radioactive waste from German nuclear and other industries, research facilities and increasingly decommissioned nuclear installations is handled and prepared for interim storage and later disposal in the licensed KONRAD repository. This paper presents aspects, experiences and perspectives of container design testing and qualification procedures. Several new container designs, in particular different types of steel plate containers, have been tested and licensed; some are handled at present or just applied. Examples from typical qualification procedures including drop tests from 0.8 and 5 m height with prototype containers are presented. On the other hand several thousand waste packages are currently stored in interim storage facilities, many of them for more than 10 or 15 years. Based on existing package documentation applications and safety assessments for KONRAD are prepared and have to be evaluated. The paper discusses aspects, difficulties and strategies to demonstrate sufficient compliance to the current KONRAD repository requirements for the large number of existent waste packages. (authors)

Volzke, H.; Nieslony, G.; Hagenow, P. [BAM Bundesanstalt fur Materialforschung und - prufung, Federal Institute for Materials Research and Testing, Berlin (Germany)

2008-07-01T23:59:59.000Z

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


401

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

SciTech Connect

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.

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

2006-03-28T23:59:59.000Z

402

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

SciTech Connect

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

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

1990-12-01T23:59:59.000Z

403

Staff Technical Position on geological repository operations area underground facility design: Thermal loads  

SciTech Connect

The purpose of this Staff Technical Position (STP) is to provide the US Department of Energy (DOE) with a methodology acceptable to the Nuclear Regulatory Commission staff for demonstrating compliance with 10 CFR 60.133(i). The NRC staff`s position is that DOE should develop and use a defensible methodology to demonstrate the acceptability of a geologic repository operations area (GROA) underground facility design. The staff anticipates that this methodology will include evaluation and development of appropriately coupled models, to account for the thermal, mechanical, hydrological, and chemical processes that are induced by repository-generated thermal loads. With respect to 10 CFR 60.133(i), the GROA underground facility design: (1) should satisfy design goals/criteria initially selected, by considering the performance objectives; and (2) must satisfy the performance objectives 10 CFR 60.111, 60.112, and 60.113. The methodology in this STP suggests an iterative approach suitable for the underground facility design.

Nataraja, M.S. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of High-Level Waste Management; Brandshaug, T. [Itasca Consulting Group, Inc., Minneapolis, MN (United States)

1992-12-01T23:59:59.000Z

404

Staff Technical Position on geological repository operations area underground facility design: Thermal loads  

SciTech Connect

The purpose of this Staff Technical Position (STP) is to provide the US Department of Energy (DOE) with a methodology acceptable to the Nuclear Regulatory Commission staff for demonstrating compliance with 10 CFR 60.133(i). The NRC staff's position is that DOE should develop and use a defensible methodology to demonstrate the acceptability of a geologic repository operations area (GROA) underground facility design. The staff anticipates that this methodology will include evaluation and development of appropriately coupled models, to account for the thermal, mechanical, hydrological, and chemical processes that are induced by repository-generated thermal loads. With respect to 10 CFR 60.133(i), the GROA underground facility design: (1) should satisfy design goals/criteria initially selected, by considering the performance objectives; and (2) must satisfy the performance objectives 10 CFR 60.111, 60.112, and 60.113. The methodology in this STP suggests an iterative approach suitable for the underground facility design.

Nataraja, M.S. (Nuclear Regulatory Commission, Washington, DC (United States). Div. of High-Level Waste Management); Brandshaug, T. (Itasca Consulting Group, Inc., Minneapolis, MN (United States))

1992-12-01T23:59:59.000Z

405

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

SciTech Connect

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.

Barrett, L. H.

2002-02-25T23:59:59.000Z

406

Regulatory Review of the Safety Case for Siting Licensing of Saligny Low and Intermediate Waste Repository  

SciTech Connect

The paper contains the regulatory review comments produced following submission of siting license application of Saligny repository. The regulatory review was conducted in order to verify the compliance with Romanian regulatory criteria and requirements. After assessment of completeness of safety case and availability of supporting documents the review the main technical areas started. The review process was focused on the site characteristics, waste characteristics, safety considerations as scenarios development, mathematical models, identification and treatment of uncertainties, availability of parameters. (authors)

Dogaru, D.M. [National Commission for Nuclear Activities Control, 5 Bucharest (Romania)

2008-07-01T23:59:59.000Z

407

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

SciTech Connect

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

Smith, M.J.

1980-05-01T23:59:59.000Z

408

Making the Postclosure Safety Case for the Proposed Yucca Mountain Repository  

SciTech Connect

The International Atomic Energy Agency (IAEA), in its advisory standard for geological repositories promulgated jointly with the Nuclear Energy Agency (NEA) of the Organization for Economic Co-operation and Development, explicitly distinguishes between the concepts of a safety case and a safety assessment. As defined in the advisory standard, the safety case is a broader set of arguments that provide confidence and substantiate the formal analyses of system safety made through the process of safety assessment. Although the IAEAYs definitions include both preclosure (i.e., operational) safety and post-closure performance in the overall safety assessment and safety case, the emphasis in here is on long-term performance after waste has been emplaced and the repository has been closed. This distinction between pre- and postclosure aspects of the repository is consistent with the U.S. regulatory framework defined by the U.S. Environmental Protection Agency (Chapter 40 of the Code of Federal Regulations, Part 197, or 40 CFR 197) [2] and implemented by the U.S. Nuclear Regulatory Commission (Chapter 10 of the Code of Federal Regulations, Part 63, or 10 CFR 63) [3]. The separation of the pre- and postclosure safety cases is also consistent with the way in which the U.S. Department of Energy has assigned responsibilities for developing the safety case. Bechtel SAIC Company is the Management and Operating contractor responsible for the design and operation of the Yucca Mountain facility and is therefore responsible for the preparation of the preclosure aspects of the safety case. Sandia National Laboratories has lead responsibility for scientific work evaluating post-closure performance, and therefore is responsible for developing the post-closure aspects of the safety case. In the context of the IAEA definitions, both preclosure and postclosure safety, including safety assessment and the safety case, will be documented in the license application being prepared for the proposed Yucca Mountain repository, and in the documents that support that license application.

P. Swift; A.V. Luik

2006-08-28T23:59:59.000Z

409

Potentiodynamic polarization studies on candidate container alloys for the Tuff Repository  

SciTech Connect

Cortest Columbus Technologies, Inc. (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 cyclic-potentiodynamic-polarization (CCP) studies performed on candidate container materials for the Tuff Repository. The CPP technique was used to provide an understanding of how specific variables such as environmental composition, temperature, alloy composition, and welding affect both the general- and localized-corrosion behavior of two copper-base and two Fe-Cr-Ni alloys in simulated repository environments. A statistically-designed test solution matrix was formulated, based on an extensive search of the literature, to evaluate the possible range of environmental species that may occur in the repository over the life of the canister. Forty-two CPP curves were performed with each alloy and the results indicated that several different types of corrosion were possible. The copper-base alloys exhibited unusual CCP behavior in that hysteresis was not always associated with pitting. The effects of temperature on the corrosions behavior were evaluated in two types of tests; isothermal tests at temperatures from 50{degrees}C to 90{degrees}C and heat-transfer tests where the solution was maintained at 50{degrees}C and the specimen was internally heated to 90{degrees}C. In the isothermal test, CPP curves were obtained with each alloy in simulated environments at 50{degrees}C, 75{degrees}C, and 90{degrees}C. The results of these CCP experiments indicated that no systematic trends were evident for the environments tested. Lastly, the effects of welding on the corrosion behavior of the alloys in simulated environments were examined.

Thompson, N.G.; Beavers, J.A.; Durr, C.L. [Cortest Columbus Technologies, OH (United States)

1992-01-01T23:59:59.000Z

410

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

SciTech Connect

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.

none,

1985-04-01T23:59:59.000Z

411

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

SciTech Connect

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.

