National Library of Energy BETA

Sample records for disposal cell covers

  1. Sustainable Disposal Cell Covers: Legacy Management Practices,

    Energy Savers [EERE]

    Improvements, and Long-Term Performance | Department of Energy Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance PDF icon Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance More

  2. New Facility Will Test Disposal Cell Cover Renovation | Department...

    Office of Environmental Management (EM)

    Services New Facility Will Test Disposal Cell Cover Renovation New Facility Will Test Disposal Cell Cover Renovation New Facility Will Test Disposal Cell Cover Renovation PDF ...

  3. Design and Installation of a Disposal Cell Cover Field Test ...

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

    February 27 through March 3, 2011, Phoenix, Arizona. C.H. Benson, W.J. Waugh, W.H. Albright, G.M. Smith, R.P. Bush PDF icon Design and Installation of a Disposal Cell Cover Field ...

  4. UMTRA project disposal cell cover biointrusion sensitivity assessment, Revision 1

    SciTech Connect (OSTI)

    1995-10-01

    This study provides an analysis of potential changes that may take place in a Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cell cover system as a result of plant biointrusion. Potential changes are evaluated by performing a sensitivity analysis of the relative impact of root penetrations on radon flux out of the cell cover and/or water infiltration into the cell cover. Data used in this analysis consist of existing information on vegetation growth on selected cell cover systems and information available from published studies and/or other available project research. Consistent with the scope of this paper, no new site-specific data were collected from UMTRA Project sites. Further, this paper does not focus on the issue of plant transport of radon gas or other contaminants out of the disposal cell cover though it is acknowledged that such transport has the potential to be a significant pathway for contaminants to reach the environment during portions of the design life of a disposal cell where plant growth occurs. Rather, this study was performed to evaluate the effects of physical penetration and soil drying caused by plant roots that have and are expected to continue to grow in UMTRA Project disposal cell covers. An understanding of the biological and related physical processes that take place within the cover systems of the UMTRA Project disposal cells helps the U.S. Department of Energy (DOE) determine if the presence of a plant community on these cells is detrimental, beneficial, or of mixed value in terms of the cover system`s designed function. Results of this investigation provide information relevant to the formulation of a vegetation control policy.

  5. Design and Installation of a Disposal Cell Cover Field Test

    SciTech Connect (OSTI)

    Benson, C.H. [University of Wisconsin–Madison, Madison, Wisconsin; Waugh, W.J. [S.M. Stoller Corporation, Grand Junction, Colorado; Albright, W.H. [Desert Research Institute, Reno, Nevada; Smith, G.M. [Geo-Smith Engineering, Grand Junction, Colorado; Bush, R.P. [U.S. Department of Energy, Grand Junction, Colorado

    2011-02-27

    The U.S. Department of Energy’s Office of Legacy Management (LM) initiated a cover assessment project in September 2007 to evaluate an inexpensive approach to enhancing the hydrological performance of final covers for disposal cells. The objective is to accelerate and enhance natural processes that are transforming existing conventional covers, which rely on low-conductivity earthen barriers, into water balance covers, that store water in soil and release it as soil evaporation and plant transpiration. A low conductivity cover could be modified by deliberately blending the upper layers of the cover profile and planting native shrubs. A test facility was constructed at the Grand Junction, Colorado, Disposal Site to evaluate the proposed methodology. The test cover was constructed in two identical sections, each including a large drainage lysimeter. The test cover was constructed with the same design and using the same materials as the existing disposal cell in order to allow for a direct comparison of performance. One test section will be renovated using the proposed method; the other is a control. LM is using the lysimeters to evaluate the effectiveness of the renovation treatment by monitoring hydrologic conditions within the cover profile as well as all water entering and leaving the system. This paper describes the historical experience of final covers employing earthen barrier layers, the design and operation of the lysimeter test facility, testing conducted to characterize the as-built engineering and edaphic properties of the lysimeter soils, the calibration of instruments installed at the test facility, and monitoring data collected since the lysimeters were constructed.

  6. Appendix K Disposal Cell Groundwater Monitoring Plan

    Office of Legacy Management (LM)

    Disposal Cell Groundwater Monitoring Plan

  7. disposal_cell.cdr

    Office of Legacy Management (LM)

    The disposal cell was constructed in the area formerly occupied by the Weldon Spring Uranium Feed Materials Plant production buildings. The cell provides long-term isolation and ...

  8. Approaches to consider covers and liners in a low-level waste disposal facility performance assessment

    SciTech Connect (OSTI)

    Seitz, R.

    2015-03-17

    On-site disposal cells are in use and being considered at several USDOE sites as the final disposition for large amounts of waste associated with cleanup of contaminated areas and facilities. These disposal cells are typically regulated by States and/or the USEPA in addition to having to comply with requirements in DOE Order 435.1, Radioactive Waste Management. The USDOE-EM Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnel associated with these Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to performance and risk assessments in support of a Record of Decision and Disposal Authorization Statement. One task completed by the working group addressed approaches for considering the performance of covers and liners/leachate collections systems in the context of a performance assessment (PA). A document has been prepared which provides recommendations for a general approach to address covers and liners/leachate collection systems in a PA and how to integrate assessments with defense-in-depth considerations such as design, operations and waste acceptance criteria to address uncertainties. Specific information and references are provided for details needed to address the evolution of individual components of cover and liner/leachate collection systems. This information is then synthesized into recommendations for best practices for cover and liner system design and examples of approaches to address the performance of covers and liners as part of a performance assessment of the disposal system.

