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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.


1

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

E-Print Network [OSTI]

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

Recanati, Catherine

2

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

3

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

E-Print Network [OSTI]

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

Boyer, Edmond

4

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

5

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

E-Print Network [OSTI]

applica- tions such as biotechnology, catalysis, drug delivery, electronics, energy storage, magnetic correspondence concerning this service should be sent to the repository administrator: staff dimensional 1D nanowires NWs and nanotubes NTs were prepared by electrodeposition through the porous structure

Mailhes, Corinne

6

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

E-Print Network [OSTI]

) 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

7

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

E-Print Network [OSTI]

, Ph. ( 2010) CO2 sensing properties of semiconducting copper oxide and spinel ferrite nanocomposite concerning this service should be sent to the repository administrator: staff-oatao@inp-toulouse.fr. #12;CO2 layer for CO2 sensing based on semiconducting CuO­CuxFe3-xO4 (with 0 x 1) nanocom- posite was prepared

Mailhes, Corinne

8

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

9

Coal pile leachate treatment  

SciTech Connect (OSTI)

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

Davis, E C; Kimmitt, R R

1982-09-01T23:59:59.000Z

10

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

11

Repository performance confirmation.  

SciTech Connect (OSTI)

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

12

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

SciTech Connect (OSTI)

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

13

Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2009  

SciTech Connect (OSTI)

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

14

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

E-Print Network [OSTI]

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

15

Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2008  

SciTech Connect (OSTI)

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

16

Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2006  

SciTech Connect (OSTI)

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

R. L. Weiss

2007-05-30T23:59:59.000Z

17

Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2006  

SciTech Connect (OSTI)

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

R. L. Weiss

2007-12-05T23:59:59.000Z

18

Repository Performance Confirmation - 12119  

SciTech Connect (OSTI)

Repository performance confirmation links the technical bases of repository science and societal acceptance. Among the countless aspects of monitoring, performance confirmation holds a special place, involving distinct activities combining technical and social significance in radioactive waste management. Discussion is divided into four themes: 1. A distinction is drawn between performance confirmation monitoring and other testing and monitoring objectives, 2. A case study illustrates confirmation activities integrated within a long-term testing and monitoring strategy for Yucca Mountain, 3. A case study reviews compliance monitoring developed and implemented for the Waste Isolation Pilot Plant, and 4. An approach for developing, evaluating and implementing the next generation of performance confirmation monitoring is presented. International interest in repository monitoring is exhibited by the European Commission Seventh Framework Programme 'Monitoring Developments for Safe Repository Operation and Staged Closure' (MoDeRn) Project. The MoDeRn partners are considering the role of monitoring in a phased approach to the geological disposal of radioactive waste. As repository plans advance in different countries, the need to consider monitoring strategies within a controlled framework has become more apparent. The MoDeRn project pulls together technical and societal experts to assimilate a common understanding of a process that could be followed to develop a monitoring program. Experience from two repository programs in the United States sheds light on how performance confirmation has been executed. Lessons learned can help the next generation of performance confirmation. (author)

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

2012-07-01T23:59:59.000Z

19

Ion chromatographic analysis of oil shale leachates  

SciTech Connect (OSTI)

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

20

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

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

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

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

E-Print Network [OSTI]

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

Schrab, Gregory Ernst

1990-01-01T23:59:59.000Z

22

EVALUATION OF LEACHATE QUALITY FROM PENTACHLOROPHENOL, CREOSOTE AND ACA  

E-Print Network [OSTI]

-chlorinated phenols, resin acids and f~h toxicity. A quality assurance and quality control (QA/QC) program#12;EVALUATION OF LEACHATE QUALITY FROM PENTACHLOROPHENOL, CREOSOTE AND ACA PRESERVED WOOD PRODUCTS, total organic carbon, ammonia, metals, polynuclear aromatic hydrocarbons (PAH), chlorinated and non

23

Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2007  

SciTech Connect (OSTI)

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

R. L. Weiss; T. A. Lee

2008-06-25T23:59:59.000Z

24

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

25

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, and methane, and (2) negligible oxygen, nitrate, and sulfate concentrations. Methane concentrations and stable carbon isotope (13C) values suggest anaerobic methane oxidation was occurring within the plume and at its

Grossman, Ethan L.

26

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

SciTech Connect (OSTI)

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

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

1995-12-01T23:59:59.000Z

27

Groundwater and Leachate Monitoring and Sampling at ERDF, CY 2010  

SciTech Connect (OSTI)

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

28

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

SciTech Connect (OSTI)

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

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

2006-05-04T23:59:59.000Z

29

Membrane bioreactor technology: A novel approach to the treatment of compost leachate  

SciTech Connect (OSTI)

Highlights: • First membrane bioreactor treatment method for compost leachate. • No chemical additive or UV radiation source in this new biological method. • Removal rates of more than 99% for organics and ammonium were achieved. • Heavy metals were reduced by at least 82.7% except copper. - Abstract: Compost leachate forms during the composting process of organic material. It is rich in oxidizable organics, ammonia and metals, which pose a risk to the environment if released without proper treatment. An innovative method based on the membrane bioreactor (MBR) technology was developed to treat compost leachate over 39 days. Water quality parameters, such as pH, dissolved oxygen, ammonia, nitrate, nitrite and chemical oxygen demand (COD) were measured daily. Concentrations of caffeine and metals were measured over the course of the experiment using gas chromatography – mass spectrometry (GC/MS) and inductively coupled plasma – mass spectrometry (ICP–MS) respectively. A decrease of more than 99% was achieved for a COD of 116 g/L in the initial leachate. Ammonia was decreased from 2720 mg/L to 0.046 mg/L, while the nitrate concentration in the effluent rose to 710 mg/L. The bacteria in the MBR system adjusted to the presence of the leachate, and increased 4 orders of magnitude. Heavy metals were removed by at least 82.7% except copper. These successful results demonstrated the membrane bioreactor technology is feasible, efficient method for the treatment of compost leachate.

Brown, Kayleigh; Ghoshdastidar, Avik J.; Hanmore, Jillian [Department of Chemistry, Acadia University, Wolfville, NS, Canada B4P 2R6 (Canada); Frazee, James [E and Q Consulting and Associates Limited, Wolfville, NS, Canada B4P 2R1 (Canada); Tong, Anthony Z., E-mail: anthony.tong@acadiau.ca [Department of Chemistry, Acadia University, Wolfville, NS, Canada B4P 2R6 (Canada)

2013-11-15T23:59:59.000Z

30

Thermomechanical response of WIPP repositories  

SciTech Connect (OSTI)

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

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

1980-05-01T23:59:59.000Z

31

Energy Systems Laboratory: Building a Model Repository Collection  

E-Print Network [OSTI]

, and offices on the main campus of Texas A&M. The group consists of five faculty members from the Department of Mechanical Engineering, as well as three faculty members from the Departments of Architecture and Construction Science. The lab currently employs...

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

2008-06-05T23:59:59.000Z

32

EXTENDING GEOSPATIAL REPOSITORIES WITH GEOSEMANTIC PROXIMITY FUNCTIONALITIES  

E-Print Network [OSTI]

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

33

Reference repository design concept for bedded salt  

SciTech Connect (OSTI)

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

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

1980-10-08T23:59:59.000Z

34

Overburden effects on waste compaction and leachate generation in municipal landfills  

E-Print Network [OSTI]

, known as GasPro, which was developed by Stallard (1990) and an automatic gridding and filling scheme constructed by Beck (1994). Both the leachate production and the waste compaction portions of the model were found to be sensitive to the sequence...

Mehevec, Adam Wade

1994-01-01T23:59:59.000Z

35

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

E-Print Network [OSTI]

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

36

Optimisation of sanitary landfill leachate treatment in a sequencing batch reactor  

E-Print Network [OSTI]

- strength wastewater characterized by a low BOD/TKN ratio. Therefore, biological nitrogen removal can been demonstrated to be feasible for biological leachate treatment (EPA 1995). Nitrogen removal from), have been reported for wastewater treatment monitoring and control. In the present study a lab

37

Cost-Effective Cementitious Material Compatible with Yucca Mountain Repository Geochemistry  

SciTech Connect (OSTI)

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

Dole, LR

2004-12-17T23:59:59.000Z

38

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

39

MONITORED GEOLOGIC REPOSITORY SYSTEMS REQUIREMENTS DOCUMENT  

SciTech Connect (OSTI)

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

40

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

SciTech Connect (OSTI)

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

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

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

E-Print Network [OSTI]

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

Carmichael, Richard Charles

1979-01-01T23:59:59.000Z

42

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

SciTech Connect (OSTI)

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

43

License for the Konrad Deep Geological Repository  

SciTech Connect (OSTI)

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

44

Cost analysis of German waste repositories  

SciTech Connect (OSTI)

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

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

1993-12-31T23:59:59.000Z

45

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

SciTech Connect (OSTI)

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

46

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

47

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

SciTech Connect (OSTI)

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

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

2013-06-15T23:59:59.000Z

48

Fukushima Daiichi Information Repository FY13 Status  

SciTech Connect (OSTI)

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

Curtis Smith; Cherie Phelan; Dave Schwieder

2013-09-01T23:59:59.000Z

49

The German quality system for waste repositories  

SciTech Connect (OSTI)

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

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

1993-12-31T23:59:59.000Z

50

Applying insights from repository safety assessments.  

SciTech Connect (OSTI)

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

Swift, Peter N.

2010-03-01T23:59:59.000Z

51

Salt repository project closeout status report  

SciTech Connect (OSTI)

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

52

Status of Proposed Repository for Latin-American Spent Fuel  

SciTech Connect (OSTI)

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

Ferrada, J.J.

2004-10-04T23:59:59.000Z

53

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

54

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

SciTech Connect (OSTI)

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

55

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

E-Print Network [OSTI]

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

Percy, Richard Greer

1979-01-01T23:59:59.000Z

56

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

SciTech Connect (OSTI)

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

57

Monitored Geologic Repository Project Description Document  

SciTech Connect (OSTI)

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

58

Monitored Geologic Repository Project Description Document  

SciTech Connect (OSTI)

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

59

Cigeo, the French Geological Repository Project - 13022  

SciTech Connect (OSTI)

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

60

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

SciTech Connect (OSTI)

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

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

Espinosa Glaze Polychrome Bowl New Mexico Cultural Assets Digital Repository  

E-Print Network [OSTI]

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

Maccabe, Barney

62

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.