NONE

1997-12-31T23:59:59.000Z

412

Stress-corrosion-cracking studies on candidate container alloys for the Tuff Repository  

SciTech Connect

Cortest Columbus Technologies, Inc. (CC Technologies) investigated the long-term performance of container materials used for high-level waste package as part of the information needed by the Nuclear Regulatory Commission (NRC) to assess the Department of Energy`s application to construct to geologic repository for high-level radioactive waste. At the direction of the NRC, the program focused on the Tuff Repository. This report summarizes the results of Stress-Corrosion-Cracking (SCC) studies performed in Tasks 3, 5, and 7 of the program. Two test techniques were used; U-bend exposures and Slow-Strain-Rate (SSR) tests. The testing was performed on two copper-base alloys (Alloy CDA 102 and Alloy CDA 175) and two Fe-Cr-Ni alloys (Alloy 304L and Alloy 825) in simulated J-13 groundwater and other simulated solutions for the Tuff Repository. These solutions were designed to simulate the effects of concentration and irradiation on the groundwater composition. All SCC testing on the Fe-Cr-Ni Alloys was performed on solution-annealed specimens and thus issues such as the effect of sensitization on SCC were not addressed.

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

1992-05-01T23:59:59.000Z

413

ADVANTG Shielding Analysis for Closure Operations in an Open-Mode Repository  

SciTech Connect

en-mode repository concepts could require worker entry into access drifts after placement of fuel casks in order to perform activities related to backfill, plug emplacement, routine maintenance, or performance confirmation. An ideal emplacement-drift shielding configuration would minimize dose to workers while maximizing airflow through the emplacement drifts. This paper presents a preliminary investigation of the feasibility and effectiveness of radiation shielding concepts that could be employed to facilitate worker operations in an open-mode repository. The repository model for this study includes pressurized-water reactor fuel assemblies (60 GWd/MTU burnup, 40 year post-irradiation cooldown) in packages of 32 assemblies. The closest fuel packages are 5 meters from dosimetry voxels in the access drift. The unshielded dose to workers in the access drift is 73.7 rem/hour. Prior work suggests that open-mode repository concepts similar to this one would require 15 m3/s of ventilation airflow. Shielding concepts considered here include partial concrete plugs, labyrinthine shields, and stainless steel photon attenuator grids. Maximum dose to workers in the access drift was estimated for each shielding concept using MCNP5 with variance reduction parameters generated by ADVANTG. Because airflow through the shielding is important for open-mode repositories, a semi-empirical estimate of the head loss due to each shielding configuration was also calculated. Airflow and shielding performance vary widely among the proposed shielding configurations. Although the partial plug configuration had the best airflow performance, it allowed dose rates 1500 greater than the specified target. Labyrinthine shielding concepts yield doses on the order of 1 mrem/hour with configurations that impose 3 to 11 J/kg head loss. Adding 1 cm lead lining to the airflow channels of labyrinthine designs further reduces the worker dose by 65% to 95%. Photon-attenuator concepts may reduce worker dose to as low as 29 mrem/hour with head loss on the order of 1.9 J/kg.

Bevill, Aaron M [ORNL] [ORNL; Radulescu, Georgeta [ORNL] [ORNL; Scaglione, John M [ORNL] [ORNL; Howard, Rob L [ORNL] [ORNL

2013-01-01T23:59:59.000Z

414

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

SciTech Connect

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.

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

2002-02-26T23:59:59.000Z

415

Methods and Materials Sample Collection  

E-Print Network (OSTI)

collections for 7July-4 August 1961 survey. .. PACIFIC OCEAN . $lGH9 . . ~ ...56' 170· tS5- BE RI NG SEA ~ Ala

416

Final Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada  

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

TABLE OF CONTENTS Section Page 7. Repository Design, Performance, and Affected Environment .......................................................CR7-1 7.1 Repository Design ...........................................................................................................CR7-18 7.1.1 Draft EIS Repository Design ....................................................................................CR7-39 7.1.2 Supplement to the Draft EIS Flexible Design...........................................................CR7-62 7.1.2.1 Higher- and Lower-Temperature Operating Modes .................................................CR7-73 7.1.2.2 Ventilation.......................................................................................................CR7-74

417

Characterization, Propagation and Analysis of Aleatory and Epistemic Uncertainty in the 2008 Performance Assessment for the Proposed Repository for High-Level Radioactive Waste at Yucca Mountain, Nevada  

Science Journals Connector (OSTI)

The 2008 performance assessment (PA) for the proposed repository for high-level radioactive waste at Yucca Mountain (YM), Nevada, illustrates the conceptual...

Clifford W. Hansen; Jon C. Helton; Cédric J. Sallaberry

2010-01-01T23:59:59.000Z

418

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  

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

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

419

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)

geological disposal of spent CANDU fuel in Canada, a safetyhypothetical repository for spent CANDU fuel in the Canadianbuffer. The waste form: CANDU reactors in Canada are fuelled

Nguyen, T.S.

2009-01-01T23:59:59.000Z

420

Classification Schemes for Collection Mediation  

E-Print Network (OSTI)

of the author. #12;Abstract Work domain analysis and work centered design is a new approach to designClassification Schemes for Collection Mediation: Work Centered Design and Cognitive Work Analysis science. #12;Classification Schemes for Collection Mediation: Cognitive Work Analysis and Work Centered

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


421

Collective network for computer structures  

DOE Patents (OSTI)

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.

Blumrich, Matthias A; Coteus, Paul W; Chen, Dong; Gara, Alan; Giampapa, Mark E; Heidelberger, Philip; Hoenicke, Dirk; Takken, Todd E; Steinmacher-Burow, Burkhard D; Vranas, Pavlos M

2014-01-07T23:59:59.000Z

422

Collective network for computer structures  

DOE Patents (OSTI)

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.

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)

2011-08-16T23:59:59.000Z

423

Impacts of Stable Element Intake on C and I Dose Estimates - Implications for Proposed Yucca Mountain Repository  

SciTech Connect

The purpose of this study was to evaluate the influence of the intake of stable isotopes of carbon and iodine on the committed doses due to the ingestion of {sup 14}C and {sup 129}I. This was accomplished through the application of two different computational approaches. The first was based on the assumption that ground (drinking) water was the only source of intake of both {sup 14}C and {sup 129}I and stable carbon and stable iodine. For purposes of the second approach, the intake of {sup 14}C and {sup 129}I was still assumed to be only that in the ground (drinking) water, but the intake of stable carbon and stable iodine was assumed to be that in the drinking water plus other components of the diet. The doses were estimated using either a conversion formula or the applicable dose coefficients in Federal Guidance Reports No. 11 and No. 13. Serving as input for the analyses was the estimated maximum concentration of {sup 14}C or {sup 129}I that would be present in the ground water due to potential releases from the proposed Yucca Mountain high-level radioactive waste repository during the first 10,000 years after closure. The estimated concentrations of stable carbon and iodine were based on analyses of ground water samples collected in the Amargosa Valley, NV. Based on the accompanying analyses, three conclusions were reached. First, no dose estimate, using a conversion formula in which the ratios of the stable to radioactive isotopes of an element serve as input, should ever be made without including the stable element intake contributions from all components of the diet. Second, the study suggests that the dose coefficients for {sup 129}I in Federal Guidance Reports No. 11 and No. 12 which, in turn, are based on publications of the ICRP, may not be appropriate for application in developed nations of the world, especially those in which relatively large amounts of seafood are consumed and the use of iodized salt is common. The estimated average daily intake of stable iodine by the adult U.S. population, for example, is 400 pg. This is twice the value listed by the ICRP for Reference Man. This leads to a dose estimate that is too high by a factor of two. Although the ICRP accounts for stable isotope contributions through the selection of a corresponding biological half-time for iodine, the selection in this case may need reevaluation especially with respect to assessments of potential {sup 129}I releases from the proposed Yucca Mountain high-level radioactive waste repository. The third conclusion, which confirms earlier studies, is that an increase in the intake of either {sup 14}C or {sup 129}I will not lead to an increase in the dose if there is a corresponding increase in the intake of stable carbon or iodine such that the ratio of {sup 14}C or {sup 129}I to stable carbon or iodine does not change.

D.W. Moeller; M.T. Ryan; Lin-Shen C. Sun; R.N. Cherry Jr.