  9. Monitoring the Performance of an Alternative Landfill Cover at the Monticello, Utah, Uranium Mill Tailings Disposal Site

    Broader source: Energy.gov [DOE]

    Monitoring the Performance of an Alternative Landfill Cover at the Monticello, Utah, Uranium Mill Tailings Disposal Site

  10. DOE - Office of Legacy Management -- Cheney Disposal Cell - 008

    Office of Legacy Management (LM)

    Cheney Disposal Cell - 008 FUSRAP Considered Sites Site: Cheney Disposal Cell (008) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: ...

  11. DOE - Office of Legacy Management -- Clive Disposal Cell - 036

    Office of Legacy Management (LM)

    Clive Disposal Cell - 036 FUSRAP Considered Sites Site: Clive Disposal Cell (036 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: ...

  12. DOE - Office of Legacy Management -- Estes Gulch Disposal Cell...

    Office of Legacy Management (LM)

    Estes Gulch Disposal Cell - 010 FUSRAP Considered Sites Site: Estes Gulch Disposal Cell (010) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site ...

  13. DOE - Office of Legacy Management -- 11 E (2) Disposal Cell ...

    Office of Legacy Management (LM)

    11 E (2) Disposal Cell - 037 FUSRAP Considered Sites Site: 11 E. (2) Disposal Cell (037) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site ...

  14. DOE - Office of Legacy Management -- Burro Canyon Disposal Cell...

    Office of Legacy Management (LM)

    Burro Canyon Disposal Cell - 007 FUSRAP Considered Sites Site: Burro Canyon Disposal Cell (007) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site ...

  15. Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell...

    Office of Environmental Management (EM)

    Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell: Evaluation of Long-Term Performance Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell: Evaluation of...

  16. Microsoft Word - Appendix C_DisposalCellContents.doc

    Office of Legacy Management (LM)

    Disposal Cell Contents Table C-1. Contents of the Weldon Spring, Missouri, Disposal Cell U.S. Department of Energy Weldon Spring Site LTS&M Plan July 2005 Doc. No. S0079000 Page C-3 Work Zone Per WP437 and Material Description Cell Placement Considerations Occupied Cell Volume (cy) Raffinate Pits Work Zone CSS Grout Produced in CSS Plant and pumped to cell. Volume as determined at the plant. 188,443.00 Raffinate Pit 4 residual sludge Stabilized in situ with grout then mixed with TSA

  17. A Water Balance Study of Four Landfill Cover Designs at Material Disposal Area B in Los Alamos, New Mexico

    SciTech Connect (OSTI)

    David D. Breshears; Fairley J. Barnes; John W. Nyhan; Johnny A. Salazar

    1998-09-01

    The goal of disposing of low-level radioactive and hazardous waste in shallow landfills is to reduce risk to human health and the environment by isolating contaminants until they no longer pose an unacceptable hazard. In order to achieve this, the Department of Energy Environmental Restoration Program is comparing the performance of several different surface covers at Material Disposal Area (MDA) B in Los Alamos. Two conventional landfill were compared with an improved cover designed to minimize plant and animal intrusion and to minimize water infiltration into the underlying wastes. The conventional covers varied in depth and both conventional and improved designs had different combinations of vegetation (grass verses shrub) and gravel mulch (no mulch verses mulch). These treatments were applied to each of 12 plots and water balance parameters were measured from March1987 through June 1995. Adding a gravel mulch significantly influenced the plant covered field plots receiving no gravel mulch averaged 21.2% shrub cover, while plots with gravel had a 20% larger percent cover of shrubs. However, the influence of gravel mulch on the grass cover was even larger than the influence on shrub cover, average grass cover on the plots with no gravel was 16.3%, compared with a 42% increase in grass cover due to gravel mulch. These cover relationships are important to reduce runoff on the landfill cover, as shown by a regression model that predicts that as ground cover is increased from 30 to 90%,annual runoff is reduced from 8.8 to 0.98 cm-a nine-fold increase. We also found that decreasing the slope of the landfill cover from 6 to 2% reduced runoff from the landfill cover by 2.7-fold. To minimize the risk of hazardous waste from landfills to humans, runoff and seepage need to be minimized and evapotranspiration maximized on the landfill cover. This has to be accomplished for dry and wet years at MDA B. Seepage consisted of 1.9% and 6.2% of the precipitation in the average and once in ten year events, respectively, whereas corresponding values for runoff were 13% and 16%; these changes were accompanied by corresponding decreases in evapotranspiration, which accounted for 86% and only 78% of the precipitation occurring on the average and once in ten year even~ respectively.

  18. Revegetation/rock cover for stabilization of inactive uranium mill tailings disposal sites

    SciTech Connect (OSTI)

    Beedlow, P.A.; McShane, M.C.; Cadwell, L.L.