63

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

64

Repository Subsurface Preliminary Fire Hazard Analysis  

SciTech Connect (OSTI)

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

65

Monitored Geologic Repository Project Description Document  

SciTech Connect (OSTI)

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

66

Repository surface design site layout analysis  

SciTech Connect (OSTI)

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

67

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

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

68

Collection understanding  

E-Print Network [OSTI]

overview of the proposed architecture. Digital Image Collections DBMS CGI Ambient Slide Show Variably Gridded Thumbnails SERVER Streaming Collage CLIENT Figure 1. System overview. Figure 2 gives a high...

Chang, Michelle T.

2004-09-30T23:59:59.000Z

69

Large Plate Lysimeter Efficiency for Collecting Water Transported from Soil to Ground Water  

SciTech Connect (OSTI)

A large, zero-tension, plate lysimeter (3.05 x 2.13 m) was installed to intercept percolating soil water at Bikini Atoll (11 35'N, 165 25'E), a former nuclear test-site. In two experiments controlled amounts of irrigation water were applied over the lysimeter and leachate water was collected. Evapotranspiration (ET) calculations were made using the Penman-Monteith equation and climate data collected at the atoll. The efficiency of the lysimeter was essentially 100% in contrast to low efficiencies reported for smaller plate lysimeters. Lysimeter design, installation, and water balance results are discussed.

Robison, W; Stone, E L; Hamilton, T

2004-04-14T23:59:59.000Z

70

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

E-Print Network [OSTI]

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

Jenny, Bernhard

71

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

72

Viability Assessment of a Repository at Yucca Mountain  

Broader source: Energy.gov [DOE]

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

73

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

74

The DSpace Institutional Digital Repository System: Current Functionality  

E-Print Network [OSTI]

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

Tansley, Robert

2003-01-01T23:59:59.000Z

75

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

76

A Repository for Beyond-the-Standard-Model Tools  

SciTech Connect (OSTI)

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

77

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

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

78

An analysis of repository waste-handling operations  

SciTech Connect (OSTI)

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

79

Characteristics of potential repository wastes. Volume 2  

SciTech Connect (OSTI)

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

Not Available

1992-07-01T23:59:59.000Z

80

LIFE Materials: Fuel Cycle and Repository Volume 11  

SciTech Connect (OSTI)

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

Shaw, H; Blink, J A

2008-12-12T23:59:59.000Z

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

Integrating repositories with fuel cycles: The airport authority model  

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

82

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

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

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

83

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

SciTech Connect (OSTI)

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

84

Proceedings of the scientific visit on crystalline rock repository development.  

SciTech Connect (OSTI)

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

85

Transportation analysis for the concept of regional repositories  

SciTech Connect (OSTI)

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

86

Monte Carlo simulations for generic granite repository studies  

SciTech Connect (OSTI)

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

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

2010-12-08T23:59:59.000Z

87

Implementation of the Brazilian National Repository - RBMN Project - 13008  

SciTech Connect (OSTI)

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

88

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

89

The Proposed Yucca Mountain Repository From A Corrosion Perspective  

SciTech Connect (OSTI)

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

90

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

E-Print Network [OSTI]

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

McBrien, Peter

91

Nuclear waste repository transparency technology test bed demonstrations at WIPP  

SciTech Connect (OSTI)

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

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

2000-01-27T23:59:59.000Z

92

Impact of Pyrophoric Events on Long-Term Repository Performance  

SciTech Connect (OSTI)

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

93

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

94

Effect of repository underground ventilation on emplacement drift temperature control  

SciTech Connect (OSTI)

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

95

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

96

Environmental effects on corrosion in the Tuff repository  

SciTech Connect (OSTI)

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

97

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

98

Nevada potential repository preliminary transportation strategy Study 2. Volume 1  

SciTech Connect (OSTI)

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

99

Repository-relevant testing applied to the Yucca Mountain Project  

SciTech Connect (OSTI)

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

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

1989-04-01T23:59:59.000Z

100

Lithophysal Rock Mass Mechanical Properties of the Repository Host Horizon  

SciTech Connect (OSTI)

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

D. Rigby

2004-11-10T23:59:59.000Z

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

Expected brine movement at potential nuclear waste repository salt sites  

SciTech Connect (OSTI)

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

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

1987-08-01T23:59:59.000Z

102

Repository relevant testing applied to the Yucca Mountain Project  

SciTech Connect (OSTI)

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

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

1990-10-01T23:59:59.000Z

103

GEOLOGY, January 2007 1 GSA Data Repository item 2007010, Figures  

E-Print Network [OSTI]

GEOLOGY, January 2007 1 1 GSA Data Repository item 2007010, Figures DR1A (photo of speleothem PP1 and methods for uranium-series chronology), and DR2, (18 O and 13 C data), is available online at www 9140, Boulder, CO 80301, USA. Geology, January 2007; v. 35; no. 1; p.1­4; doi: 10.1130/G22865A.1; 3

Massachusetts at Amherst, University of

104

Current Status of The Romanian National Deep Geological Repository Program  

SciTech Connect (OSTI)

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

105

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

SciTech Connect (OSTI)

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

Not Available

1985-10-01T23:59:59.000Z

106

E-Print Network 3.0 - alternative repository criticality-control...  

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

approach called Product Data... a repository design that addresses the requirements. Section 4 concludes with an overview of how we plan Source: Bieman, James M. - Department...

107

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

108

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

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

and Information Sciences 83 Panel Organization 1. Panel on Structural Geology & Geoengineering Summary: in a repository, are thoroughly analyzed. Appendix E E-5 12;The study...

109

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

Broader source: Energy.gov [DOE]

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

110

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

E-Print Network [OSTI]

Mallants, D. , 2002. Gas generation and migration in Boomof Post-Disposal Gas Generation in a Repository for SpentCorrosion-Induced Gas Generation in a Nuclear Waste

Xu, T.

2009-01-01T23:59:59.000Z

111

TNA Data Collection Tool  

Broader source: Energy.gov [DOE]

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

112

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

SciTech Connect (OSTI)

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

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

1980-09-01T23:59:59.000Z

113

Converting repository storage criteria into rules for materials conditioning  

SciTech Connect (OSTI)

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

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

1993-12-31T23:59:59.000Z

114

Building of multilevel stakeholder consensus in radioactive waste repository siting  

SciTech Connect (OSTI)

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

115

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

SciTech Connect (OSTI)

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

116

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

SciTech Connect (OSTI)

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

117

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

118

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

119

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

120

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

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

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

E-Print Network [OSTI]

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

Godfrey, Michael W.

122

Version control: Answers 1. Create a directory in your svn repository.  

E-Print Network [OSTI]

Version control: Answers 1. Create a directory in your svn repository. Answer: For example: export the directory project_name in your user account (svn requires you to provide a log message using an editor the commit log. Answer: svn log 4. Checkout your repository into another directory. Make a commit from

Alavi, Ali

123

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

124

Immersion studies on candidate container alloys for the Tuff Repository  

SciTech Connect (OSTI)

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

125

Dessicant materials screening for backfill in a salt repository  

SciTech Connect (OSTI)

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

126

Hydrogeologic effects of natural disruptive events on nuclear waste repositories  

SciTech Connect (OSTI)

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

Davis, S.N.

1980-06-01T23:59:59.000Z

127

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

SciTech Connect (OSTI)

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

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

1986-06-01T23:59:59.000Z

128

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

SciTech Connect (OSTI)

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

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

2011-07-15T23:59:59.000Z

129

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 (OSTI)

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

130

Natural vegetation at the proposed Reference Repository Location in southeastern Washington  

SciTech Connect (OSTI)

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

131

THERMAL CONDUCTIVITY OF NON-REPOSITORY LITHOSTRATIGRAPHIC LAYERS  

SciTech Connect (OSTI)

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

R. JONES

2004-10-22T23:59:59.000Z

132

DOE Geothermal Data Repository - Tethering Data to Information: Preprint  

SciTech Connect (OSTI)

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

133

Generic repository design concepts and thermal analysis (FY11).  

SciTech Connect (OSTI)

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

134

Chemistry of transuranium elements in salt-base repository  

SciTech Connect (OSTI)

The mobility and potential release of actinides into the accessible environment continues to be the key performance assessment concern of nuclear repositories. Actinide, in particular plutonium speciation under the wide range of conditions that can exist in the subsurface is complex and depends strongly on the coupled effects of redox conditions, inorganic/organic complexation, and the extent/nature of aggregation. Understanding the key factors that define the potential for actinide migration is, in this context, an essential and critical part of making and sustaining a licensing case for a nuclear repository. Herein we report on recent progress in a concurrent modeling and experimental study to determine the speciation of plutonium, uranium and americium in high ionic strength Na-CI-Mg brines. This is being done as part of the ongomg recertification effort m the Waste Isolation Pilot Plant (WIPP). The oxidation-state specific solubility of actinides were established in brine as function of pC{sub H+}, brine composition and the presence and absence of organic chelating agents and carbonate. An oxidation-state invariant analog approach using Nd{sup 3+} and Th{sup 4+} was used for An{sup 3+} and An{sup 4+} respectively. These results show that organic ligands and hydrolysis are key factors for An(III) solubility, hydrolysis at pC{sub H+} above 8 is predominate for An(IV) and carbonates are the key factor for U(VI) solubility. The effect of high ionic strength and brine components measured in absence of carbonates leads to measurable increased in overall solubility over analogous low ionic strength groundwater. Less is known about the bioreduction of actinides by halo-tolerant microorganisms, but there is now evidence that bioreduction does occur and is analogous, in many ways, to what occurs with soil bacteria. Results of solubility studies that focus on Pitzer parameter corrections, new species (e.g. borate complexation), and the thermodynamic parameters for modeling are discussed.

Borkowski, Marian [Los Alamos National Laboratory; Reed, Donald T [Los Alamos National Laboratory; Lucchini, Jean - Francois [Los Alamos National Laboratory; Richmann, Michael K [Los Alamos National Laboratory; Khaing, H [Los Alamos National Laboratory; Swanson, J [Los Alamos National Laboratory; Ams, D [Los Alamos National Laboratory

2010-12-02T23:59:59.000Z

135

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

SciTech Connect (OSTI)

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

136

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

E-Print Network [OSTI]

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

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

2009-01-01T23:59:59.000Z

137

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...

138

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

139

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

140

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

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

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

142

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

SciTech Connect (OSTI)

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

143

Adapting Dry Cask Storage for Aging at a Geologic Repository  

SciTech Connect (OSTI)

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

144

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

SciTech Connect (OSTI)

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

Tsujimoto, Keiichi; Ahn, J.

1999-07-01T23:59:59.000Z

145

Utility Data Collection Service  

Broader source: Energy.gov [DOE]

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

146

UESC Data Collection Update  

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

Collection Template: Agency Facility State Utility Contract Type Contract Term Task OrderDeliver y Order Award Date Completion Date Energy Conservation Measures Implemented In...