2004-12-21T23:59:59.000Z

424

Coherent X-ray Imaging Data Bank (CXIDB): An Open Repository for CXI Experimental Data  

DOE Data Explorer (OSTI)

Nowadays there are several groups around the world doing excellent work using different kinds of techniques all based on the physics of coherent X-ray imaging (CXI). Due to several reasons, including lack of a standard file format, there has been limited sharing of data which severely limits possible synergies inside the community. At the same time there is a population of researchers who do not have access to the facilities required to make such kinds of experiments, or do not have the expertise and resources necessary to carry them out. But many of them would be able to test new ideas and techniques if they would have access to the experimental data. The main goal of the Coherent X-ray Imaging Data Bank is to address these problems by creating an open repository for CXI experimental data. Such a repository provides several important benefits including: Expansion of the CXI community directly leading to an increase in the science output, the existence of an archival place for all the experimental data would ensure that such data does not gets lost forever when the group that did the experiment is no longer interested in the data, the availability of the experimental data to the entire community greatly facilitates reproducibility, leading to higher quality and more transparent science, the development of a well documented file format for CXI data facilitates data sharing and might one day lead to its emergence as a de facto standard. Current free electron laser facilities such as the LCLS are capable of producing very large amounts of data (20TB a day) and the coming European FEL is expected to increase this rate a factor of 500. The analyzes of such large bodies of data will have to be distributed through a large community to make it manageable, and this repository could be an important facilitator in this process.

425

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

SciTech Connect

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.

Dr. J.H. Payer

2006-04-18T23:59:59.000Z

426

Accelerated Dissolution Process of the Spent Fuel (UO{sub 2}) under Repository Conditions  

SciTech Connect

Nowadays, nuclear energy is one of the options for developed countries in order to maintain the demand of electric energy. One of the key problems associated with kind of energy generation is the residual waste formed after a fuel cycle (spent nuclear fuel). The thermal treatment received in the reactor and there composition renders these materials very difficult to characterize and thus exhaustive studies are required to obtain knowledge that will help to build a complete, reliable and very safety underground facility. In this way, the option known as the Deep Geological Repository (DGR) is under development by each country taking part in the nuclear energy industry. The unique pathway for the migration to the biosphere of the radionuclide, actinide and lanthanides content in the spent fuel pellet (UO{sub 2}) after the closing of the deep geological repository is by a water transport phenomena. It is a fundamental question to know how much time they will spend on their trip and the first step is the rate of liberation of these radionuclides from the spent fuel pellet. In this way the matrix dissolution rate of the spent fuel pellet, which is not dependent on the specific surface area after normalization by the initial value is a key parameter to begin the performance assessment for any deep geological repository. The specific surface value is, following the Matrix Alteration Model (MAM) sensitivity analysis, one of the most important parameters controlling the radionuclides liberation. In this way, several measurements were carried out to obtain values in different conditions for different sieves of UO{sub 2} powder treated as fresh fuel. First of all, the specific surface area was measured with a multi-point isothermal procedure with N{sub 2} and Kr for both. The values obtained are presented in order to obtain a general law for the rate of evolution with the particle size. These data are part of a bigger project about the complete description of the spent fuel analogues, which are very useful for obtaining new dissolution rates for spent nuclear fuel under repository simulated conditions. (authors)

Iglesias, Eduardo; Quinones, Javier; Rodriguez, Nieves [Energy, CIEMAT, Avda. Complutense 22, Madrid, 28040 (Spain)

2008-07-01T23:59:59.000Z

427

Convergence of Advances in Genomics, Team Science, and Repositories as Drivers of Progress in Psychiatric Genomics  

Science Journals Connector (OSTI)

Abstract After many years of unfilled promise, psychiatric genetics has seen an unprecedented number of successes in recent years. We hypothesize that the field has reached an inflection point through a confluence of four key developments: advances in genomics; the orientation of the scientific community around large collaborative team science projects; the development of sample and data repositories; and a policy framework for sharing and accessing these resources. We discuss these domains and their effect on scientific progress and provide a perspective on why we think this is only the beginning of a new era in scientific discovery.

Thomas Lehner; Geetha Senthil; Anjené M. Addington

2015-01-01T23:59:59.000Z

428

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

SciTech Connect

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.

Not Available

2012-02-01T23:59:59.000Z

429

CONTACTS FOR INFORMATION MANAGEMENT: Forms, Information Collection...  

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

CONTACTS FOR INFORMATION MANAGEMENT: Forms, Information Collection (PRA), & Records CONTACTS FOR INFORMATION MANAGEMENT: Forms, Information Collection (PRA), & Records Name Contact...

430

Data Collection, Analysis, and Reporting  

Office of Energy Efficiency and Renewable Energy (EERE)

The Data Collection, Analysis, and Reporting business line is responsive to the Office of Energy Efficiency and Renewable Energy's (EERE) need for timely, accurate, and detailed analysis reporting...

431

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

SciTech Connect

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)

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

1985-07-01T23:59:59.000Z

432

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

E-Print Network (OSTI)

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.

Alain Bourgeat; Mladen Jurak; Farid Smaď

2008-02-29T23:59:59.000Z

433

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

E-Print Network (OSTI)

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.

Bourgeat, Alain; Smaď, Farid

2008-01-01T23:59:59.000Z

434

Thermal Performance of Deep-Burn Fusion-Fission Hybrid Waste in a Repository  

SciTech Connect

The Laser Inertial Confinement Fusion Fission Energy (LIFE) Engine [1] combines a neutron-rich but energy-poor inertial fusion system with an energy-rich but neutron-poor subcritical fission blanket. Because approximately 80% of the LIFE Engine energy is produced from fission, the requirements for laser efficiency and fusion target performance are relaxed, compared to a pure-fusion system, and hence a LIFE Engine prototype can be based on target performance in the first few years of operation of the National Ignition Facility (NIF) at Lawrence Livermore National Laboratory (LLNL). Similarly, because of the copious fusion neutrons, the fission blanket can be run in a subcritical, driven, mode, without the need for control rods or other sophisticated reactivity control systems. Further, because the fission blanket is inherently subcritical, fission fuels that can be used in LIFE Engine designs include thorium, depleted uranium, natural uranium, spent light water reactor fuel, highly enriched uranium, and plutonium. Neither enrichment nor reprocessing is required for the LIFE Engine fuel cycle, and burnups to 99% fraction of initial metal atoms (FIMA) being fissioned are envisioned. This paper discusses initial calculations of the thermal behavior of spent LIFE fuel following completion of operation in the LIFE Engine [2]. The three time periods of interest for thermal calculations are during interim storage (probably at the LIFE Engine site), during the preclosure operational period of a geologic repository, and after closure of the repository.

Blink, J A; Chipman, V; Farmer, J; Shaw, H; Zhao, P

2008-11-25T23:59:59.000Z

435

Evaluation of radionuclide migration in the homogeneous system of a geological repository  

Science Journals Connector (OSTI)

The aim of this paper is to study radionuclide migration and release from a deep underground repository situated in a clay formation. An insight into the processes influencing the radionuclide transport in the near field and far field will be presented. For the calculation, a set of radionuclides has been chosen, considering the half-life, decay chains, capacity of the sorption, solubility limits and diffusion coefficients. The migration of radionuclides is dependent on transport properties of the particular nuclide. Due to the low hydraulic conductivity of the backfill material and clay geological formation, the transport in the repository occurs mainly by diffusion. The migration rate will be influenced by the water chemistry, solubility, retardation and diffusive properties of the nuclides, and the water flow rate in the clay. The release rates of radionuclides from the geosphere to the biosphere will be converted into the indicative dose rates using dose conversion factors for ingestion. The impact of the critical group is considered via consumption of meat, root vegetables and drinking water from wells.

S. Prvakova; J. Duran; V. Necas

2005-01-01T23:59:59.000Z

436

Selection of candidate canister materials for high-level nuclear waste containment in a tuff repository  

SciTech Connect

A repository located at Yucca Mountain at the Nevada Test Site is a potential site for permanent geological disposal of high-level nuclear waste. The repository can be located in a horizon in welded tuff, a volcanic rock, which is above the static water level at this site. The environmental conditions in this unsaturated zone are expected to be air and water vapor dominated for much of the containment period. Type 304L stainless steel is the reference material for fabricating canisters to contain the solid high-level wastes. Alternative stainless alloys are considered because of possible susceptibility of 304L to localized and stress forms of corrosion. For the reprocessed glass wastes, the canisters serve as the recipient for pouring the glass with the result that a sensitized microstructure may develop because of the times at elevated temperatures. Corrosion testing of the reference and alternative materials has begun in tuff-conditioned water and steam environments. 21 references, 8 figures, 8 tables.

McCright, R.D.; Weiss, H.; Juhas, M.C.; Logan, R.W.