    1982-07-01

    Pacific Northwest Laboratory is developing design and performance guidelines for surface stabilization of inactive uranium mill tailings. In this work, vegetation and rock covers are being evaluated for maintaining long-term integrity of impoundment systems. Methods are being developed to estimate erosion rates associated with rock and/or vegetation covers, and to determine the effects of surface treatments on soil moisture. Interactions between surface treatments and barriers (radon and biological) are being studied as well. The product will be a set of guidelines to aid in designing surface covers. This report presents the status of this program and a discussion of considerations pertinent to the application of surface covers to tailings. Test plots located in Grand Junction, Colorado and Waterflow, New Mexico are being used to study: (1) the interactions between vegetation and radon and biological barriers, (2) the effects of surface covers on soil moisture, and (3) the effects of rock covers on vegetation.

  19. Final closure cover for a Hanford radioactive mixed waste disposal facility

    SciTech Connect (OSTI)

    Johnson, K.D.

    1996-02-06

    This study provides a preliminary design for a RCRA mixed waste landfill final closure cover. The cover design was developed by a senior class design team from Seattle University. The design incorporates a layered design of indigenous soils and geosynthetics in a layered system to meet final closure cover requirements for a landfill as imposed by the Washington Administrative Code WAC-173-303 implementation of the Resource Conservation and Recovery Act.

  20. Extending facility life by combining embankments: permitting energy solutions class a combined disposal cell

    SciTech Connect (OSTI)

    McCandless, S.J.; Shrum, D.B.

    2007-07-01

    EnergySolutions' Class A low-level radioactive waste management operations are limited to a 540-acre section of land in Utah's west desert. In order to optimize the facility lifetime, EnergySolutions has launched an effort to improve the waste disposal utilization of this acreage. A chief component of this effort is the Class A Combined embankment. The Class A Combined embankment incorporates the footprint of both the currently licensed Class A cell and the Class A North cell, and also includes an increase in the overall embankment height. By combining the cells and raising the height of the embankment, disposal capacity is increased by 50% over the two-cell design. This equates to adding a second Class A cell, at approximately 3.8 million cubic yards capacity, without significantly increasing the footprint of disposal operations. In order to justify the design, EnergySolutions commissioned geotechnical and infiltration fate and transport evaluations, modeling, and reports. Cell liner and cover materials, specifications, waste types, and construction methods will not change. EnergySolutions estimates that the Class A Combined cell will add at least 10 years of capacity to the site, improving utilization of the permitted area without unacceptable environmental impacts. (authors)

  1. US DOE-EM On-Site Disposal Cell Working Group - Fostering Communication On Performance Assessment Challenges

    SciTech Connect (OSTI)

    Seitz, Roger R.; Suttora, Linda C.; Phifer, Mark

    2014-03-01

    On-site disposal cells are in use and being considered at several U.S. Department of Energy (USDOE) sites as the final disposition for large amounts of waste associated with cleanup of contaminated areas and facilities. These facilities are typically developed with regulatory oversight from States and/or the US Environmental Protection Agency (USEPA) in addition to USDOE. The facilities are developed to meet design standards for disposal of hazardous waste as well as the USDOE performance based standards for disposal of radioactive waste. The involvement of multiple and different regulators for facilities across separate sites has resulted in some differences in expectations for performance assessments and risk assessments (PA/RA) that are developed for the disposal facilities. The USDOE-EM Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnel associated with these Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to performance and risk assessments in support of a Record of Decision and Disposal Authorization Statement. The working group holds teleconferences, as needed, focusing on specific topics of interest. The topics addressed to date include an assessment of the assumptions used for performance assessments and risk assessments (PA/RAs) for on-site disposal cells, requirements and assumptions related to assessment of inadvertent intrusion, DOE Manual 435.1-1 requirements, and approaches for consideration of the long-term performance of liners and covers in the context of PAs. The working group has improved communication among the staff and oversight personnel responsible for onsite disposal cells and has provided a forum to identify and resolve common concerns.

  2. Output-increasing, protective cover for a solar cell

    DOE Patents [OSTI]

    Hammerbacher, Milfred D.

    1995-11-21

    A flexible cover (14) for a flexible solar cell (12) protects the cell from the ambient and increases the cell's efficiency. The cell(12)includes silicon spheres (16) held in a flexible aluminum sheet matrix (20,22). The cover (14) is a flexible, protective layer (60) of light-transparent material having a relatively flat upper, free surface (64) and an irregular opposed surface (66). The irregular surface (66) includes first portions (68) which conform to the polar regions (31R) of the spheres (16) and second convex (72) or concave (90) portions (72 or 90) which define spaces (78) in conjunction with the reflective surface (20T) of one aluminum sheet (20). Without the cover (14) light (50) falling on the surface (20T) between the spheres (16) is wasted, that is, it does not fall on a sphere (16). The surfaces of the second portions are non-parallel to the direction of the otherwise wasted light (50), which fact, together with a selected relationship between the refractive indices of the cover and the spaces, result in sufficient diffraction of the otherwise wasted light (50) so that about 25% of it is reflected from the surface (20T) onto a sphere (16).

  3. Deployment of an Alternative Closure Cover and Monitoring System at the Mixed Waste Disposal Unit U-3ax/bl at the Nevada Test Site

    SciTech Connect (OSTI)

    Levitt, D.G.; Fitzmaurice, T.M.