147

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

SciTech Connect (OSTI)

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

148

Water, Vapor, and Salt Dynamics in a Hot Repository  

SciTech Connect (OSTI)

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

149

Mechanical interaction between rock, buffer and canister in repositories  

SciTech Connect (OSTI)

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

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

1993-12-31T23:59:59.000Z

150

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

E-Print Network [OSTI]

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

Mailhes, Corinne

151

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

E-Print Network [OSTI]

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

Mailhes, Corinne

152

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 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

153

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

E-Print Network [OSTI]

ParisTech researchers and makes it freely available over the web where possible. This is an author-deposited changes in microstructure and crystalline orientations and lead to residual stress generation. The study state and the influence of residual stress variations. 2. Experimental procedures 2.1. Material

154

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

E-Print Network [OSTI]

ParisTech researchers and makes it freely available over the web where possible. This is an author-deposited this version : Lucas BOUCINHA, Amine AMMAR, Anthony GRAVOUIL, Anthony NOUY - Ideal minimal residual in Applied Mechanics and Engineering (2014) 56-76" #12;Ideal minimal residual-based proper generalized

155

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

156

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

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

Boyer, Edmond

157

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

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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

158

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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

159

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

Boyer, Edmond

160

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

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

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.


161

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

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

Paris-Sud XI, Université de

162

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

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

Boyer, Edmond

163

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

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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

164

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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

165

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

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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

166

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

Paris-Sud XI, Université de

167

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

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

Paris-Sud XI, Université de

168

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

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

169

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

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Carbon Films for Micro-Supercapacitors. Science, vol. 328 (n° 5977). pp. 480-483. ISSN 1095-9203 Any-oatao@inp-toulouse.fr. #12;Monolithic Carbide-Derived Carbon Films for Micro-Supercapacitors John Chmiola,1 * Celine Largeot as power and temperature range of operation issues that are alleviated with the use of supercapacitors

Mailhes, Corinne

170

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

E-Print Network [OSTI]

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

171

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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

172

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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

173

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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

174

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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

175

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

Paris-Sud XI, Université de

176

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

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whole plant in twin-screw extruder: Influence of thermo-pressing conditions. (2012) Polymer Degradation fiberboards from cake generated during biorefinery of sunflower whole plant in twin-screw extruder: Influence, France Keywords: Sunflower whole plant Twin-screw extruder Lignocellulosic fibers Proteins Thermo

Paris-Sud XI, Université de

177

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

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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

178

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 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

179

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

Paris-Sud XI, Université de

180

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

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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

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

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

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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

182

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 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

183

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

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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

184

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

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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

185

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

E-Print Network [OSTI]

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

186

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

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

Paris-Sud XI, Université de

187

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

188

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loop. The recovery of the carbon reinforcement (based on the solvolysis of the matrix by water under VIABLE THE RECYCLING OF CARBON FIBER/THERMOSET MATRIX COMPOSITES. FIRST ELEMENTS OF STUDY - 2013 Any in Gothenburg 2013 MAKING VIABLE THE RECYCLING OF CARBON FIBER/THERMOSET MATRIX COMPOSITES. FIRST ELEMENTS

Boyer, Edmond

189

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

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dioxide (CO2). The two organic fluids are characterized by complex molecules and moderate to high recent studies suggest that supercritical Organic Rankine Cycles have a great potential for low architecture. In this work we investigate flows of dense gases through axial, multi-stage, supercritical ORC

Boyer, Edmond

190

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

191

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

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-Wen and Vivier , Vincent and Orazem, Mark E. and Pébère, Nadine and Tribollet, Bernard ( 2007) The Apparent Constant-Phase-Element Behavior of a Disk Electrode with Faradaic Reactions. Journal of The Electrochemical Author manuscript, published in "Journal of The Electrochemical Society (JES) vol. 154 (2007) C99-C107

192

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.04.036 To cite this version : Blanc, Christine and Orazem, Mark E. and Pébère, Nadine and Tribollet, Bernard Pierre et Marie Curie, 75252 Paris cedex 05, France Keywords: Local electrochemical impedance Galvanic of an electrode with geometry-induced current and potential distributions. 1. Introduction The electrochemical

Mailhes, Corinne

193

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

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-Wen and Vivier , Vincent and Orazem, Mark E. and Pébère, Nadine and Tribollet, Bernard ( 2007) The Apparent Constant-Phase-Element Behavior of an Ideally Polarized Blocking Electrode. Journal of The Electrochemical Author manuscript, published in "Journal of The Electrochemical Society (JES) vol. 154 (2007) C81-C88

Paris-Sud XI, Université de

194

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

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electrochemical impedance spectroscopy. KEYWORDS Adherence; Coil coating; Electrochemical impe- dance spectroscopy of a polymer. The trade mark ``Smoosteel'' is the property of ArcelorMittal (Montataire, France). Weight saving

Mailhes, Corinne

195

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.roucoules@utt.fr ABSTRACT Nowadays, the use of digital modelling through multiple CAx systems becomes more and more not data breakdown) and then are not yet efficient for CAx systems interoperability. The paper aims to integrate and merge multidisciplinary product data breakdown and to exchange them with other CAx

Paris-Sud XI, Université de

196

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

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Keywords: product design, eco-design, LCA, CAX modelling Abstract Integrating environmental aspects process and of eco-design (among the related software such as CAD, CAx, PLM, and LCA). This "digital

Boyer, Edmond

197

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

Mailhes, Corinne

198

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

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Department of Materials Science & Engineering, University of California, Los Angeles, California 90095, USA d-active materials. This property is of great interest for electrochemical capacitors because of the substantially levels of pseudocapacitance have been obtained with nanoscale materials, the development of practical

Boyer, Edmond

199

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

Boyer, Edmond

200

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

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

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

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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

202

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

Mailhes, Corinne

203

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

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

Paris-Sud XI, Université de

204

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

Paris-Sud XI, Université de

205

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

206

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

E-Print Network [OSTI]

] 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

207

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

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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

208

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

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-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

209

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of temperature, UV-light wavelength and intensity on polypropylene photothermal oxidation - Polymer Degradation, published in "Polymer Degradation and Stability 100, 1 (2014) 10-20" DOI : 10.1016/j.polymdegradstab.2013.12.038 #12;Influenceoftemperature,UV-light wavelengthandintensityon polypropylenephotothermaloxidation

Boyer, Edmond

210

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.-F. Colomer a,) , C. Stephan b , S. Lefrant b , G. Van Tendeloo c , I. Willems a , Z. Konya a , A. Fonseca

Boyer, Edmond

211

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

Boyer, Edmond

212

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

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

Mailhes, Corinne

213

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Drouet, Pierre Alphonse,,1 Jos´e Luis Garc´ia Fierro, and Abel Rousset Laboratoire de Chimie des Mat´eriaux Inorganiques et Energ´etiques, Universit´e Paul Sabatier, 118 Route de Narbonne, 31062 Toulouse Cedex 04

Mailhes, Corinne

214

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, Comisi´on Nacional de Energ´ia At´omica, 1650 San Martin, Buenos Aires, Argentina dSchool of Chemistry Sabatier, 31062 Toulouse, Cedex 4, France fDepartamento de Fisi´on Nuclear, Centro de Investigaciones Energ

Mailhes, Corinne

215

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Energ´ia At´omica, 1650 San Martin, Buenos Aires, Argentina dSchool of Chemistry, Monash University, Cedex 4, France fDepartamento de Fisi´on Nuclear, Centro de Investigaciones Energ

Paris-Sud XI, Université de

216

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

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. Real-time non-invasive Raman measurement has been performed on stationary vinyl chloride monomer of vinyl chloride (S-PVC) by a free-radical mechanism consists in dispersing liquid monomer under its-decomposition of the organic initiator into the vinyl chloride monomer (VCM). As a consequence, the reaction proceeds

Mailhes, Corinne

217

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performed on stationary vinyl chloride monomer droplets and has provided values of effective reaction orders into the vinyl chloride monomer (VCM). As a c, ThierryOnline Monitoring of Vinyl Chloride Polymerization in a Microreactor Using Raman Spectroscopy

Paris-Sud XI, Université de

218

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

Paris-Sud XI, Université de

219

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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

220

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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

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

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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

222

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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

223

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and Wu, Hsuan-Ta (2010) Flash Point Measurements and Modeling for Ternary Partially Miscible Aqueous-oatao@inp-toulouse.fr #12;Flash Point Measurements and Modeling for Ternary Partially Miscible Aqueous-Organic Mixtures@mail.cmu.edu.tw 1 #12;Flash Point Measurements and Modeling for Ternary Partially Miscible Aqueous-Organic Mixtures

Mailhes, Corinne

224

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

Mailhes, Corinne

225

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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

226

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, 2005). Hydrothermal reactions are also responsible for many ore processing and hydrothermal ( 2010) A thermosyphon-driven hydrothermal flow-through cell for in situ and time-resolved neutron-oatao@inp-toulouse.fr #12;A thermosyphon-driven hydrothermal flow-through cell for in situ and time-resolved neutron

Mailhes, Corinne

227

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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

228

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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

229

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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

230

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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

231

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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

232

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

Paris-Sud XI, Université de

233

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

Paris-Sud XI, Université de

234

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

Boyer, Edmond

235

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

Mailhes, Corinne

236

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

Mailhes, Corinne

237

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

Boyer, Edmond

238

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

Paris-Sud XI, Université de

239

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

Mailhes, Corinne

240

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

Mailhes, Corinne

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.