1983-11-01T23:59:59.000Z

437

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

SciTech Connect

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)

Forsberg, C. [Massachusetts Institute of Technology, 77 Massachusetts Ave. Cambridge, MA 20129 (United States)

2013-07-01T23:59:59.000Z

438

Sequential evaluation of the potential geologic repository site at Yucca Mountain, Nevada, USA  

SciTech Connect

This paper discusses the changes that are planned for the characterization program at Yucca Mountain due to budget changes. Yucca Mountain is the only site being studied in the US for a geologic repository. Funding for the site characterization program at Yucca Mountain program was cut by roughly one half from the 1994 projected budget to complete three major milestones. These project milestones included: (1) a time-phased determination of site suitability, and if a positive finding, (2) completion of an Environmental Impact Statement, and (3) preparation of a License Application to the US NRC to authorize repository construction. In reaction, Yucca Mountain Site Characterization Project has shifted from parallel development of these milestones to a sequenced approach with the site suitability evaluation being replaced with a management assessment. Changes to the regulatory structure for the disposal program are under consideration by DOE and the NRC. The possibility for NRC and Doe to develop a site-specific regulatory structure follows from the National Energy Policy Act of 1992 that authorized the US EPA to develop a site specific environmental standard for Yucca Mountain.

Bjerstedt, T.W.

1996-12-31T23:59:59.000Z

439

Information Repository  

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

CBFO Job Opportunities Job Title Job Announcement Number Nuclear Engineer (Nuclear Safety Specialist) 15-CBFO-018-MP Nuclear Engineer (Nuclear Safety Specialist) 15-CBFO-018-DE...

440

Concurrent Collections Zoran Budimlic1  

E-Print Network (OSTI)

University 2 Intel Corporation 3 UCLA Abstract We introduce the Concurrent Collections (CnC) programming model. CnC supports flexible combinations of task and data parallelism while retaining determinism. CnC that together form a CnC graph. We formally describe the execution semantics of CnC and prove that the model

Budimliæ, Zoran

Note: This page contains sample records for the topic "repository leachate collection" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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441

Connectivity-based garbage collection  

Science Journals Connector (OSTI)

We introduce a new family of connectivity-based garbage collectors (Cbgc) that are based on potential object-connectivity properties. The key feature of these collectors is that the placement of objects into partitions is determined by performing ... Keywords: connectivity based garbage collection

Martin Hirzel; Amer Diwan; Matthew Hertz

2003-11-01T23:59:59.000Z

442

Supplemental Performance Analyses for the Potential High-Level Nuclear Waste Repository at Yucca Mountain  

SciTech Connect

The U.S. Department of Energy (DOE) is considering the possible recommendation of a site at Yucca Mountain, Nevada, for the potential development of a geologic repository for the disposal of high-level radioactive waste and spent nuclear fuel. To facilitate public review and comment, in May 2001 the DOE released the Yucca Mountain Science and Engineering Report (S&ER) (1), which presents technical information supporting the consideration of the possible site recommendation. The report summarizes the results of more than 20 years of scientific and engineering studies. Based on internal reviews of the S&ER and its key supporting references, the Total System Performance Assessment for the Site Recommendation (TSPA-SR) (2) and the Analysis Model Reports and Process Model Reports cited therein, the DOE has recently identified and performed several types of analyses to supplement the treatment of uncertainty in support of the consideration of a possible site recommendation. The results of these new analyses are summarized in the two-volume report entitled FY01 Supplemental Science and Performance Analysis (SSPA) (3,4). The information in this report is intended to supplement, not supplant, the information contained in the S&ER. The DOE recognizes that important uncertainties will always remain in any assessment of the performance of a potential repository over thousands of years (1). One part of the DOE approach to recognizing and managing these uncertainties is a commitment to continued testing and analysis and to the continued evaluation of the technical basis supporting the possible recommendation of the site, such as the analysis contained in the SSPA. The goals of the work described here are to provide insights into the implications of newly quantified uncertainties, updated science, and evaluations of lower operating temperatures on the performance of a potential Yucca Mountain repository and to increase confidence in the results of the TSPA described in the S&ER (1). The primary tool used to evaluate the implications of the three types of supplemental information described in the SSPA (3,4) is the Yucca Mountain integrated TSPA model.

Sevougian, S. D.; McNeish, J. A.; Coppersmith, K.; Jenni, K. E.; Rickertsen, L. D.; Swift, P. N.; Wilson, M. L.

2002-02-26T23:59:59.000Z

443

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

SciTech Connect

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)

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

2012-07-01T23:59:59.000Z

444

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

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

Component Library: Component Library: An Online Repository to Facilitate Building Energy Model Creation Preprint Katherine Fleming, Nicholas Long, and Alex Swindler To be presented at the ACEEE Summer Study on Energy Efficiency in Buildings Pacific Grove, California August 12-17, 2012 Conference Paper NREL/CP-5500-54710 May 2012 NOTICE The submitted manuscript has been offered by an employee of the Alliance for Sustainable Energy, LLC (Alliance), a contractor of the US Government under Contract No. DE-AC36-08GO28308. Accordingly, the US Government and Alliance retain a nonexclusive royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for US Government purposes. This report was prepared as an account of work sponsored by an agency of the United States government.

445

Design and Implementation of an International Training Program on Repository Development and Management  

SciTech Connect

Korea Hydro and Nuclear Power Co., Ltd. (KHNP) is an electric company in the Republic of Korea with twenty operational nuclear power plants and eight additional units that are either planned or currently under construction. Regulations require that KHNP manage the radioactive waste generated by their nuclear power plants. In the course of planning low, intermediate, and high level waste storage facilities, KHNP sought interaction with an acknowledged expert in the field of radioactive waste management and, consequently, contacted Sandia National Laboratories (SNL). KHNP has contracted with SNL to provide a year long training program on repository science. This paper discusses the design of the curriculum, specific plans for execution of the training program, and recommendations for smooth implementation of international training programs. (authors)

Vugrin, K.W. [Sandia National Laboratories Carlsbad Programs Group, Performance Assessment and Decision Analysis Department, Carlsbad, NM (United States); Twitchell, Ch.A. [Sandia National Laboratories, Carlsbad Programs Group, Center Business Operations Department, Carlsbad, NM (United States)

2008-07-01T23:59:59.000Z

446

Characterization of several plasters and one retarder for repository sealing mixtures. Final report  

SciTech Connect

Samples of plasters (i.e., calcium sulfate hemihydrate, CaSO4.1/2H/sup 2/0) from six sources and one plaster retarder from a different source were obtained and characterized by a combination of chemical and physical testing and by petrographic examination. The petrographic examination included x-ray diffraction, optical microscopy, differential thermal analysis, and scanning electron microscopy procedures. The intent of this work was twofold. One purpose was to determine if plaster per se could be used as an ingredient for cementitious mixtures intended for repository sealing applications, Previous experience had been with use of a proprietary admixture that contained plaster. The second purpose was to determine one or more methods of distinguishing between the alpha and beta forms of calcium sulfate hemihydrate. Keywords: nuclear wastes; plaster of paris; tables(data).

Buck, A.D.; Burkes, J.P.; Reinhold, R.E.

1985-09-01T23:59:59.000Z

447

Packaging Strategies for Criticality Safety for "Other" DOE Fuels in a Repository  

SciTech Connect

Since 1998, there has been an ongoing effort to gain acceptance of U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in the national repository. To accomplish this goal, the fuel matrix was used as a discriminating feature to segregate fuels into nine distinct groups. From each of those groups, a characteristic fuel was selected and analyzed for criticality safety based on a proposed packaging strategy. This report identifies and quantifies the important criticality parameters for the canisterized fuels within each criticality group to: (1) demonstrate how the “other” fuels in the group are bounded by the baseline calculations or (2) allow identification of individual type fuels that might require special analysis and packaging.

Larry L Taylor

2004-06-01T23:59:59.000Z

448

Repository sealing plan for the Nevada Nuclear Waste Storage Investigations Project, fiscal years 1984 through 1990  

SciTech Connect

This report presents a plan to develop acceptable sealing methods for a prospective nuclear waste repository in unsaturated tuff in Yucca Mountain, which is on and adjacent to the Nevada Test Site. Sealing is the permanent closure of the underground facility, shafts, ramps, and boreholes. Questiona associated with the performance of the sealing system form the basis for this plan. Tasks that contribute to the resolution of these questions and support the documentation required for the construction authorization application are proposed. The approach to answering the performance-related questions is divided into six steps: (1) assess the need for sealing, (2) define the design requirements, (3) measure the material properties, (4) assess the performance of sealing designs, (5) perform laboratory analyses and field testing, and (6) reassess the performance of sealing designs. Organization of the tasks supporting each step is illustrated by detailed work-flow diagrams.