    2001-02-01

    In October 2000, final closure was initiated of U-3ax/bl, a mixed waste disposal unit at the Nevada Test Site (NTS). The application of approximately 30 cm of topsoil, composed of compacted native alluvium onto an operational cover, seeding of the topsoil, installation of soil water content sensors within the cover, and deployment of a drainage lysimeter facility immediately adjacent to the disposal unit initiated closure. This closure is unique in that it required the involvement of several U.S. Department of Energy (DOE) Environmental Management (EM) groups: Waste Management (WM), Environmental Restoration (ER), and Technology Development (TD). Initial site characterization of the disposal unit was conducted by WM. Regulatory approval for closure of the disposal unit was obtained by ER, closure of the disposal unit was conducted by ER, and deployment of the drainage lysimeter facility was conducted by WM and ER, with funding provided by the Accelerated Site Technology Deployment ( ASTD) program, administered under TD. In addition, this closure is unique in that a monolayer closure cover, also known as an evapotranspiration (ET) cover, consisting of native alluvium, received regulatory approval instead of a traditional Resource Conservation and Recovery Act (RCRA) multi-layered cover. Recent studies indicate that in the arid southwestern United States, monolayer covers may be more effective at isolating waste than layered covers because of the tendency of clay layers to desiccate and crack, and subsequently develop preferential pathways. The lysimeter facility deployed immediately adjacent to the closure cover consists of eight drainage lysimeters with three surface treatments: two were left bare; two were revegetated with native species; two were allowed to revegetate with invader species; and two are reserved for future studies. The lysimeters are constructed such that any drainage through the bottoms of the lysimeters can be measured. Sensors installed in the closure cover provide soil water content data, whereas sensors installed in the lysimeters provide soil water content, soil water potential, soil temperature, and drainage data for a detailed evaluation of the cover performance. Revegetation establishes a stable plant community that maximizes water loss through transpiration and reduces water and wind erosion and ultimately restores the disposal unit to its surrounding Great Basin Desert environment.

  4. Idaho Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell

    Broader source: Energy.gov [DOE]

    American Recovery and Reinvestment Act cleanup crews at the Idaho site recently disposed of a hot cell as heavy as nine fully loaded Boeing 737s.

  5. A new design for a disposable and modifiable electrochemical cell (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | SciTech Connect Journal Article: A new design for a disposable and modifiable electrochemical cell Citation Details In-Document Search Title: A new design for a disposable and modifiable electrochemical cell Authors: Dattelbaum, Andrew M [1] ; Gupta, Gautam [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2011-09-09 OSTI Identifier: 1095867 Report Number(s): LA-UR-11-05239; LA-UR-11-5239 DOE Contract Number: AC52-06NA25396 Resource Type: Journal

  6. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites

    Office of Legacy Management (LM)

    Bluewater, New Mexico Page 1-1 1.0 Bluewater, New Mexico, Disposal Site 1.1 Compliance Summary The Bluewater, New Mexico, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title II Disposal Site was inspected on August 19 and 20, 2015. A significant pond was present on the top slope of the main tailings disposal cell cover in an area where shallow depressions are present; disposal cell performance is being evaluated to determine if additional monitoring or cover enhancement is necessary.

  7. Cover and startup gas supply system for solid oxide fuel cell generator

    DOE Patents [OSTI]

    Singh, Prabhakar; George, Raymond A.

    1999-01-01

    A cover and startup gas supply system for a solid oxide fuel cell power generator is disclosed. Hydrocarbon fuel, such as natural gas or diesel fuel, and oxygen-containing gas are supplied to a burner. Combustion gas exiting the burner is cooled prior to delivery to the solid oxide fuel cell. The system mixes the combusted hydrocarbon fuel constituents with hydrogen which is preferably stored in solid form to obtain a non-explosive gas mixture. The system may be used to provide both non-explosive cover gas and hydrogen-rich startup gas to the fuel cell.

  8. Cover and startup gas supply system for solid oxide fuel cell generator

    DOE Patents [OSTI]

    Singh, P.; George, R.A.

    1999-07-27

    A cover and startup gas supply system for a solid oxide fuel cell power generator is disclosed. Hydrocarbon fuel, such as natural gas or diesel fuel, and oxygen-containing gas are supplied to a burner. Combustion gas exiting the burner is cooled prior to delivery to the solid oxide fuel cell. The system mixes the combusted hydrocarbon fuel constituents with hydrogen which is preferably stored in solid form to obtain a non-explosive gas mixture. The system may be used to provide both non-explosive cover gas and hydrogen-rich startup gas to the fuel cell. 4 figs.

  9. Portsmouth Waste Disposal | Department of Energy

    Office of Environmental Management (EM)

    Environmental Cleanup Portsmouth Waste Disposal Portsmouth Waste Disposal Preliminary design cross section of Planned On-site Disposal Cell Preliminary design cross section of ...

  10. Evaluation of Background Concentrations of Contaminants in an Unusual Desert Arroyo Near a Uranium Mill Tailings Disposal Cell - 12260

    SciTech Connect (OSTI)

    Bush, Richard P.; Morrison, Stan J.