241

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

Boyer, Edmond

242

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level pose accuracy and to achieve a good path tracking. Unfortunately industrial robots are designed are concidered [4]. In [5], authors have worked on modeling the Cartesian compliance of an industrial robot the Accuracy of Industrial Robots by offline Compensation of Joints Errors - 2013 Any correspondence concerning

Paris-Sud XI, Université de

243

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. Delamination D. Optical microscopy a b s t r a c t A laser shock wave technique has been used to study the damage tolerance of T800/M21 CFRP (Carbon Fiber Reinforced Polymer) composite material with different lay_ups. Different levels of damage have been created according to various laser irradiation conditions. Several

Paris-Sud XI, Université de

244

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

Boyer, Edmond

245

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cycle assessment and genetic algorithms: application to PET bottles. (2012) Resources, Conservation and Recycling, vol. 69 . pp. 66-81. ISSN 0921-3449 Any correspondance concerning this service should be sent manuscript, published in "Resources, Conservation and Recycling vol. 69 (2012) pp. 66-81" DOI : 10.1016/j

Paris-Sud XI, Université de

246

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

Mailhes, Corinne

247

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

Mailhes, Corinne

248

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

Boyer, Edmond

249

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

Paris-Sud XI, Université de

250

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Métiers 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

251

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

Boyer, Edmond

252

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.g., Generation IV International Forum [3] and The Sustain- able Nuclear Energy Technology Platform [4 by chlorination: Part I. (2011) Journal of Nuclear Materials, vol. 414 . pp. 12-18. ISSN 0022-3115 #12;Recovery for recovery of actinides from spent nuclear fuel. The fuel is anodically dissolved to the molten salt

Mailhes, Corinne

253

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

Paris-Sud XI, Université de

254

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of Varistors Made From Zinc Oxide Nanoparticles Through Low Temperature Spark Plasma Sintering By Le´na Saint Made From Zinc Oxide Nanoparticles Through Low Temperature Spark Plasma Sintering. Advanced Functional Renaud, and Bruno Chaudret* 1. Introduction Zinc oxide is characterized by remarkable optical, thermal

Mailhes, Corinne

255

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

Paris-Sud XI, Université de

256

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

Boyer, Edmond

257

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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

258

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

Boyer, Edmond

259

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

Boyer, Edmond

260

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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

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,
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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

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- not be disposed but it must be transported to waste disposal sites to be treated. So, environmental and health of aver- age fluxes is observed beyond a given limit of transmembrane pressure. This fact was attributed

Mailhes, Corinne

262

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also a negative impact on environment; after uses, it can- not be disposed but it must be transported containing 0.2 g/l mannoprotein and 0.5 g/l pectin, a loss of aver- age fluxes is observed beyond a given to waste disposal sites to be treated. So, environmental and health restrictions force the oenology sector

Boyer, Edmond

263

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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

264

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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

265

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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

266

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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

267

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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

268

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with associated cost reduction, both in terms of operational expenditures (Opex) and capital expenditures (Capex, with the primary goal of reducing Opex, but less work deals with Capex reduction. The latter objective can

Paris-Sud XI, Université de

269

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and thermal processes integrated in ProSimPlusÃ? as a well-adapted process simulator for energy efficiency. The applicability of the proposed meth- odology in ProSimPlusÃ? 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

270

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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

271

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range of industrial applications such as Fluidized Catalytic Cracking (FCC), Chemical Looping Combustion, and biomass gasi- fication. Since few years, the development of computational ability and Computational Fluid

Mailhes, Corinne

272

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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

273

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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

274

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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

275

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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

276

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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

277

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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

278

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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

279

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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

280

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

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,
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to obtain the most current and comprehensive results.


281

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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

282

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

Paris-Sud XI, Université de

283

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

Paris-Sud XI, Université de

284

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

285

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­Al joining at a solid state with friction stir weld- ing. Similarly, Kahraman et al. (2007) have carried out with laser in welding­brazing regime whereas Ma et al. (2013) have carried out tungsten arc butt

Paris-Sud XI, Université de

286

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

287

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this version : Loreleï COMMIN, Myriam DUMONT, Jean-eric MASSE, Laurent BARRALLIER - Friction stir welding of AZ Materialia 57, 2 (2009) 326-334" DOI : 10.1016/j.actamat.2008.09.011 #12;Friction stir welding of AZ31 friction stir welding (FSW) and the resulting residual stresses of AZ31 Mg alloy were studied to get

288

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

289

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

Paris-Sud XI, Université de

290

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or future nuclear power plants considering various radiation en- vironments including normal and accidental facilities and for the new security systems to be implemented in existing nuclear power plants, spent on the vulnerability of advanced CMOS technologies to MGy dose environments. (2013) IEEE Transactions on Nuclear

Mailhes, Corinne

291

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modules, is developed for an industrial waste gasification process, in an industrial moving bed reactor Derived Fuel) waste for producing 12 MW. Drying, pyrolysis, combustion / gasification and plasma polishing Inert molten slag 1200°C Valuable fuel 1. WASTE TO FUEL Gasification Syngas Plasma Polishing Raw syngas

Paris-Sud XI, Université de

292

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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

293

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

Paris-Sud XI, Université de

294

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

Paris-Sud XI, Université de

295

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

Paris-Sud XI, Université de

296

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

Paris-Sud XI, Université de

297

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friendly since catalyst and surfactant are recycled and pure adipic acid is produced in high yield (70 of carpet fibers, upholstery, tire reinforcements, auto parts, and many other products (Castellan et al materials like nitrous oxide (N2O) in large amounts (0.3 metric ton emitted per metric ton of ADA produced

Paris-Sud XI, Université de

298

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strength, high thermal conductivity, excellent damping capacity, good castability, and recyclability, magnesium alloys have one major advan- tage over all other structural metallic materials: low density.1 by casting processes.3 Nowa- days, die-casting magnesium alloys are used in many auto- mobile parts

299

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

Mailhes, Corinne

300

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

Boyer, Edmond

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.


301

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

Paris-Sud XI, Université de

302

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

Mailhes, Corinne

303

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

Boyer, Edmond

304

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. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 204 2. Process equipment for the intensification of FAME production this version : Mazubert, Alex and Poux, Martine and Aubin, Joelle Intensified processes for FAME production administrator: staff-oatao@listes-diff.inp-toulouse.fr #12;Intensified processes for FAME production from waste

Mailhes, Corinne

305

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

Paris-Sud XI, Université de

306

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

Mailhes, Corinne

307

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-claude.bayeul-laine@ensam.eu Abstract. The present wind turbine is a small one which can be used on roofs or in gardens. This turbine has a vertical axis. Each turbine blade combines a rotating movement around its own axis and around. The benefits of combined rotating blades have been shown. The performance coefficient of this kind of turbine

Paris-Sud XI, Université de

308

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

Paris-Sud XI, Université de

309

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element simulation of magnesium alloys laser beam welding - Journal of Materials Processing Technology, published in "Journal of Materials Processing Technology 210, 9 (2010) 1131-1137" DOI : 10.1016/j energy density and shielding gases to protect the metal from the oxygen action. Basically, TIG and MIG

310

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

Mailhes, Corinne

311

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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

312

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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

313

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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

314

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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

315

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

Boyer, Edmond

316

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- Stochastic post-processing calculation of iron losses ­ application to a PMSM - COMPEL: The International : archiveouverte@ensam.eu #12;STOCHASTIC POST-PROCESSING CALCULATION OF IRON LOSSES - APPLICATION TO A PMSM M, the Monte-Carlo sampling method is used to calculate, in post- processing, the iron loss density in a PMSM

Boyer, Edmond

317

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

Paris-Sud XI, Université de

318

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

Paris-Sud XI, Université de

319

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

320

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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

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

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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

322

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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

323

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

Paris-Sud XI, Université de

324

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

Mailhes, Corinne

325

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

Mailhes, Corinne

326

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

SciTech Connect (OSTI)

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

none,

1982-07-01T23:59:59.000Z

327

Repository Surface Design Engineering Files Report Rev 00 ICN 1  

SciTech Connect (OSTI)

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

DOE

2001-05-08T23:59:59.000Z

328

Nevada potential repository preliminary transportation strategy: Study 1  

SciTech Connect (OSTI)

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

NONE

1995-04-01T23:59:59.000Z

329

UESC Data Collection Update  

Broader source: Energy.gov [DOE]

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

330

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

SciTech Connect (OSTI)

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

331

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

SciTech Connect (OSTI)

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

NONE

1998-07-01T23:59:59.000Z

332

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

SciTech Connect (OSTI)

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

333

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

SciTech Connect (OSTI)

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

334

Status of LANL investigations of temperature constraints on clay in repository environments  

SciTech Connect (OSTI)

The Used Fuel Disposition (UFD) Campaign is presently evaluating various generic options for disposal of used fuel. The focus of this experimental work is to characterize and bound Engineered Barrier Systems (EBS) conditions in high heat load repositories. The UFD now has the ability to evaluate multiple EBS materials, waste containers, and rock types at higher heat loads and pressures (including deep boreholes). The geologic conditions now available to the U.S.A. and the international community for repositories include saturated and reduced water conditions, along with higher pressure and temperature (P, T) regimes. Chemical and structural changes to the clays, in either backfill/buffer or clay-rich host rock, may have significant effects on repository evolution. Reduction of smectite expansion capacity and rehydration potential due to heating could affect the isolation provided by EBS. Processes such as cementation by silica precipitation and authigenic illite could change the hydraulic and mechanical properties of clay-rich materials. Experimental studies of these repository conditions at high P,T have not been performed in the U.S. for decades and little has been done by the international community at high P,T. The experiments to be performed by LANL will focus on the importance of repository chemical and mineralogical conditions at elevated P,T conditions. This will provide input to the assessment of scientific basis for elevating the temperature limits in clay barriers.

Caporuscio, Florie A [Los Alamos National Laboratory; Cheshire, Michael C [Los Alamos National Laboratory; Newell, Dennis L [Los Alamos National Laboratory; McCarney, Mary Kate [Los Alamos National Laboratory

2012-08-22T23:59:59.000Z

335

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

SciTech Connect (OSTI)

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

Choung, Sungwook [Pohang Univ. of Science and Technology (Korea, Republic of); Um, Wooyong [Pohang Univ. of Science and Technology (Korea, Republic of); Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Choi, Seho [Pohang Univ. of Science and Technology (Korea, Republic of); Francis, Arokiasamy J. [Pohang Univ. of Science and Technology (Korea, Republic of); Brookhaven National Laboratory (BNL), Upton, NY (United States); Kim, Sungpyo [Korea Univ., Sejong (Korea, Republic of); Park, Jin beak [Korea Radioactive Waste Agency (KORAD), Daejeon (Korea, Republic of); Kim, Suk-Hoon [FNC Technology Co., Seoul National University (Korea, Republic of)

2014-03-18T23:59:59.000Z

336

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

E-Print Network [OSTI]

Repository Creating and Evaluating Metadata for a Large Legacy Thesis Collection: From ?Vocational Agriculture? (1922) to ?Microemulsion-mediated syntheses? (2004) This project would not have been possible without the work of many..., Digital Initiatives, Texas A&M University Libraries Background: In the summer of 2012, Texas A&M University Libraries uploaded more than 16,000 retrospectively-digitized masters-level theses, dating from 1922 to 2004, into our DSpace institutional...

Potvin, Sarah; Creel, James Silas

2013-05-23T23:59:59.000Z

337

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

SciTech Connect (OSTI)

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

338

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

SciTech Connect (OSTI)

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

339

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

SciTech Connect (OSTI)

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

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

2006-03-01T23:59:59.000Z

340

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

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.