Fernandez, J.A.

1985-02-01T23:59:59.000Z

449

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)

#12;2 efficiency; greenhouse gas emissions; electrolysis water use; levelized biofuels production cost Sustainability assessment of an integrated High Temperature Steam Electrolysis - enhanced Biomass to Liquid Fuel Electrolysis - enhanced Biomass to Liquid Fuel process Quentin Bernical,, Xavier Joulia, Isabelle Noirot

Boyer, Edmond

450

French Geological Repository Project for High Level and Long-Lived Waste: Scientific Programme  

SciTech Connect

The feasibility study presented in the Dossier 2005 Argile set out to evaluate the conditions for building, operating and managing a reversible disposal facility. The research was directed at demonstrating a potential for confining long-lived radioactive waste in a deep clay formation by establishing the feasibility of the disposal principle. Results have been enough convincing and a Planning Act was passed on 28 June, 2006. Decision in principle has been taken to dispose of intermediate and high level long-lived radioactive waste in a geological repository. An application file for a license to construct a disposal facility is requested by end of 2014 and its commissioning is planned for 2025. Based on previous results as well as on recommendations made by various Dossier 2005 evaluators, a new scientific programme for 2006-2015 has been defined. It gives details of what will be covered over the 2006-2015 period. Particular emphasis is placed on consolidating scientific data, increasing understanding of certain mechanisms and using a scientific and technical integration approach. It aims at integrating scientific developments and engineering advances. The scientific work envisaged beyond 2006 has the benefit of a unique context, which is direct access to the geological medium over long timescales. It naturally extends the research carried out to date, and incorporates additional investigations of the geological medium, and the preparation of demonstration work especially through full-scale tests. Results will aim at improving the representation of repository evolutions over time, extract the relevant parameters for monitoring during the reversibility phases, reduce the parametric uncertainties and enhance the robustness of models for performance calculations and safety analyses. Structure and main orientation of the ongoing scientific programme are presented. (author)

Landais, P.; Lebon, P.; Ouzounian, G. [Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA), 92 - Chatenay Malabry (France)

2008-07-01T23:59:59.000Z

451

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

SciTech Connect

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.

Mark Deinert; K.B. Cady

2011-09-04T23:59:59.000Z

452

Continuous Improvement and the Safety Case for the Waste Isolation Pilot Plant Geologic Repository - 13467  

SciTech Connect

The Waste Isolation Pilot Plant (WIPP) is a geologic repository 2150 feet (650 m) below the surface of the Chihuahuan desert near Carlsbad, New Mexico. WIPP permanently disposes of transuranic waste from national defense programs. Every five years, the U.S. Department of Energy (DOE) submits an application to the U.S. Environmental Protection Agency (EPA) to request regulatory-compliance re-certification of the facility for another five years. Every ten years, DOE submits an application to the New Mexico Environment Department (NMED) for the renewal of its hazardous waste disposal permit. The content of the applications made by DOE to the EPA for re-certification, and to the NMED for permit-renewal, reflect any optimization changes made to the facility, with regulatory concurrence if warranted by the nature of the change. DOE points to such changes as evidence for its having taken seriously its 'continuous improvement' operations and management philosophy. Another opportunity for continuous improvement is to look at any delta that may exist between the re-certification and re-permitting cases for system safety and the consensus advice on the nature and content of a safety case as being developed and published by the Nuclear Energy Agency's Integration Group for the Safety Case (IGSC) expert group. DOE at WIPP, with the aid of its Science Advisor and teammate, Sandia National Laboratories, is in the process of discerning what can be done, in a reasonably paced and cost-conscious manner, to continually improve the case for repository safety that is being made to the two primary regulators on a recurring basis. This paper will discuss some aspects of that delta and potential paths forward to addressing them. (authors)

Van Luik, Abraham; Patterson, Russell; Nelson, Roger [US Department of Energy, Carlsbad Field Office, 4021 S. National parks Highway, Carlsbad, NM 88220 (United States)] [US Department of Energy, Carlsbad Field Office, 4021 S. National parks Highway, Carlsbad, NM 88220 (United States); Leigh, Christi [Sandia National Laboratories Carlsbad Operations, 4100 S. National parks Highway, Carlsbad, NM 88220 (United States)] [Sandia National Laboratories Carlsbad Operations, 4100 S. National parks Highway, Carlsbad, NM 88220 (United States)

2013-07-01T23:59:59.000Z

453

A comparative application of the Repository Integration Program (RIP) to Total System Performance Assessment, 1991  

SciTech Connect

During Fiscal Year (FY) 1991 and FY 1992, Sandia National Laboratory and Battelle Pacific Northwest Laboratory were assigned the responsibility to generate initial Total System Performance Assessments (TSPAs) of the Yucca Mountain site. The analyses performed by these organizations (called TSPA-1991) are reported in Barnard et al(1992) and Eslinger et al. (1993). During this same time period, Golder Associates Inc. was assigned the task of generating a model capable of analyzing the total system performance of a high-level radioactive waste repository. The developed model, called Repository Integration Program (RIP), is documented in Kossik and Hachey (1993), Miller et al. (1993), and Golder Associates Inc. (1993). In FY 1993, the Civilian Radioactive Waste Management System Contractor was assigned the responsibility to plan, coordinate, and contribute to the second iteration of TSPA-2. Prior to initiating the next TSPA iteration, it was decided that it would be valuable to evaluate the applicability of RIP for use in this iteration. Therefore, analyses were conducted to compare the results generated by RIP to those reported in TSPA-1991. In particular, the aim was to generate a RIP input data set as equivalent as possible to that documented in Barnard et al. (1992) and to analyze the total system performance (as well as the performance of the individual subsystem components of the waste package/Engineered Barrier System (EBS), unsaturated gaseous flow and transport, unsaturated aqueous flow and transport, saturated flow and transport, and disruptive processes/events). The performance measure for comparison with the results of TSPA-1991 is the cumulative release of radionuclides to the accessible environment over a 10,000-year period following closure normalized to the US Environmental Protection Agency (EPA) release limits specified in 40 CFR 191.

NONE

1993-07-16T23:59:59.000Z

454

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

SciTech Connect

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.

Flach, G.

2009-12-11T23:59:59.000Z

455

Information Collection Management | Department of Energy  

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

Information Collection Management Information Collection Management The Paperwork Reduction Act (PRA) of 1995 requires each Federal agency to seek and obtain approval from the...

456

Advances in understanding solar energy collection materials  

NLE Websites -- All DOE Office Websites (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...

457

UESC Data Collection Update | Department of Energy  

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

UESC Data Collection Update UESC Data Collection Update Presentation-given at the April 2012 Federal Utility Partnership Working Group (FUPWG) meeting-provides an overview of...

458

THE WORLD'S Biggest Fan Collection  

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

WORLD'S Biggest Fan Collection WORLD'S Biggest Fan Collection If you only know the Big Ass Fan Company as the preeminent designer and manufacturer of high volume, low speed fans for factories and cows, it's time you get to know us better. While we continue to lead the way in industrial and agricultural air movement, we've also refined these designs to bring the same innovation and benefits of our famous fans to circulate an ocean of air in sound-sensitive commercial spaces and homes. And when our customers said they wanted something for smaller spaces, we listened - and we think you'll like the results. We've got you covered - ceiling to floor, wall to door! Features ď‚ž New patented airfoil system uses 10 Powerfoil airfoils, winglets and patent-pending AirFence(tm) technology to increase

459

Collective effects in the microlaser  

Science Journals Connector (OSTI)

In a microlaser experiment performed by An et al. with collaborators [Phys. Rev. Lett. 73, 3375 (1994)] an atomic beam interacts with a microcavity field under such conditions that the average number of atoms in the cavity is less than unity. However, due to the random statistics of atoms in the beam, the probability of two atoms being in the cavity simultaneously in time is not negligible. This must lead to collective two-atom effects that are not included in the standard microlaser model. We have developed a theory that incorporates such collective effects. This theory allows a better understanding of the observed experimental results and predicts some different features of the microlaser.