    2012-07-01

    The U.S. Department of Energy (DOE) Office of Legacy Management (LM) manages 27 sites that have groundwater containing uranium concentrations above background levels. The distal portions of the plumes merge into background groundwater that can have 50 ÎĽg/L or more uranium. Distinguishing background from site-related uranium is often problematic, but it is critical to determining if remediation is warranted, establishing appropriate remediation goals, and evaluating disposal cell performance. In particular, groundwater at disposal cells located on the upper Cretaceous Mancos Shale may have relatively high background concentrations of uranium. Elevated concentrations of nitrate, selenium, and sulfate accompany the uranium. LM used geologic analogs and uranium isotopic signatures to distinguish background groundwater from groundwater contaminated by a former uranium processing site. The same suite of contaminants is present in groundwater near former uranium processing sites and in groundwater seeps emanating from the Mancos Shale over a broad area. The concentrations of these contaminants in Many Devils Wash, located near LM's Shiprock disposal cell, are similar to those in samples collected from many Mancos seeps, including two analog sites that are 8 to 11 km from the disposal cell. Samples collected from Many Devils Wash and the analog sites have high AR values (about 2.0)-in contrast, groundwater samples collected near the tailings disposal cell have AR values near 1.0. These chemical signatures raise questions about the origin of the contamination seeping into Many Devils Wash. (authors)

  11. PORTSMOUTH ON-SITE DISPOSAL CELL HIGH DENSITY POLYETHYLENE GEOMEMBRANE LONGEVITY

    SciTech Connect (OSTI)

    Phifer, M.

    2012-01-31

    It is anticipated that high density polyethylene (HDPE) geomembranes will be utilized within the liner and closure cap of the proposed On-Site Disposal Cell (OSDC) at the Portsmouth Gaseous Diffusion Plant. The likely longevity (i.e. service life) of HDPE geomembranes in OSDC service is evaluated within the following sections of this report: (1) Section 2.0 provides an overview of HDPE geomembranes, (2) Section 3.0 outlines potential HDPE geomembranes degradation mechanisms, (3) Section 4.0 evaluates the applicability of HDPE geomembrane degradation mechanisms to the Portsmouth OSDC, (4) Section 5.0 provides a discussion of the current state of knowledge relative to the longevity (service life) of HDPE geomembranes, including the relation of this knowledge to the Portsmouth OSDC, and (5) Section 6.0 provides summary and conclusions relative to the anticipated service life of HDPE geomembranes in OSDC service. Based upon this evaluation it is anticipated that the service life of HDPE geomembranes in OSDC service would be significantly greater than the 200 year service life assumed for the OSDC closure cap and liner HDPE geomembranes. That is, a 200 year OSDC HDPE geomembrane service life is considered a conservative assumption.

  12. Work plan for phase 1A paleochannel studies at the Cheney disposal cell, Grand Junction, Colorado: Draft

    SciTech Connect (OSTI)

    1996-11-01

    This document will serve as a Work Plan for continuing paleochannel characterization activities at the Cheney disposal site near Grand Junction, Colorado. Elevated levels of nitrate were encountered in ground water from two monitor wells installed in alluvial paleochannels near the Cheney disposal cell in 1994. This triggered a series of investigations (Phase 1) designed to determine the source of nitrate and other chemical constituents in ground water at the site. A comprehensive summary of the Phase 1 field investigations (limited to passive monitoring and modeling studies) conducted by the Remedial Action Contractor (RAC) and Technical Assistance Contractor (TAC) to date is provided in Section 2.0 of this document. Results of Phase 1 were inconclusive regarding the potential interaction between the disposal cell and the paleochannels, so additional Phase 1A investigations are planned. Recommendations for Phase 1A tasks and possible future activities are discussed in Section 3.0. Detailed information on the implementation of the proposed Phase 1A tasks appears in Section 4.0 and will provide the basis for Statements of Work (SOW) for each of these tasks. A detailed sampling plan is provided to ensure quality and a consistency with previous data collection efforts.

  13. WIPP - Pioneering Nuclear Waste Disposal

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

    Pioneering Nuclear Waste Disposal Cover Page and Table of Contents Closing the Circle The Long Road to WIPP - Part 1 The Long Road to WIPP - Part 2 Looking to the Future Related Reading and The WIPP Team

  14. A new design for a disposable and modifiable electrochemical...

    Office of Scientific and Technical Information (OSTI)

    A new design for a disposable and modifiable electrochemical cell Citation Details In-Document Search Title: A new design for a disposable and modifiable electrochemical cell ...

  15. Changes in Vegetation at the Monticello, Utah, Disposal Site...

    Energy Savers [EERE]

    the Performance of an Alternative Landfill Cover at the Monticello, Utah, Uranium Mill Tailings Disposal Site Monitoring the Performance of an Alternative Cover Using Caisson...

  16. Tuba City, Arizona, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    ... A lined solar evaporation pond receives the waste liquid (brine) and the softener ... Disposal Cell Design The fve-sided disposal cell occupies an area of 50 acres on the ...

  17. Journal Covers

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

    Journal Covers Journal Covers The Crystallization of PEDOT:PSS Polymeric Electrodes Probed In Situ during Printing Print Thursday, 18 June 2015 11:53 Organic electronics have...

  18. Disposal rabbit

    DOE Patents [OSTI]

    Lewis, L.C.; Trammell, D.R.

    1983-10-12

    A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

  19. Disposable rabbit

    DOE Patents [OSTI]

    Lewis, Leroy C.; Trammell, David R.

    1986-01-01

    A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

  20. Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan - Cover

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

    Year Research, Development, and Demonstration Plan Planned program activities for 2011-2020 Fuel Cell Technologies Office NOTICE This report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or

  1. front cover

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

    care. Also, this Medical Program does not cover services received outside the United States, unless there is an emergency. Most preauthorizations may be requested over...