341

Portable data collection device  

DOE Patents [OSTI]

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

French, Patrick D. (Aurora, CO)

1996-01-01T23:59:59.000Z

342

Portable data collection device  

DOE Patents [OSTI]

The present invention provides a portable data collection device that has a variety of sensors that are interchangeable with a variety of input ports in the device. The various sensors include a data identification feature that provides information to the device regarding the type of physical data produced by each sensor and therefore the type of sensor itself. The data identification feature enables the device to locate the input port where the sensor is connected and self adjust when a sensor is removed or replaced. The device is able to collect physical data, whether or not a function of a time. 7 figs.

French, P.D.

1996-06-11T23:59:59.000Z

343

Sebastian Collected Issue 1  

E-Print Network [OSTI]

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

Sebastian

2002-01-01T23:59:59.000Z

344

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

SciTech Connect (OSTI)

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

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

1992-04-01T23:59:59.000Z

345

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

SciTech Connect (OSTI)

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

NONE

1990-08-01T23:59:59.000Z

346

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

SciTech Connect (OSTI)

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

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

1980-05-22T23:59:59.000Z

347

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

SciTech Connect (OSTI)

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

348

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

349

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

SciTech Connect (OSTI)

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

350

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

351

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

352

Information Collection Management Program  

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

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

353

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.

354

Burnett Collection / Frank Burnett (collector)  

E-Print Network [OSTI]

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

Handy, Todd C.

355

Biogeochemical changes at early stage after the closure of radioactive waste geological repository in South Korea  

E-Print Network [OSTI]

Biogeochemical changes at early stage after the closure of radioactive waste geological repository e Korea Radioactive Waste Agency (KORAD), 111, Daedeok-daero 989 beon-gil, Yuseong-gu, Daejeon 305 Organic waste a b s t r a c t Permanent disposal of low- and intermediate-level radioactive wastes

Ohta, Shigemi

356

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

E-Print Network [OSTI]

Sequential Thermo-Hydraulic Modeling of Variably Saturated Flow in High-Level Radioactive Waste-Malabry, France Key words: waste repository, geological disposal, thermo- hydraulic modeling Introduction The most developed a sequential model to predict the coupled thermo-hydraulic processes at a cell-scale radioactive

Boyer, Edmond

357

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

SciTech Connect (OSTI)

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

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

1980-09-01T23:59:59.000Z

358

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

359

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.

360

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

SciTech Connect (OSTI)

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

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

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

E-Print Network [OSTI]

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

Prasanna, Viktor K.

362

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

363

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

SciTech Connect (OSTI)

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

364

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

365

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

SciTech Connect (OSTI)

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

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

1989-01-01T23:59:59.000Z

366

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

367

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

368

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

369

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

370

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

SciTech Connect (OSTI)

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

371

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

SciTech Connect (OSTI)

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

372

Kraith Collected Issue 1  

E-Print Network [OSTI]

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

Lichtenberg, Jacqueline; Multiple Contributors

1974-01-01T23:59:59.000Z

373

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

374

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

SciTech Connect (OSTI)

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

375

COLLECTIONS Community History Collection/Anacostia Community Museum  

E-Print Network [OSTI]

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

Mathis, Wayne N.

376

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

SciTech Connect (OSTI)

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

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

1982-11-01T23:59:59.000Z

377

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

SciTech Connect (OSTI)

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

Hanke, P.M.

1987-11-04T23:59:59.000Z

378

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

SciTech Connect (OSTI)

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

379

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

SciTech Connect (OSTI)

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

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

1983-05-01T23:59:59.000Z

380

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

SciTech Connect (OSTI)

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

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

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

SciTech Connect (OSTI)

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

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

1983-11-01T23:59:59.000Z

382

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

E-Print Network [OSTI]

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

American Society for Testing and Materials. Philadelphia

2009-01-01T23:59:59.000Z

383

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

SciTech Connect (OSTI)

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

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

2004-05-11T23:59:59.000Z

384

Collective systems for creative expression  

E-Print Network [OSTI]

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

Ar?kan, Harun Burak

2006-01-01T23:59:59.000Z

385

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

SciTech Connect (OSTI)

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

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

1986-12-01T23:59:59.000Z

386

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

SciTech Connect (OSTI)

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

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

1991-07-01T23:59:59.000Z

387

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

SciTech Connect (OSTI)

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

388

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

SciTech Connect (OSTI)

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

389

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

SciTech Connect (OSTI)

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

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

2012-05-01T23:59:59.000Z

390

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

SciTech Connect (OSTI)

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

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

1993-12-31T23:59:59.000Z

391

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

SciTech Connect (OSTI)

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

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

1992-02-01T23:59:59.000Z

392

A comparison of two potential repositories: The Waste Isolation Pilot Plant and Yucca Mountain  

SciTech Connect (OSTI)

Two repositories in the same country, yet Congress and the DOE manage them differently. While Congress encumbers WIPP with unanticipated oversight and inappropriate regulations, Congress streamlines the commercial repository program and promises improved regulations for Yucca Mountain. While DOE encouraged science at the expense of the WIPP infrastructure, DOE postponed its scientific investigations at Yucca Mountain and constructed an infrastructure, large enough to support an ambitious program that was never realized. Somewhere between WIPP and Yucca Mountain lies an ideal repository program. A program where consistent national policy promotes progress; where lucid regulations inspire confidence; where science and infrastructure are balanced; and where oversight groups do not become the tail that wags the dog. Neither WIPP nor Yucca Mountain are ideal programs, but each has its advantages that approach the ideal. Consistent national policy would steer the ideal repository program in a predictable direction. Here Yucca Mountain has the advantage. Successive legislation has streamlined the siting process and promises better regulations. From the beginning, the ideal program would know its regulators and regulations. Again, Yucca Mountain has the advantage. More familiar with regulators and regulations, the Yucca Mountain program had the foresight not to declare HLW to be hazardous and subject to dual regulations. The ideal program would equitably balance its science and infrastructure. Here neither program has the advantage and could possibly represent extremes. The WIPP`s emphasis on scientific investigations left it with little or no infrastructure to deal with regulations and oversight. A regulatory infrastructure, for example, could have forewarned WIPP that its in situ tests were not relevant to the regulations. On the opposite extreme, the Yucca Mountain`s emphasis on infrastructure left it with less money for scientific investigations.

Pflum, C.G.

1994-07-11T23:59:59.000Z

393

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

394

Houghton Library Collection Development Guidelines  

E-Print Network [OSTI]

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

Liu, X. Shirley

395

Collection Management Policy Executive Summary  

E-Print Network [OSTI]

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

Levi, Ran

396

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

SciTech Connect (OSTI)

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

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

1987-10-01T23:59:59.000Z

397

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

SciTech Connect (OSTI)

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

McNulty, E.G.

1987-08-01T23:59:59.000Z

398

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

SciTech Connect (OSTI)

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

399

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

SciTech Connect (OSTI)

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

400

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

SciTech Connect (OSTI)

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

K.C. Holt

2006-03-13T23:59:59.000Z

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

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

SciTech Connect (OSTI)

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

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

2001-02-01T23:59:59.000Z

402

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

Broader source: Energy.gov [DOE]

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

403

CHAPTER 1. COLLECTIVE PLASMA PHENOMENA 1 Collective Plasma  

E-Print Network [OSTI]

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

Callen, James D.

404

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

405

EM Launches Comprehensive Flickr Collection  

Broader source: Energy.gov [DOE]

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

406

Bentonite alteration due to thermal-hydro-chemical processes during the early thermal period in a nuclear waste repository  

SciTech Connect (OSTI)

After closure of an underground nuclear waste repository, the decay of radionuclides will raise temperature in the repository, and the bentonite buffer will resaturate by water inflow from the surrounding host rock. The perturbations from these thermal and hydrological processes are expected to dissipate within hundreds to a few thousand years. Here, we investigate coupled thermal-hydro-chemical processes and their effects on the short-term performance of a potential nuclear waste repository located in a clay formation. Using a simplified geometric configuration and abstracted hydraulic parameters of the clayey formation, we examine geochemical processes, coupled with thermo-hydrologic phenomena, and potential changes in porosity near the waste container during the early thermal period. The developed models were used for evaluating the mineral alterations and potential changes in porosity of the buffer, which can affect the repository performance. The results indicate that mineral alteration and associated changes in porosity induced by early thermal and hydrological processes are relatively small and are expected to not significantly affect flow and transport properties. Chlorite precipitation was obtained in all simulation cases. A maximum of one percent volume fraction of chlorite could be formed, whose process may reduce swelling and sorption capacity of bentonite clay, affecting the performance of the repository. llitisation process was not obtained from the present simulations.

Xu, T.; Senger, R.; Finsterle, S.

2011-02-01T23:59:59.000Z

407

Tritium monitor and collection system  

DOE Patents [OSTI]

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

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

1992-01-01T23:59:59.000Z

408

Tritium monitor and collection system  

DOE Patents [OSTI]

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

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

1992-01-14T23:59:59.000Z

409

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

SciTech Connect (OSTI)

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

NONE

1998-04-01T23:59:59.000Z

410

Diffusion Dominant Solute Transport Modelling In Deep Repository Under The Effect of Emplacement Media Degradation - 13285  

SciTech Connect (OSTI)

Deep geologic disposal of high activity and long-lived radioactive waste is being actively considered and pursued in many countries, where low permeability geological formations are used to provide long term waste contaminant with minimum impact to the environment and risk to the biosphere. A multi-barrier approach that makes use of both engineered and natural barriers (i.e. geological formations) is often used to further enhance the containment performance of the repository. As the deep repository system subjects to a variety of thermo-hydro-chemo-mechanical (THCM) effects over its long 'operational' lifespan (e.g. 0.1 to 1.0 million years, the integrity of the barrier system will decrease over time (e.g. fracturing in rock or clay)). This is broadly referred as media degradation in the present study. This modelling study examines the effects of media degradation on diffusion dominant solute transport in fractured media that are typical of deep geological environment. In particular, reactive solute transport through fractured media is studied using a 2-D model, that considers advection and diffusion, to explore the coupled effects of kinetic and equilibrium chemical processes, while the effects of degradation is studied using a pore network model that considers the media diffusivity and network changes. Model results are presented to demonstrate the use of a 3D pore-network model, using a novel architecture, to calculate macroscopic properties of the medium such as diffusivity, subject to pore space changes as the media degrade. Results from a reactive transport model of a representative geological waste disposal package are also presented to demonstrate the effect of media property change on the solute migration behaviour, illustrating the complex interplay between kinetic biogeochemical processes and diffusion dominant transport. The initial modelling results demonstrate the feasibility of a coupled modelling approach (using pore-network model and reactive transport model) to examine the long term behaviour of deep geological repositories with media property change under complex geochemical conditions. (authors)