Mikhail I. Kolobov and Fritz Haake

1997-04-01T23:59:59.000Z

460

Apparatus for collecting solar energy  

SciTech Connect

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.

Wildenrotter, K.

1981-08-18T23:59:59.000Z

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


461

MONTICELLO NPL SITES  

Office of Legacy Management (LM)

April 1 - June 30, 2008 April 1 - June 30, 2008 DOE Site Manager: Jalena Maestas This report summarizes current project status, activities implemented during April through June 2008, and provides a schedule of planned near term activities, for the Monticello Mill Tailings Site (MMTS) and the Monticello Vicinity Properties (MVP) NPL sites. This report also includes repository and Pond 4 leachate collection data, quarterly site inspection results, and site meteorological monitoring data. 1.0 MMTS Activities/Status Repository and Pond 4 * Monthly and quarterly inspection of the repository identified no abnormalities. * Shrub seedlings planted last fall had a poor survival rate. * New damage to shrubs and vole infestation is not evident. * Monthly inspection of Pond 4 identified no abnormalities.

462

MONTICELLO NPL SITES  

Office of Legacy Management (LM)

.. ' \ MONTICELLO NPL SITES FFA QUARTERLY REPORT: October 1 -December 31, 2008 DOE Site Manager: Jalena Dayvault JR 7CJ7 This report summarizes current project status and activities implemented during October tiU'ough December 2008, and provides a schedule of planned near term activities for the Monticello MIII Tailings Site (MMTS) and the Monticello Vicinity Properties (MVP) NPL sites. This report also includes repository and Pond 4 leachate collection data, quarterly site inspection repmis, site meteorological data, and monitoring summary for tlw ex situ ground water treatment system. 1.0 MMTS Activities/Status Repository and Pond 4 · * Monthly and quarterly inspection of the repository identified no abnormalities (see attached repmis). .

463

Understanding Personal Digital Collections: An Interdisciplinary Exploration  

E-Print Network (OSTI)

, humanities, curatorship, digital collections ACM Classification Keywords H5.m. Information interfaces

Feinberg, Melanie

464

TNA Data Collection Tool | Department of Energy  

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

TNA Data Collection Tool TNA Data Collection Tool TNA Data Collection Tool The Training Needs Assessment (TNA) Data Collection Tool Instructions provides detailed guidance on how to complete the TNA Data Collection Tool. It is a good idea to print this document prior to completing 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. The training POC will enter mission critical training needs as well as competencies needed to meet their organization's mission. FY14 TNA Data Collection Tool Instructions FY14 TNA Data Collection Tool.xlsx Description FY14 TNA Data Collection Tool More Documents & Publications Reference Buildings by Building Type: Small office

465

DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Liberty High School, Bedford, Virginia: Session 2, March 24, 1986: Transcript of proceedings  

SciTech Connect

This document contains a transcript of the comments of 10 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository. (TEM)

Not Available

1986-01-01T23:59:59.000Z

466

DOE hearing on the Draft Area Recommendation Report for the Crystalline Repository Project, Liberty High School, Bedford, Virginia, Session 1: Transcript of proceedings  

SciTech Connect

This document contains a transcript of the comments of 52 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository. (TEM)

Not Available

1986-03-24T23:59:59.000Z

467

Uncertainty and sensitivity analysis for two-phase flow in the vicinity of the repository in the 1996 performance assessment for the Waste Isolation Pilot Plant: Undisturbed conditions  

SciTech Connect

Uncertainty and sensitivity analysis results obtained in the 1996 performance assessment for the Waste Isolation Pilot Plant are presented for two-phase flow the vicinity of the repository under undisturbed conditions. Techniques based on Latin hypercube sampling, examination of scatterplots, stepwise regression analysis, partial correlation analysis and rank transformation are used to investigate brine inflow, gas generation repository pressure, brine saturation and brine and gas outflow. Of the variables under study, repository pressure is potentially the most important due to its influence on spallings and direct brine releases, with the uncertainty in its value being dominated by the extent to which the microbial degradation of cellulose takes place, the rate at which the corrosion of steel takes place, and the amount of brine that drains from the surrounding disturbed rock zone into the repository.

HELTON,JON CRAIG; BEAN,J.E.; ECONOMY,K.; GARNER,J.W.; MACKINNON,ROBERT J.; MILLER,JOEL D.; SCHREIBER,JAMES D.; VAUGHN,PALMER

2000-05-19T23:59:59.000Z

468

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

Science Journals Connector (OSTI)

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 ...

Clifford W. Hansen; Jon C. Helton; Cédric J. Sallaberry

2010-09-01T23:59:59.000Z

469

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

E-Print Network (OSTI)

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

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

2004-01-01T23:59:59.000Z

470

Microbiological evaluation of the condition of cement compounds with radioactive wastes after long-term storage in near-surface repositories  

Science Journals Connector (OSTI)

Analysis of the core material taken by check drilling of a monolith of cemented radioactive waste in near-surface repositories operated for 15–45 years revealed the presence of damaged areas in the cement matr...

O. A. Gorbunova; A. S. Barinov

2012-04-01T23:59:59.000Z

471

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)

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 among these universities...

Mercer, Holly; Emmett, Ada

2005-10-01T23:59:59.000Z

472

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

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.

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

2010-09-03T23:59:59.000Z

473

Confidentiality and the Desire for Open Communication in the Transport of Radioactive Material to a National Repository  

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

Confidentiality, Security and Confidentiality, Security and Confidentiality, Security and Confidentiality, Security and the Desire for Open the Desire for Open Communication in the Communication in the Transport of Radioactive Transport of Radioactive Material to a National Material to a National Repository Repository A presentation to the A presentation to the DOE Transportation External Coordination (TEC) DOE Transportation External Coordination (TEC) Working Group Meeting Working Group Meeting Albuquerque, NM Albuquerque, NM 21 21 - - 23 April 2004 23 April 2004 Ronald B. Pope Consultant April 2004 April 2004 Confidentiality Confidentiality - - TEC Working TEC Working Group Group - - Albuquerque Albuquerque 2 2 Objectives Objectives Address and prompt TEC discussion on issues Address and prompt TEC discussion on issues

474

AN EVALUATION OF HYDROGEN INDUCED CRACKING SUSCEPTIBILITY OF TITANIUM ALLOYS IN US HIGH-LEVEL NUCLEAR WASTE REPOSITORY ENVIRONMENTS  

SciTech Connect

This paper evaluates hydrogen-induced cracking (HIC) susceptibility of titanium alloys in environments anticipated in the Yucca Mountain nuclear waste repository with particular emphasis on the. effect of the oxide passive film on the hydrogen absorption process of titanium alloys being evaluated. The titanium alloys considered in this review include Ti 2, 5 , 7, 9, 11, 12, 16, 17, 18, 24 and 29. In general, the concentration of hydrogen in a titanium alloy can increase due to absorption of atomic hydrogen produced from passive general corrosion of that alloy or galvanic coupling of it to a less noble metal. It is concluded that under the exposure conditions anticipated in the Yucca Mountain repository, the HIC of titanium drip shield will not occur because there will not be sufficient hydrogen in the metal even after 10,000 years of emplacement. Due to the conservatisms adopted in the current evaluation, this assessment is considered very conservative.