  2. Bluewater, New Mexico, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    ... Much of the remainder of the site is covered with fne-grained material deposited by wind and water. The region around the disposal site is sparsely populated, and the main land use ...

  3. Consideration of liners and covers in performance assessments

    SciTech Connect (OSTI)

    Phifer, Mark A.; Seitz, Robert R.; Suttora, Linda C.

    2014-09-18

    On-site disposal cells are in use and being considered at several United States Department of Energy (USDOE) sites as the final disposition for large amounts of waste associated with cleanup of contaminated areas and facilities. These disposal cells are typically regulated by States and/or the U.S. Environmental Protection Agency under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) in addition to having to comply with requirements in DOE Order 435.1, Radioactive Waste Management due to the radioactive waste. The USDOE-Environmental Management Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnel associated with these CERCLA disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to CERCLA risk assessments and DOE Order 435.1 performance assessments in support of a Record of Decision and Disposal Authorization Statement, respectively. One of the issues considered by the working group, which is addressed in this report, was how to appropriately consider the performance of covers and liners/leachate collections systems in the context of a DOE Order 435.1 performance assessment (PA). This same information may be appropriate for consideration within CERCLA risk assessments for these facilities. These OSDCs are generally developed to meet hazardous waste (HW) disposal design standards under the Resource Conservation and Recovery Act (RCRA) as well as the DOE Order 435.1 performance based standards for disposal of radioactive waste. To meet the standards for HW, the facilities typically include engineered covers and liner/leachate collection systems. Thus, when considering such facilities in the context of a DOE Order 435.1 PA, there is a need to address the evolution of performance of covers and liner/leachate collection systems in the context of meeting a performance standard considering time frames of 1,000 years for compliance and potentially thousands of years based on the wastes to test the robustness of the system. Experience has shown that there are a range of expectations and perspectives from the different regulators involved at different sites when reviewing assumptions related to cover and liner/leachate collection system performance. However for HW disposal alone under RCRA the design standards are typically considered sufficient by the regulators without a requirement to assess long-term performance thus avoiding the need to consider the details addressed in this report. This report provides suggestions for a general approach to address covers and liners/leachate collection systems in a DOE Order 435.1 PA and how to integrate assessments with defense-in-depth considerations such as design, operations, and waste acceptance criteria to address uncertainties. The emphasis is on water balances and management in such assessments. Specific information and references are provided for details needed to address the evolution of individual components of cover and liner/leachate collection systems. This information was then synthesized into suggestions for best practices for cover and liner system design and examples of approaches to address the performance of covers and liners as part of a performance assessment of the disposal system. Numerous references are provided for sources of information to help describe the basis for performance of individual components of cover and liner systems.

  4. Alternative Evaluation Study: Methods to Mitigate/Accommodate Subsidence for the Radioactive Waste Management Sites at the Nevada Test Site, Nye County Nevada, with Special Focus on Disposal Cell U-3ax/bl

    SciTech Connect (OSTI)

    Barker, L.

    1997-09-01

    An Alternative Evaluation Study is a type of systematic approach to problem identification and solution. An Alternative Evaluation Study was convened August 12-15, 1997, for the purpose of making recommendations concerning closure of Disposal Cell U-3ax/bl and other disposal cells and mitigation/accommodation of waste subsidence at the Radioactive Waste Management Sites at the Nevada Test Site. This report includes results of the Alternative Evaluation Study and specific recommendations.

  5. On-Site Disposal Facility Inspection Report

    Office of Legacy Management (LM)

    On-Site Disposal Facility Inspection Report September 2013 6319-D6242 8947.2 0913 East Face Cell 1 West Face Cell 1 6319D-6208 6319D-6231 8947.3 0913 North Face Cell 1 North ...

  6. Long-Term Surveillance Plan for the Burro Canyon Disposal Cell, Slick Rock, Colorado, DOE/AL/236, Revision 05/1998, May 1998

    Office of Legacy Management (LM)

    DOE/AL/62350-236~v'('/fl) ilWL I . LONG-TERM SURVEILLANCE PLAN -- FOR THE BURRO CANYON DISPOSAL CELL SLICK ROCK., COLORADO *- May 1998 J!f' 1 MASTER Uranium Mill Tailings Berr:ed.ial Action Project DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the

  7. Long-Term Surveillance Plan for the Upper Burbank Disposal Cell, Uravan, Colorado, DOE/AL/62350-250, Revision 1, July 1999

    Office of Legacy Management (LM)

    LONG-TERM SURVEILLANCE PLAN FOR THE UPPER BURBANK DISPOSAL CELL URAUAN, COLORADO July 1999 Prepared for U.S. Department of Energy Environmental Restoration Dhrision U MTRA Project Team Albuquerque, New Mexico DOElAU62350-250 REV. 1 Prepared by Jacobs Engineering Group Inc. Albuquerque, New Mexico This page intentionally left blank LONG-TERM GURMIWNCE P U N FOR THE UPPER BURBANK DrsPosAL CEU. WYAAI. COhORAOD TABLE OF DONENTe TABLE OF CONTENTS 1.0 PURPOSEANDSCOPE