Kwong, S. [National Nuclear Laboratory (United Kingdom)] [National Nuclear Laboratory (United Kingdom); Jivkov, A.P. [Research Centre for Radwaste and Decommissioning and Modelling and Simulation Centre, University of Manchester (United Kingdom)] [Research Centre for Radwaste and Decommissioning and Modelling and Simulation Centre, University of Manchester (United Kingdom)

2013-07-01T23:59:59.000Z

411

Collective neutrino oscillations in supernovae  

SciTech Connect (OSTI)

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

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

2014-06-24T23:59:59.000Z

412

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

413

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

SciTech Connect (OSTI)

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

414

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

SciTech Connect (OSTI)

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

415

Environmental Impacts of Transportation to the Potential Repository at Yucca Mountain  

SciTech Connect (OSTI)

The 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 analyzes a Proposed Action to construct, operate, monitor, and eventually close a geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste. As part of the Proposed Action, the EIS analyzes the potential impacts of transporting commercial and DOE spent nuclear fuel and high-level radioactive waste to Yucca Mountain from 77 sites across the United States. The analysis includes information on the comparative impacts of transporting these materials by truck and rail and discusses the impacts of building a rail line or using heavy-haul trucks to move rail casks from a mainline railroad in Nevada to the site. This paper provides an overview of the analyses and the potential impacts of these transportation activities. The potential transportation impacts were looked at from two perspectives: transportation of spent nuclear fuel and high-level radioactive waste by legal-weight truck or by rail on a national scale and impacts specific to Nevada from the transportation of these materials from the State borders to the Yucca Mountain site. In order to address the range of impacts that could result from the most likely modes, legal-weight truck and rail, the EIS employed two analytical scenarios--mostly legal-weight truck and mostly rail. Estimated national transportation impacts were based on 24 years of transportation activities. Approximately 8 fatalities could occur from all causes in the nationwide general population from incident-free transportation activities of the mostly legal-weight truck scenario and about 4 from the mostly rail scenario. The analysis examined the radiological consequences under the maximum foreseeable accident scenario and also overall accident risk. The overall accident risk over the 24 year period would be about 0.0002 latent cancer fatality for the mostly legal-weight truck scenario and about 0.0005 latent cancer fatality for the mostly rail scenario. The maximum reasonably foreseeable accident scenario resulted in 0.55 latent cancer fatality for the legal-weight truck case and 5 latent cancer fatalities in the case of mostly rail. The EIS also analyzed the impacts associated with the transportation of spent nuclear fuel and high-level radioactive waste in the State of Nevada. This included: constructing a branch rail line and using it to ship waste to the repository; upgrading highways in Nevada for use by heavy-haul trucks; constructing and operating an intermodal transfer station; and transporting personnel and materials to support construction and operation of the repository.

R.L. Sweeney; R. Best; P. Bolton; P. Adams

2002-01-03T23:59:59.000Z

416

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

417

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

418

Faris Committee Collection / Gordon Selman (collector)  

E-Print Network [OSTI]

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

Handy, Todd C.

419

New developments in measurement technology relevant to the studies of deep geological repositories in domed salt and basalt  

SciTech Connect (OSTI)

This report briefly describes recent geophysical and geotechnical instrumentation developments relevant to the studies of deep geologic repositories. Special emphasis has been placed on techniques that appear to minimize measurement problems associated with repositories constructed in basalt or domed salt. Included in the listing are existing measurement capabilities and deficiencies that have been identified by a few authors and instrumentation workshops that have assessed the capabilities of existing instrumentation with respect to repository applications. These deficiencies have been compared with the reported advantages and limitations of the new developments described. Based on these comparisons, areas that merit further research and development have been identified. The report is based on a thorough literature review and on discussions with several instrumentation specialists involved in instrumentation development.

Ramirez, A.L.; Mao, N.H.

1980-05-21T23:59:59.000Z

420

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

SciTech Connect (OSTI)

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

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

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 Smaï

2008-02-29T23:59:59.000Z

422

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; Smaï, Farid

2008-01-01T23:59:59.000Z

423

Paleoclimatic data applications: Long-term performance of uranium mill tailings repositories  

SciTech Connect (OSTI)

Abandoned uranium mill tailings sites in the Four Corners region are a lasting legacy of the Cold War. The U.S. Department of Energy (DOE) is designing landfill repositories that will isolate hazardous constituents of tailings from biological intrusion, erosion, and the underlying aquifer for up to 1,000 years. With evidence of relatively rapid past climate change, and model predictions of global climatic variation exceeding the historical record, DOE recognizes a need to incorporate possible ranges of future climatic and ecological change in the repository design process. In the Four Corners region, the center of uranium mining and milling activities in the United States, proxy paleoclimatic records may be useful not only as a window on the past, but also as analogs of possible local responses to future global change. We reconstructed past climate change using available proxy data from tree rings, packrat middens, lake sediment pollen, and archaeological records. Interpretation of proxy paleoclimatic records was based on present-day relationships between plant distribution, precipitation, and temperature along a generalized elevational gradient for the region. For the Monticello, Utah, uranium mill tailings site, this first approximation yielded mean annual temperature and precipitation ranges of 2 to 10{degrees} C, and 38 to 80 cm, respectively, corresponding to late glacial and Altithermal periods. These data are considered to be reasonable ranges of future climatic conditions that can be input to evaluations of groundwater recharge, radon-gas escape, erosion, frost penetration, and biointrusion in engineered earthen barriers designed to isolate tailings.

Waugh, W.J. [Environmental Sciences Lab., Grand Junction, CO (United States); Petersen, K.L. [Washington State Univ., Richland, WA (United States)

1995-09-01T23:59:59.000Z

424

Application of oil exploration techniques toward finding a nuclear waste repository site  

SciTech Connect (OSTI)

Through its National Waste Terminal Storage (NWTS) Program, the U.S. Department of Energy is responsible for providing facilities to permanently dispose of high-level nuclear waste in a manner that will ensure public health and safety and that will be environmentally acceptable. Three separately coordinated projects, which have placed emphasis on deep, underground repositories are described. They are the Basalt Waste Isolation Project at the Hanford Reservation in Wahington, the Nevada Nuclear Waste Storage investigations at the Nevada Test Site, and a project focusing on suitable rock types in the remainder of the conterminous 48 states, managed by the Office of Nuclear Waste Isolation in Columbus, Ohio. The last-mentioned project is presently focused on rock salt and crystalline formations as suitable host rocks for a repository. The geologic evaluation considers stratigraphy, structure, hydrogeology, seismicity, tectonic history, Quaternary features, physiography, energy/mineral resources, and geotechnical factors. Extensive use has been made of drill stem test data, a mainstay of petroleum exploration since the late 1920`s, to obtain hydrologic information. (JMT)

Laughon, R.B.

1982-06-01T23:59:59.000Z

425

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

SciTech Connect (OSTI)

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

426

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

SciTech Connect (OSTI)

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

427

Stability of ceramic waste forms in potential repository environments: a review  

SciTech Connect (OSTI)

Most scenarios for geologic disposal of high-level nuclear waste include the eventual intrusion of groundwater into the repository. Reactions in the system and eventual release of the radionuclides, if any, will be controlled by the chemistry of the groundwater, the surrounding rock, the waste form, and any engineered barrier materials that are present, as well as by the temperature and pressure of the system. This report is a compilation and evaluation of the work completed to date on interactions within the waste-form/host-rock/groundwater system at various points in its lifetime. General results from leaching experiments are presented as a basis for comparison. The factors involved in studying the complete system are discussed so that future research may avoid some of the oversights of past research. Although relatively little hard data on prototype waste-form/repository-system interactions exist at this time, the available data and their implications are discussed. Sorption studies and models for predicting radionuclide migration are also presented, again with a study of the factors involved.

Johnston, R. J.; Palmer, R. A.

1982-03-31T23:59:59.000Z

428

Labour Relations Research Collection / Mark Thompson (collector)  

E-Print Network [OSTI]

Labour Relations Research Collection / Mark Thompson (collector) Compiled by Erwin Wodarczak (2004 of Contents Collection Description o Title / Dates of Creation / Physical Description o Collector catalogue) #12;Collection Description Labour Relations Research Collection / Mark Thompson (collector

Handy, Todd C.

429

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

430

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

Broader source: Energy.gov [DOE]

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

431

Information Repository  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickrinformation for planningtoA Journey InsideVorticesInflux -0

432

Information Repository  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickrinformation for planningtoA Journey InsideVorticesInflux -01

433

Information Repository  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickrinformation for planningtoA Journey InsideVorticesInflux -012

434

Information Repository  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickrinformation for planningtoA Journey InsideVorticesInflux -0123

435

Information Repository  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickrinformation for planningtoA Journey InsideVorticesInflux -01234

436

Information Repository  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Region service area.Portaldefault Sign In AboutIn theIndustry

437

Data collection for groundwater study  

SciTech Connect (OSTI)

Supporting data for a recent groundwater study at Fermilab are collected together in one document, and are described in the context of how they were obtained and how they were used in the study.

Wehmann, A.A.; Malensek, A.J.; Elwyn, A.J.; Moss, K.J.; Kesich, P.M.

1993-11-30T23:59:59.000Z

438

APEC Inquiry Collection (various collectors)  

E-Print Network [OSTI]

APEC Inquiry Collection (various collectors) Compiled by Jennifer Pecho (2008) University (various collectors). ­ 1997-2001. 6.45 m of textual records and other materials.. Background In 1997

Handy, Todd C.

439

Collections  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New SubstationClean Communities ofCellulosic(SNfactory) | DOE Dataat

440

New cubic perovskites for one-and two-photon water splitting using the computational materials repository  

E-Print Network [OSTI]

the reactions, the number of different materials involved and the size of their bandgaps can be combined for high-performance piezoelectrics,12 for organic photovoltaics using molecules,13­15 and bandgap system, the Computational Materials Repository, for easy access and analysis of the data. Since

Thygesen, Kristian

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.