G. De; K. Mon; G. Gordon; D. Shoesmith; F. Hua

2006-02-21T23:59:59.000Z

475

Technical Design and Optimization of a HLW-Repository in the Gorleben Salt Dome including Detailed Design of the Sealing System - 13305  

SciTech Connect

The preliminary safety analysis for a HLW repository at Gorleben, the potential repository site in Germany, takes 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 'Safety Requirements Governing the Final Disposal of Heat-Generating Radioactive Waste' as at 30 September 2010. A repository design was developed for two emplacement concepts (drift disposal and borehole disposal) mainly influenced by the thermal impact of the heat-generating waste on the host rock and taking into account mining constrains. According to the objective to create the conditions for a safe containment of the waste containers in the host rock, a closure concept consisting of backfilling and sealing measures was developed. The repository was designed in such a way that retrievability requirements can be met for all waste containers within the operating phase of the repository. In addition, it could be shown that sufficient measures for ensuring subcriticality are provided both during the operational and the post-closure phases of the repository. (authors)

Bollingerfehr, W.; Filbert, W.; Herold, P.; Lerch, C.; Mueller-Hoeppe, N. [DBE TECHNOLOGY GmbH, Eschenstrasse 55, D-31224 Peine (Germany)] [DBE TECHNOLOGY GmbH, Eschenstrasse 55, D-31224 Peine (Germany); Charlier, F. [International nuclear safety engineering GmbH, Jesuitenstrasse 4, D-52062 Aachen (Germany)] [International nuclear safety engineering GmbH, Jesuitenstrasse 4, D-52062 Aachen (Germany); Kilger, R. [Gesellschaft fuer Anlagen und Reaktorsicherheit mbH (GRS), Boltzmannstr. 14, D-85748 Garching (Germany)] [Gesellschaft fuer Anlagen und Reaktorsicherheit mbH (GRS), Boltzmannstr. 14, D-85748 Garching (Germany)

2013-07-01T23:59:59.000Z

476

Analysis on the use of engineered barriers for geologic isolation of spent fuel in a reference salt site repository  

SciTech Connect

A perspective on the potential durability and effectiveness requirements for the waste form, container and other engineered barriers for geologic disposal of spent nuclear fuel has been developed. This perspective is based on calculated potential doses to individuals who may be exposed to radioactivity released from a repository via a groundwater transport pathway. These potential dose commitments were calculated with an integrated geosphere transport and bioshpere transport model. A sensitivity analysis was accomplished by varying four important system parameters, namely the waste radionuclide release rate from the repository, the delay prior to groundwater contact with the waste (leach initiation), aquifer flow velocity and flow path length. The nuclide retarding capacity of the geologic media, a major determinant of the isolation effectiveness, was not varied as a parameter but was held constant for a particular reference site. This analysis is limited to looking only at engineered barriers whose net effect is either to delay groundwater contact with the waste form or to limit the rate of release of radionuclides into the groundwater once contact has occurred. The analysis considers only leach incident scenarios, including a water well intrusion into the groundwater near a repository, but does not consider other human intrusion events or catastrophic events. The analysis has so far been applied to a reference salt site repository system and conclusions are presented.Basically, in nearly all cases, the regional geology is the most effective barrier to release of radionuclides to the biosphere; however, for long-lived isotopes of carbon, technetium and iodine, which were poorly sorbed on the geologic media, the geology is not very effective once a leach incident is initiated.

Cloninger, M.O.; Cole, C.R.; Washburn, J.F.

1980-12-01T23:59:59.000Z

477

THE INFLUENCE OF REPOSITORY THERMAL LOAD ON MULTIPHASE FLOW AND HEAT TRANSFER IN THE UNSATURATED ZONE OF YUCCA MOUNTAIN  

SciTech Connect

This paper investigates the impact of proposed repository thermal-loading on mountain-scale flow and heat transfer in the unsaturated fractured rock of Yucca Mountain, Nevada. In this context, a model has been developed to study the coupled thermal-hydrological (TH) processes at the scale of the entire Yucca Mountain. This mountain-scale TH model implements the current geological framework and hydrogeological conceptual models, and incorporates the latest rock thermal and hydrological properties. The TH model consists of a two-dimensional north-south vertical cross section across the entire unsaturated zone model domain and uses refined meshes near and around the proposed repository block, based on the current repository design, drift layout, thermal loading scenario, and estimated current and future climatic conditions. The model simulations provide insights into thermally affected liquid saturation, gas- and liquid-phase fluxes, and elevated water and rock temperature, which in turn allow modelers to predict the changes in water flux driven by evaporation/condensation processes, and drainage between drifts.

Yu-Shu Wu, Sumit Mukhopadhyay, Keni Zhang, and G. S. Bodvarsson

2006-04-16T23:59:59.000Z

478

Probabilistic risk assessment for salt repository conceptual design of subsurface facilities: A techical basis for Q-list determination  

SciTech Connect

Subpart G ''Quality Assurance'' of 10 CFR Part 60 requires that the US Department of Energy (DOE) apply a quality assurance program to ''all systems, structures, and components important to safety'' and to ''design and characterization of barriers important to waste isolation.'' In April 1986, DOE's Office of Geologic Repositories (OGR) issued general guidance for formulating a list of such systems, structures, and components---the Q-list. This guidance called for the use of probabilistic risk assessment (PRA) techniques to identify Q-list items. In this report, PRA techniques are applied to the underground facilities and systems described in the conceptual design report for the Salt Repository Project (SRP) in Deaf Smith County, Texas. Based on probability and dose consequence calculations, no specific items were identified for the Q-list. However, evaluation of the analyses indicated that two functions are important in precluding off-site releases of radioactivity: disposal container integrity; and isolation of the underground facility by the heating, ventilation, and air conditioning (HVAC) systems. Items related to these functions are recommended for further evaluation as the repository design progresses. 13 refs., 20 figs.

Chen, C.P.; Mayberry, J.J.; Shepherd, J.; Koza, H.; Rahmani, H.; Sinsky, J.

1987-12-01T23:59:59.000Z

479

Nye County Nuclear Waste Repository Project Office independent scientific investigations program annual report, May 1997--April 1998  

SciTech Connect

This annual summary report, prepared by the Nye County Nuclear Waste Repository Project Office (NWRPO), summarizes the activities that were performed during the period from May 1, 1997 to April 30, 1998. These activities were conducted in support of the Independent Scientific Investigation Program (ISIP) of Nye County at the Yucca Mountain Site (YMS). The Nye County NWRPO is responsible for protecting the health and safety of the Nye County residents. NWRPO`s on-site representative is responsible for designing and implementing the Independent Scientific Investigation Program (ISIP). Major objectives of the ISIP include: Investigating key issues related to conceptual design and performance of the repository that can have major impact on human health, safety, and the environment; identifying areas not being addressed adequately by the Department of Energy (DOE). Nye County has identified several key scientific issues of concern that may affect repository design and performance which were not being adequately addressed by DOE. Nye County has been conducting its own independent study to evaluate the significance of these issues. This report summarizes the results of monitoring from two boreholes and the Exploratory Studies Facility (ESF) tunnel that have been instrumented by Nye County since March and April of 1995. The preliminary data and interpretations presented in this report do not constitute and should not be considered as the official position of Nye County. The ISIP presently includes borehole and tunnel instrumentation, monitoring, data analysis, and numerical modeling activities to address the concerns of Nye County.

NONE

1998-07-01T23:59:59.000Z

480

CBNTiJALKESEARCHLIBRAKY DOCUMENT COLLECTION  

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

" 9 " 9 0 0 3 ' 9 ,^ r.V- ou 15 -^ CBNTiJALKESEARCHLIBRAKY DOCUMENT COLLECTION n P - - 5 9 0 0 3 1 9 DE05 900319 The Abundances of the Elements Hans E. Suess U.S. geological Surveys \, aeoiogififl and Harold C. Urey Department of Chemistry and Institute for Nuclear Studies University of Chicago ^ Chicagos Illinois ' i v j \ ^ \1>^ I 9 S S MASTDI *OSICE plStltJEFUKT I S ILLEGIBLE TO A A DES!?rB f l i f SpCSUTOE? SATISFACTORY REPRODUCTIOH DtSlUffiVnOR OF TMS KKUMERT fS BmiMfTED DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or

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


481

Data Collection Class-8.pub  

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

Long Haul Long Haul Operations and Fuel Economy Analysis Research Brief Oak Ridge National Laboratory managed by UT-Battelle, LLC for the U.S. Department of Energy under Contract number DE-AC05-00OR22725 Research Areas Freight Flows Passenger Flows Supply Chain Efficiency Transportation: Energy Environment Safety Security Vehicle Technologies A s part of a long-term study sponsored by the U.S. Department of Energy (DOE) Of- fice of Vehicle Technologies (OVT), the Oak Ridge National Laboratory (ORNL) in conjunction with a number of industry partners (Michelin Americas Research Company - Michelin), have collected data and information related to Class -8 heavy truck long-haul operations in real-world highway environments. Six Class-8 tractors and ten

482

Recent characterization activities of Midway Valley as a potential repository surface facility site  

SciTech Connect

Midway Valley, located at the eastern base of Yucca Mountain, Nye County, Nevada, has been identified as a possible location for the surface facilities of a potential high-level nuclear-waste repository. This structural and topographic valley is bounded by two north- trending, down-to-the-west normal faults: the Paintbrush Canyon fault on the east and the Bow Ridge fault on the west. Surface and near-surface geological data have been acquired from Midway Valley during the past three years with particular emphasis on evaluating the existence of Quaternary faults. A detailed (1:6000) surficial geological map has been prepared based on interpretation of new and existing aerial photographs, field mapping, soil pits, and trenches. No evidence was found that would indicate displacement of these surficial deposits along previously unrecognized faults. However, given the low rates of Quaternary faulting and the extensive areas that are covered by late Pleistocene to Holocene deposits south of Sever Wash, Quaternary faulting between known faults cannot be precluded based on surface evidence alone. Middle to late Pleistocene alluvial fan deposits (Unit Q3) exist at or near the surface throughout Midway Valley. Confidence is increased that the potential for surface fault rupture in Midway Valley can be assessed by excavations that expose the deposits and soils associated with Unit Q3 or older units (middle Pleistocene or earlier).