  8. front cover

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

    Preferred Provider Option (PPO) Medical Program For Active Employees and Their Covered Family Members and Non- Medicare Eligible Retirees and Their Covered Family Members Administered by: N113794 01/15 CUSTOMER ASSISTANCE Customer Service: Medical/Surgical Claims and Prescription Drugs-The 24/7 Nurseline can help when you have a health problem or concern. The 24/7 Nurseline is staffed by registered nurses who are available 24 hours a day, 7 days a week. 24/7 Nurseline toll-free telephone number:

  9. front cover

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

    Exclusive Provider Option (EPO) Medical Program For Medicare Retirees and Their Covered Family Members Administered by: N113794 01/15 CUSTOMER ASSISTANCE Customer Service: Medical/Surgical Claims and Prescription Drugs-The 24/7 Nurseline can help when you have a health problem or concern. The 24/7 Nurseline is staffed by registered nurses who are available 24 hours a day, 7 days a week. 24/7 Nurseline toll-free telephone number: 1-800-973-6329 When you have a non- medical benefit question or

  10. front cover

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

    Preferred Provider Option (PPO) Medical Program For Medicare Retirees and Their Covered Family Members Administered by: N113794 01/15 CUSTOMER ASSISTANCE Customer Service: Medical/Surgical Claims and Prescription Drugs-The 24/7 Nurseline can help when you have a health problem or concern. The 24/7 Nurseline is staffed by registered nurses who are available 24 hours a day, 7 days a week. 24/7 Nurseline toll-free telephone number: 1-800-973-6329 When you have a non- medical benefit question or

  11. Disposal Information - Hanford Site

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

    About Us Hanford Site Wide Programs Hanford Site Solid Waste Acceptance Program Tools Disposal Information About Us Hanford Site Solid Waste Acceptance Program What's New Acceptance Criteria Acceptance Process Tools Approved High Integrity Containers Approved Sorbents, Stabilizers, and Void Fillers Disposal Information Points of Contact Disposal Information Email Email Page | Print Print Page |Text Increase Font Size Decrease Font Size Disposal of Radioactive Waste at Hanford The Hanford Site

  12. Design of UMTRA covers to mitigate the effect of frost penetration

    SciTech Connect (OSTI)

    Banani, A.M.; Claire, R.F.

    1994-03-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project, contracted by the US Department of Energy (DOE), requires construction of disposal cells for residual radioactive materials from abandoned uranium mill tailings. A disposal cell consists of contaminated material placed within a stabilized embankment with a top cover. The embankment and cover should be effective for up to 1000 years, to the extent reasonably achievable, and in any case for at least 200 years. The embankment cover usually consists of a radon/infiltration barrier, a frost barrier and erosion protection layer consisting of bedding and riprap layers. The radon/infiltration barrier and frost barrier are two important elements of the cover systems. A radon/infiltration barrier is designed to reduce the radon emissions from the contaminated materials and to limit the surface water infiltration into the contaminated material. However, a radon/infiltration barrier has to be protected from repeated freeze-thaw cycles to prevent an increase in permeability. Frost penetration depth is site specific and depends on local climatic conditions and soil properties of the cover system. However, placing a frost barrier is not only very costly but also reduces the disposal capacity of the embankment. Recent laboratory test results indicate that freeze-thaw cycles do not significantly effect the permeability of compacted sand-bentonite mixtures. Therefore, radon/infiltration barriers using sand-bentonite mixtures may not require frost barriers for protection against the effects of freeze-thaw. In this paper the design of UMTRA covers is briefly explained; the criteria to determine a 200 year freeze event, and the frost penetration depth are discussed. The results of freeze-thaw permeability tests on compacted clay and sand-bentonite mixtures are also presented.

  13. Radiological performance assessment for the E-Area Vaults Disposal Facility

    SciTech Connect (OSTI)

    Cook, J.R.; Hunt, P.D.

    1994-04-15

    The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type.

  14. Cell and current collector felt arrangement for solid oxide electrochemical cell combinations

    DOE Patents [OSTI]

    Reichner, Philip

    1988-01-01

    A solid electrolyte electrochemical cell combination 1 is made, comprising an annular, axially elongated, inner electrode 2 containing at least one interior gas feed conduit 3; annular solid electrolyte segments 4 around and covering portions of the inner electrode; annular outer electrode segments 6 around and covering portions of the electrolyte segments; electronically conducting, non-porous, interconnection material 5 disposed between electrolyte segments and in contact with the inner electrode, and electronically conducting, porous, metal fiber current collector felts 7 disposed on top of the non-porous interconnect material and outer electrode segments, where both the non-porous interconnect material and the porous metal felts are disposed circumferentially about the cell, transversely to the axial length of the cell and the inner electrode is continuous for the entire axial length of the cell combination.

  15. Disposal Activities and the Unique Waste Streams at the Nevada National Security Site (NNSS)

    SciTech Connect (OSTI)

    Arnold, P.

    2012-10-31

    This slide show documents waste disposal at the Nevada National Security Site. Topics covered include: radionuclide requirements for waste disposal; approved performance assessment (PA) for depleted uranium disposal; requirements; program approval; the Waste Acceptance Review Panel (WARP); description of the Radioactive Waste Acceptance Program (RWAP); facility evaluation; recent program accomplishments, nuclear facility safety changes; higher-activity waste stream disposal; and, large volume bulk waste streams.