441

Preclosure seismic design methodology for a geologic repository at Yucca Mountain. Topical report YMP/TR-003-NP  

SciTech Connect (OSTI)

This topical report describes the methodology and criteria that the U.S. Department of Energy (DOE) proposes to use for preclosure seismic design of structures, systems, and components (SSCs) of the proposed geologic repository operations area that are important to safety. Title 10 of the Code of Federal Regulations, Part 60 (10 CFR 60), Disposal of High-Level Radioactive Wastes in Geologic Repositories, states that for a license to be issued for operation of a high-level waste repository, the U.S. Nuclear Regulatory Commission (NRC) must find that the facility will not constitute an unreasonable risk to the health and safety of the public. Section 60.131 (b)(1) requires that SSCs important to safety be designed so that natural phenomena and environmental conditions anticipated at the geologic repository operations area will not interfere with necessary safety functions. Among the natural phenomena specifically identified in the regulation as requiring safety consideration are the hazards of ground shaking and fault displacement due to earthquakes.

NONE

1996-10-01T23:59:59.000Z

442

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

SciTech Connect (OSTI)

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

443

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

SciTech Connect (OSTI)

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

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

1980-01-01T23:59:59.000Z

444

Collective thermoelectrophoresis of charged colloids  

E-Print Network [OSTI]

Thermally driven colloidal transport is, to a large extent, due to the thermoelectric or Seebeck effect of the charged solution.We show that, contrary to the generally adopted single-particle picture, the transport coefficient depends on the colloidal concentration. For solutions that are dilute in the hydrodynamic sense, collective effects may significantly affect the thermophoretic mobility. Our results provide an explanation for recent experimental observations on polyelectrolytes and charged particles and suggest that for charged colloids collective behavior is the rule rather than the exception.

Arghya Majee; Alois Würger

2014-01-29T23:59:59.000Z

445

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

SciTech Connect (OSTI)

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

446

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

SciTech Connect (OSTI)

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

447

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

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

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

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

448

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

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

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

Arkin, Adam (LBNL); Hazen, Terry (LBNL)

449

RESOLUTION STRATEGY FOR GEOMECHANICALLY-RELATED REPOSITORY DESIGN FOR THERMAL-MECHANICAL EFFECTS (RDTME)  

SciTech Connect (OSTI)

In September of 2000, the U.S. Nuclear Regulatory Commission (NRC) issued an Issue Resolution Status Report (NRC 2000). The Key Technical Issue (KTI) agreements on Repository Design and Thermal-Mechanical Effects (RDTME) were jointly developed at the Technical Exchange and Management Meeting held on February 6-8, 2001 in Las Vegas, Nevada. In that report, a number of geomechanically-related issues were raised regarding the determination of rock properties, the estimation of the impacts of geologic variability, the use of numerical models, and the examination of drift degradation and design approach to the ground support system for the emplacement drifts. Ultimately, the primary end products of the KTI agreement resolution processes are an assessment of the preclosure stability of emplacement drifts and the associated ground support requirements. There is also an assessment of the postclosure degradation of the excavations when subjected to thermal and seismic-related stresses as well as in situ loading over time.

M. Board

2003-04-01T23:59:59.000Z

450

NSNFP Activities in Support of Repository Licensing for Disposal of DOE SNF  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Office of Civilian Radioactive Waste Management is in the process of preparing the Yucca Mountain license application for submission to the Nuclear Regulatory Commission as the nation’s first geologic repository for spent nuclear fuel (SNF) and high-level waste. Because the DOE SNF will be part of the license application, there are various components of the license application that will require information relative to the DOE SNF. The National Spent Nuclear Fuel Program (NSNFP) is the organization that directs the research, development, and testing of treatment, shipment, and disposal technologies for all DOE SNF. This report documents the work activities conducted by the NSNFP and discusses the relationship between these NSNFP technical activities and the license application. A number of the NSNFP activities were performed to provide risk insights and understanding of DOE SNF disposal as well as to prepare for anticipated questions from the regulatory agency.

Henry H. Loo; Brett W.. Carlsen; Sheryl L. Morton; Larry L. Taylor; Gregg W. Wachs

2004-09-01T23:59:59.000Z

451

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

SciTech Connect (OSTI)

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

452

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

SciTech Connect (OSTI)

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

453

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

SciTech Connect (OSTI)

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

454

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

SciTech Connect (OSTI)

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

455

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

SciTech Connect (OSTI)

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

456

Carbon-14 releases from an unsaturated repository: A senseless but expensive dilemma  

SciTech Connect (OSTI)

The purpose of the US Environmental Protection Agency (EPA) Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR Part 191 or standards) is to protect public health and safety. The 1985 rule was developed on the basis of the assumption that the repository would be located in a geologic formation that lies below the water table. It is appropriate to examine gaseous releases and transport of pollutants in order to determine site adequacy. When the provisions of the 1985 standard are applied to Yucca Mountain, specifically the limits for carbon-14, we can release in 10,000 years no more than 7,000 curies of carbon-14 in the form of carbon dioxide. Meanwhile, the US Department of Energy (DOE) and others indicate that the repository may release about 8,000 curies of carbon-14 dioxide, an amount that exceeds the standard by 10 to 20 percent. The original basis of the 1985 standards was that, in a site below the water table, the limit for carbon-14 was technically achievable. It was not a standard based on a release level that would prevent a danger to public health. If we examine the danger to public health of the release of 8,000 curies of carbon-14 dioxide during and 8,000-year period, this release would not a pose a significant threat to the average individual. Industry and natural sources release many times this amount of carbon-14 dioxide each year. The question therefore becomes: is it appropriate to spend an additional $3.2 billion on waste packages when the expenditure does not measurably improve the public health?

Pflum, C.G.

1993-10-01T23:59:59.000Z

457

Regulatory Considerations Of Waste Emplacement Within The WIPP Repository: Random Versus Non-Random Distribution  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) is responsible for disposing of transuranic waste in the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. As part of that responsibility, DOE must comply with the U.S. Environmental Protection Agency's (EPA) radiation protection standards in Title 40 Code of Federal Regulations (CFR), Parts 191 and 194. This paper addresses compliance with the criteria of 40 CFR Section 194.24(d) and 194.24(f) that require DOE to either provide a waste loading scheme for the WIPP repository or to assume random emplacement in the mandated performance and compliance assessments. The DOE established a position on waste loading schemes during the process of obtaining the EPA's initial Certification in 1998. The justification for utilizing a random waste emplacement distribution within the WIPP repository was provided to the EPA. During the EPA rulemaking process for the initial certification, the EPA questioned DOE on whether waste would be loaded randomly as modeled in long-term performance assessment (PA) and the impact, if any, of nonrandom loading. In response, DOE conducted an impact assessment for non-random waste loading. The results of this assessment supported the contention that it does not matter whether random or non-random waste loading is assumed for the PA. The EPA determined that a waste loading plan was unnecessary because DOE had assumed random waste loading and evaluated the potential consequences of non-random loading for a very high activity waste stream. In other words, the EPA determined that DOE was not required to provide a waste loading scheme because compliance is not affected by the actual distribution of waste containers in the WIPP.

Casey, S. C.; Patterson, R. L.; Gross, M.; Lickliter, K.; Stein, J. S.

2003-02-25T23:59:59.000Z

458

Powder collection apparatus/method  

DOE Patents [OSTI]

Device for separating and collecting ultrafine atomized powder from the gas stream of a gas atomizing apparatus comprises a housing having an interior wall oriented at an angle relative to horizontal so as to form a downwardly converging, conical expansion chamber, an inlet conduit communicated to the expansion chamber proximate an upper region thereof for receiving the gas stream, and an outlet proximate a lower region of the expansion chamber. The inlet conduit is oriented at a compound inclined angle (with respect to horizontal) selected to promote separation and collection of powder from the gas stream in the expansion chamber. The compound angle comprises a first entrance angle that is greater than the angle of repose of the powder on the housing interior wall such that any powder accumulation in the inlet conduit tends to flow down the wall toward the outlet. The second angle is selected generally equal to the angle of the housing interior wall measured from the same horizontal plane so as to direct the gas stream into the expansion chamber generally tangent to the housing interior wall to establish a downward swirling gas stream flow in the expansion chamber. A powder collection container is communicated to the outlet of the expansion chamber to collect the powder for further processing. 4 figures.

Anderson, I.E.; Terpstra, R.L.; Moore, J.A.

1994-01-11T23:59:59.000Z

459

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]

process simulation software ­ ProSimPlus® ­ to allow physical modeling as well as mass and energy balances is based on the gasification of the biomass followed by Fischer-Tropsch Synthesis (FTS), producing naphtha Sustainability assessment of an integrated High Temperature Steam Electrolysis - enhanced Biomass to Liquid Fuel

Mailhes, Corinne

460

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]

the substitution of oil.2,3 However the first-generation biofuels (using agricultural biomass) are criticized, pressure on prices) and generate significant non-recoverable by-product. The second generation liquid #12;2 efficiency; greenhouse gas emissions; electrolysis water use; levelized biofuels production cost

Boyer, Edmond

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

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]

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

Mailhes, Corinne

462

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]

components, continuous fibre-reinforced thermoplastic composites have demonstrated success in aerospace for the composites industry to develop simula- tion technologies for continuous fibre-reinforced composites [2 measurements and an infrared camera to measure the temperature in the surface of sample. The results

Paris-Sud XI, Université de

463

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]

Cedex 7, France, pascal.maussion@laplace.u niv-tlse.fr Majid Souley EDF Eco-Efficiency & Indust.Process Dept, Av. des Renardières, 77818 Moret sur Loing, France Olivier Pateau EDF Eco-Efficiency & Indust et Conversion d'Energie ENSEEIHT, 2 rue Camichel, 31071 Toulouse Cedex 7, France Stéphane Caux Member

Paris-Sud XI, Université de

464

Information Collection Management | Department of Energy  

Office of Environmental Management (EM)

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

465

Advances in understanding solar energy collection materials  

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

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

466

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 (OSTI)

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

467

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

468

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

Broader source: Energy.gov [DOE]

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

469

Annual Report for Gravity Collection Lysimeter Monitoring Plan - ERDF Cells 5 and 6  

SciTech Connect (OSTI)

The objectives of the Annual Report are to: 1) describe changes in the volume of liquid seen in each lysimeter, 2) describe concentrations and changes or trends in the concentrations of leachate-indicator constituents in any liquids accumulated in each lysimeter, 3) summarize the finding in regard to the presence or absence of leachate in each lysimeter, 4) make recommendations, if any, limited to vadose-zone study-related variables. The data and analyses contained in this report reflect the initial characterization of construction and consolidation water in Cells 5 and 6 lysimeters.