Gibson, J.D. [Sandia National Labs., Albuquerque, NM (United States); Wesling, J.R.; Swan, F.H.; Bullard, T.F. [Geomatrix Consultants, Inc., San Francisco, CA (United States)

1992-01-31T23:59:59.000Z

483

Underground facility area requirements for a radioactive waste repository at Yucca Mountain  

SciTech Connect

The Nevada Nuclear Waste Storage Investigations Project, managed by the US Department of Energy`s Nevada Operations Office, is examining the feasibility of siting a repository for high-level radioactive waste at Yucca Mountain on and adjacent to the Nevada Test Site. Preliminary waste descriptions and preliminary areal power density calculations have been completed, and the Topopah Spring Member has been recommended as the emplacement unit. Using these data, an effort has begun to determine the area needed for the underground facility. This report describes work performed to determine the area needed to emplace waste equivalent to 70,000 metric tons of uranium (MTU) initially loaded in commercial power reactors. The area needed for support functions is also described. The total area of the underground facility depends on the types of waste received, the amount of each type of waste received, the areal power density assumed, and the emplacement configuration chosen (horizontal or vertical emplacement). The areas range from about 1240 acres to about 1520 acres. For vertical emplacement of the reference inventory of spent fuel, 1520 acres are required. A significant finding of this report is the importance of low-heat-producing wastes (defense high-level waste, West Valley high-level waste, cladding hulls, transuranic waste, and spent fuel hardware) when calculating the area required for the underground facility. If other wastes are included and the spent fuel capacity is reduced consistent with a total capacity of 70,000 MTU, the area required will be smaller.

Mansure, A.J.

1985-11-01T23:59:59.000Z

484

Effects of microbial processes on gas generation under expected WIPP repository conditions: Annual report through 1992  

SciTech Connect

Microbial processes involved in gas generation from degradation of the organic constituents of transuranic waste under conditions expected at the Waste Isolation Pilot Plant (WIPP) repository are being investigated at Brookhaven National Laboratory. These laboratory studies are part of the Sandia National Laboratories -- WIPP Gas Generation Program. Gas generation due to microbial degradation of representative cellulosic waste was investigated in short-term (< 6 months) and long-term (> 6 months) experiments by incubating representative paper (filter paper, paper towels, and tissue) in WIPP brine under initially aerobic (air) and anaerobic (nitrogen) conditions. Samples from the WIPP surficial environment and underground workings harbor gas-producing halophilic microorganisms, the activities of which were studied in short-term experiments. The microorganisms metabolized a variety of organic compounds including cellulose under aerobic, anaerobic, and denitrifying conditions. In long-term experiments, the effects of added nutrients (trace amounts of ammonium nitrate, phosphate, and yeast extract), no nutrients, and nutrients plus excess nitrate on gas production from cellulose degradation.

Francis, A.J.; Gillow, J.B.

1993-09-01T23:59:59.000Z

485

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

DOE Data Explorer (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.

486

Assessment of uncertainties in measurement of pH in hostile environments characteristic of nuclear repositories  

SciTech Connect

This report focuses on evaluation and characteristics of sputtered thin film pH electrodes which can be used to assess the corrosivity of hot (100{degree}C) aqueous solutions present in nuclear repositories. Sputtered thin films have the advantages of high temperature capability, ruggedness, and low cost. The iridium oxide films were found to have a linear, 58 mV/pH, response to changes in pH. They had little hysteresis but drifted approximately 0.2 V over a period of two days exposure to pH 2--12 solutions. The films were found to be insensitive to interference from most ions such as alkali ions but had redox sensitivity to ferri-/ferrocyanide ions. Although special surface treatments were needed for the films for good adherence at 200{degree}C the films were not degraded after 20 hours exposure at pH 4, 7, and 10 at 200{degree}C. Ruthenium oxide sputtered films performed equally well to the iridium oxide films in parallel tests. The report also contains information on electrochemistry and testing of thin film electrodes and the characterization of the thin films by x-ray photoemission spectroscopy, ultraviolet photoemission spectroscopy, and ion scattering spectroscopy. 123 refs., 29 figs., 7 tabs.

Kreider, K.G.; Tarlov, M.J.; Huang, P.H. (National Inst. of Standards and Technology, Gaithersburg, MD (United States))

1991-10-01T23:59:59.000Z

487

Reaganomics and the use of collective rebates  

Science Journals Connector (OSTI)

The purpose of this article was to demonstrate that a collective rebate can be an effective tool to reduce ... -competitive policies in one package (a collective rebate) offers an opportunity to turn the public.....

William Orzechowski

1991-03-01T23:59:59.000Z

488

Intensifying the collective use of public place  

E-Print Network (OSTI)

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 ...

Aldrich, Darrell E. (Darrell Eugene)

1994-01-01T23:59:59.000Z

489

BIKE INFRASTRUCTURES Collecting knowledge of biking behavior  

E-Print Network (OSTI)

collection #12;2 A&D FILES ISSN: 1603-6204 VOLUME 51 TITEL Collecting knowledge of biking behavior into three sections (3 x 70 respondents, i.e. 210 respondents in total) ­ each section following the same

Hansen, René Rydhof

490

Processing of Audio-Visual Collections  

E-Print Network (OSTI)

DECEMBER 2012 Processing of AUDIO-VISUAL COLLECTIONS A sof June, 15 of the audio and video collections San FranciscoBay Area. The audio recordings provide broadcasts and talk

Diaz, Angel

2012-01-01T23:59:59.000Z

491

Anisotropic collective flow of a Lorentz gas  

E-Print Network (OSTI)

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

Nicolas Borghini; Clement Gombeaud

2011-06-30T23:59:59.000Z

492

marchand@cui.unige.ch Collection Guiding  

E-Print Network (OSTI)

marchand@cui.unige.ch Collection Guiding: Multimedia Collection Browsing and Visualization Stéphane Marchand-Maillet Viper ­ CVML ­ University of Geneva marchand@cui.unige.ch http://viper.unige.ch marchand Perspectives marchand@cui.unige.ch © http://viper.unige.ch ­ December 2004 3 Collection Guiding: Browsing

Genève, Université de

493

Home Energy Score Data Collection Sheet  

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

Energy Score - Data Collection 1 Energy Score - Data Collection 1 Revised 6/12/2013 Home Energy Scoring Tool Data Collection Sheet Location Information Address: ________________________________ City: ________________ State: _____ Zip: ______ Assessment Type: Initial / Test / Corrected / QA / Alternative EEM (Energy Efficiency Measures) / Final Assessment Date: _________________ Qualified Assessor: ______________________________ Comments: ________________________________________________________________________ __________________________________________________________________________________ __________________________________________________________________________________ __________________________________________________________________________________

494

Long-Term Environmental Monitoring of an Operating Deep Geologic Nuclear Waste Repository  

SciTech Connect

In the present energy dilemma in which we find ourselves, the magnitude of humanity's energy needs requires that we embrace a multitude of various energy sources and applications. Nuclear energy must be a major portion of the distribution. One often-cited strategic hurdle to the commercial production of nuclear energy is the apparent lack of an acceptable nuclear waste repository. This issue has been quietly addressed at the U. S. Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP; see http://www.wipp.energy.gov), the closest population center of significant size being Carlsbad, New Mexico. WIPP has been operating for about nine years, disposing of over 250,000 drum-equivalents of nuclear waste. From the standpoint of addressing operational and environmental risk, as well as public fear, WIPP h