W.E. Remsen

2006-12-21T23:59:59.000Z

470

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

SciTech Connect (OSTI)

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

471

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

SciTech Connect (OSTI)

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

472

Numerical modeling of gas migration at a proposed repository for low and intermediate level nuclear wastes at Oberbauenstock, Switzerland  

SciTech Connect (OSTI)

Hydrologic impacts of corrosive gas release from a hypothetical L/ILW nuclear waste repository at Oberbauenstock are explored by means of numerical simulation. A schematic two dimensional vertical section through the mountain is modeled with the simulator TOUGH, which describes two-phase flow of water and gas in porous and fractured media. Two reference cases are considered which represent the formations as a porous and as a fractured-porous (dual permeability) medium, respectively. Both cases predict similar and rather modest pressure increases, from ambient 10 bars to near 25 bars at the repository level. These results are to be considered preliminary because important parameters affecting two-phase flow, such as relative permeabilities of a fractured medium, are not well known at present. 24 refs., 15 figs., 5 tabs.

Pruess, K.

1990-03-01T23:59:59.000Z

473

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

SciTech Connect (OSTI)

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

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

1993-01-01T23:59:59.000Z

474

PMGR_COLLECTIVE V1.0  

Energy Science and Technology Software Center (OSTI)

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

475

Radioactive waste isolation in salt: special advisory report on the status of the Office of Nuclear Waste Isolation's plans for repository performance assessment  

SciTech Connect (OSTI)

Repository performance assessment is analysis that identifies events and processes that might affect a repository system for isolation of radioactive waste, examines their effects on barriers to waste migration, and estimates the probabilities of their occurrence and their consequences. In 1983 Battelle Memorial Institute's Office of Nuclear Waste Isolation (ONWI) prepared two plans - one for performance assessment for a waste repository in salt and one for verification and validation of performance assessment technology. At the request of the US Department of Energy's Salt Repository Project Office (SRPO), Argonne National Laboratory reviewed those plans and prepared this report to advise SRPO of specific areas where ONWI's plans for performance assessment might be improved. This report presents a framework for repository performance assessment that clearly identifies the relationships among the disposal problems, the processes underlying the problems, the tools for assessment (computer codes), and the data. In particular, the relationships among important processes and 26 model codes available to ONWI are indicated. A common suggestion for computer code verification and validation is the need for specific and unambiguous documentation of the results of performance assessment activities. A major portion of this report consists of status summaries of 27 model codes indicated as potentially useful by ONWI. The code summaries focus on three main areas: (1) the code's purpose, capabilities, and limitations; (2) status of the elements of documentation and review essential for code verification and validation; and (3) proposed application of the code for performance assessment of salt repository systems. 15 references, 6 figures, 4 tables.

Ditmars, J.D.; Walbridge, E.W.; Rote, D.M.; Harrison, W.; Herzenberg, C.L.

1983-10-01T23:59:59.000Z

476

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

SciTech Connect (OSTI)

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

477

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

478

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

SciTech Connect (OSTI)

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

479

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

E-Print Network [OSTI]

the engineered barrier and the accessible environment. The concept of geochemical retarda'tion has been analyzed by Domenico et al. (1988) from a regulatory point of view and the following discussion is a summary of their work. As discussed previously, a...A POSTMORTEM ASSESSMENT OF ENVIRONMENTAL COMPLIANCE OF A HIGH-LEVEL RADIOACTIVE WASTE REPOSITORY, HANFORD SITE, WASHINGTON A Thesis by RUDOLF HARALD WILHELM PETRINI Submitted to the Graduate College of Texas A & M University in partial...

Petrini, Rudolf Harald Wilhelm

1988-01-01T23:59:59.000Z

480

Nye County Nuclear Waste Repository Project Office independent scientific investigations program annual report, May 1997--April 1998  

SciTech Connect (OSTI)

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

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

An experimental investigation of copper-Zircaloy interactions under possible tuff repository conditions  

SciTech Connect (OSTI)

As part of its evaluation of copper and copper alloys for use as a container material for spent fuel, the Nevada Nuclear Waste Storage Investigations Project sponsored this experimental study to determine if the presence of copper would influence the corrosion rate of Zircaloy spent fuel cladding under possible tuff repository conditions. The experiment consisted of exposing copper/Zircaloy clad spent fuel packages to two different environments for up to 9 months. Detailed evaluation of the cladding via metallography, electron probe microanalysis, scanning electron microscopy with microanalysis, and Auger electron spectroscopy/ion milling to chemically profile the surface film failed to provide an evidence of copper-enhanced corrosion of the Zircaloy cladding. The difference in thickness of the oxide films between the 2-month and 5-month experiments, and the 2-month and 9-month experiments as indicated by the time to ion mill through the films, was on the order of 50 {angstrom}, and 100 {angstrom}, respectively, indicating a very low rate of film growth during the experiments. 20 refs., 21 figs., 8 tabs.

Smith, H D

1990-05-01T23:59:59.000Z

482

Assessment of uncertainties in measurement of pH in hostile environments characteristic of nuclear repositories  

SciTech Connect (OSTI)

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

483

Total System Performance Assessment, 1993: An evaluation of the potential Yucca Mountain repository  

SciTech Connect (OSTI)

Total System Performance Assessments are an important component in the evaluation of the suitability of Yucca Mountain, Nevada as a potential site for a mined geologic repository for the permanent disposal of high-level radioactive wastes in the United States. The Total System Performance Assessments are conducted iteratively during site characterization to identify issues which should be addressed by the characterization and design activities as well as providing input to regulatory/licensing and programmatic decisions. During fiscal years 1991 and 1992, the first iteration of Total System Performance Assessment (hereafter referred to as TSPA 1991) was completed by Sandia National Laboratories and Pacific Northwest Laboratory. Beginning in fiscal year 1993, the Civilian Radioactive Waste Management System Management and Operating Contractor was assigned the responsibility to plan, coordinate, and contribute to the second iteration of Total System Performance Assessment (hereafter referred to as TSPA 1993). This document presents the objectives, approach, assumptions, input, results, conclusions, and recommendations associated with the Management and Operating Contractor contribution to TSPA 1993. The new information incorporated in TSPA 1993 includes (1) revised estimates of radionuclide solubilities (and their thermal and geochemical dependency), (2) thermal and geochemical dependency of spent fuel waste alteration and glass dissolution rates, (3) new distribution coefficient (k{sub d}) estimates, (4) revised estimates of gas-phase velocities and travel times, and (5) revised hydrologic modeling of the saturated zone which provides updated estimates of the advective flux through the saturated zone.

Andrews, R.W.; Dale, T.F.; McNeish, J.A.

1994-03-01T23:59:59.000Z

484

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

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

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

485

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

SciTech Connect (OSTI)

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

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

1992-09-01T23:59:59.000Z

486

Devices for collecting chemical compounds  

DOE Patents [OSTI]

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

Scott, Jill R; Groenewold, Gary S

2013-12-24T23:59:59.000Z

487

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

488

Ya ri a bsod Collection 13  

E-Print Network [OSTI]

This collection contains fourteen songs collected in the grasslands of Amdo (northeast Tibet) in the area where Sichuan, Gansu, and Qinghai provinces meet. The songs represent various genres, and were all composed by Ya ri a bsod, an itinerant bard...

Sha bo don 'grub rdo rje; Skal dbang skyid

489

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

490

Chinese Canadian Research Collection / Edgar Wickberg (collector)  

E-Print Network [OSTI]

Chinese Canadian Research Collection / Edgar Wickberg (collector) Compiled by Christopher Hives Canadian Research Collection / Edgar Wickberg (collector). ­ 1885-1979, 1984-1996. 7.53 m of textual

Handy, Todd C.

491

Home Energy Score Data Collection Sheet  

Broader source: Energy.gov [DOE]

Input sheet for qualified assessors to collect data for input into the Home Energy Scoring Tool for evaluation.

492

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

493

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

E-Print Network [OSTI]

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

Lubell, Mark

494

Decentralized Swarming by Robot CollectivesDecentralized Swarming by Robot Collectives Research Goal  

E-Print Network [OSTI]

Cooperative Robots Buildings Surveillance Application Arenas: Entertainment Industry Medical Nanobots ChangeDecentralized Swarming by Robot CollectivesDecentralized Swarming by Robot Collectives Research Goal: Develop a framework for decentralized swarming by robot collectives using artificial potential

Krovi, Venkat

495

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

496

Long-Term Environmental Monitoring of an Operating Deep Geologic Nuclear Waste Repository  

SciTech Connect (OSTI)

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 has had extensive human health and environmental monitoring. The Carlsbad Environmental Monitoring and Research Center is in the Institute for Energy and the Environment, in the College of Engineering at New Mexico State University. Located in Carlsbad, NM, CEMRC has been the independent monitoring facility for the area around WIPP from 1993 to the present, i.e., from six years before disposal operations began to nine years of waste disposal operations (www.cemcr.org). Based on the radiological analyses of monitoring samples completed to date for area residents and site workers, and for selected aerosols, soils, sediments, drinking water and surface waters, there is no evidence of increases in radiological contaminants in the region of WIPP that could be attributed to releases from WIPP. Levels of radiological and non-radiological analytes measured since operations began in 1999 have been within the range of baseline levels measured previously, and are within the ranges measured by other entities at the State and local levels since well before disposal phase operations began in 1999. (authors)

Conca, J.; Kirchner, Th.; Monk, J.; Sage, S. [Carlsbad Environmental Monitoring and Research Center, IEE NMSU, 1400 University Drive, Carlsbad, NM (United States)

2008-07-01T23:59:59.000Z

497

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

498

Canadian Unity Collection / Charles Connaghan (collector)  

E-Print Network [OSTI]

Canadian Unity Collection / Charles Connaghan (collector) University of British Columbia Archives Collector's Biographical Sketch o Scope and Content o Notes Series Descriptions o Council for Canadian) #12;Collection Description Canadian Unity Collection. - 1975-1980 39 cm of textual records. Collector

Handy, Todd C.

499

Lamb Research Collection / W. Kaye Lamb (collector)  

E-Print Network [OSTI]

Lamb Research Collection / W. Kaye Lamb (collector) Compiled by Jane Turner (1990) Revised by Erwin Collection Description o Title / Dates of Creation / Physical Description o Collector's Biographical Sketch o Collection. - 1959-1991. 1.3 m of textual records. 90 maps and charts. 26 microfilm reels. Collector

Handy, Todd C.

500

Day of Concern Collection / Ture Erickson (collector)  

E-Print Network [OSTI]

Day of Concern Collection / Ture Erickson (collector) Last revised October 2011 University;Collection Description Day of Concern collection / Ture Erickson (collector). ­ 1984. 6.5 cm of textual records. Collector's Biographical Sketch Born in New Westminster, Ture Erickson became Head of Sedgewick

Handy, Todd C.