  16. Waste Disposal | Department of Energy

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

    Disposal Waste Disposal Trucks transport debris from Oak Ridge’s cleanup sites to the onsite CERCLA disposal area, the Environmental Management Waste Management Facility. Trucks transport debris from Oak Ridge's cleanup sites to the onsite CERCLA disposal area, the Environmental Management Waste Management Facility. The low-level radiological and hazardous wastes generated from Oak Ridge's cleanup projects are disposed in the Environmental Management Waste Management Facility (EMWMF). The

  17. Multiple layer insulation cover

    DOE Patents [OSTI]

    Farrell, James J.; Donohoe, Anthony J.

    1981-11-03

    A multiple layer insulation cover for preventing heat loss in, for example, a greenhouse, is disclosed. The cover is comprised of spaced layers of thin foil covered fabric separated from each other by air spaces. The spacing is accomplished by the inflation of spaced air bladders which are integrally formed in the cover and to which the layers of the cover are secured. The bladders are inflated after the cover has been deployed in its intended use to separate the layers of the foil material. The sizes of the material layers are selected to compensate for sagging across the width of the cover so that the desired spacing is uniformly maintained when the cover has been deployed. The bladders are deflated as the cover is stored thereby expediting the storage process and reducing the amount of storage space required.

  18. On-Site Disposal Facility Inspection Report

    Office of Legacy Management (LM)

    8947.1 09/13 On-Site Disposal Facility Inspection Report September 2013 6319-D6242 8947.2 09/13 East Face Cell 1 West Face Cell 1 6319D-6208 6319D-6231 8947.3 09/13 North Face Cell 1 North Drainage (looking west) 6319D-6206 6319D-6205 8947.4 09/13 East Face Cell 2 West Face Cell 2 6319D-6230 6319D-6209 8947.5 09/13 East Face Cell 3 West Face Cell 3 6319D-6229 6319D-6210 8947.6 09/13 East Face Cell 4 West Face Cell 4 6319D-6227 6319D-62111 8947.7 09/13 East Face Cell 5 West Face Cell 5 6319D-6226

  19. On-Site Disposal Facility Inspection Report

    Office of Legacy Management (LM)

    72.1 06/14 On-Site Disposal Facility Inspection Report June 2014 6319-D6320 8972.2 06/14 East Face Cell 1 West Face Cell 1 6319D-6322 6319D-6346 8972.3 06/14 North Face Cell 1 North Drainage (looking west) 6319D-6321 6319D-6320 8972.4 06/14 East Face Cell 2 West Face Cell 2 6319D-6345 6319D-6324 8972.5 06/14 East Face Cell 3 West Face Cell 3 6319D-6344 6319D-6325 8972.6 06/14 East Face Cell 4 West Face Cell 4 6319D-6342 6319D-63261 8972.7 06/14 East Face Cell 5 West Face Cell 5 6319D-6341

  20. Radioactive waste disposal package

    DOE Patents [OSTI]

    Lampe, Robert F. (Bethel Park, PA)

    1986-01-01

    A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

  1. Waste disposal package

    DOE Patents [OSTI]

    Smith, M.J.

    1985-06-19

    This is a claim for a waste disposal package including an inner or primary canister for containing hazardous and/or radioactive wastes. The primary canister is encapsulated by an outer or secondary barrier formed of a porous ceramic material to control ingress of water to the canister and the release rate of wastes upon breach on the canister. 4 figs.

  2. Evapotranspiration Cover for the 92-Acre Area Retired Mixed Waste Pits, Area 5 Waste Management Division, Nevada National Security Site, Final CQA Report

    SciTech Connect (OSTI)

    NSTec Environmental Management; The Delphi Groupe, Inc.; J. A. Cesare and Associates, Inc.

    2012-01-31

    The report is the Final Construction Quality Assurance (CQA) Report for the 92-Acrew Evapotranspiration Cover, Area 5 Waste Management Division Retired Mixed Waste Pits, Nevada National Security Site, Nevada, for the period of January 20, 2011, to January 31, 2012 The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. The 92-Acre Area encompasses the southern portion of the Area 5 RWMS, which has been designated for the first final closure operations. This area contains 13 Greater Confinement Disposal (GCD) boreholes, 16 narrow trenches, and 9 broader pits. With the exception of two active pits (P03 and P06), all trenches and pits in the 92-Acre Area had operational covers approximately 2.4 meters thick, at a minimum, in most areas when this project began. The units within the 92-Acre Area are grouped into the following six informal categories based on physical location, waste types and regulatory requirements: (1) Pit 3 Mixed Waste Disposal Unit (MWDU); (2) Corrective Action Unit (CAU) 111; (3) CAU 207; (4) Low-level waste disposal units; (5) Asbestiform low-level waste disposal units; and (6) One transuranic (TRU) waste trench.

  3. ARM - Cover Competition Winners

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

    MeetingsCover Competition Winners Science Team Meetings 2009 2008 2007 2006 2005 2004 2003 2002 2001 2000 1999 1998 1997 1996 1995 1994 1993 1992 Cover Competition Winners In order to gather more ARM science images, the ARM Science Team Meeting began a competition for the coveted meeting program cover. From 2004-2009, ARM principal investigators were invited to share their research images with meeting organizers for selection by the ARM Chief Scientist. Covers were selected based on their

  4. Electrochemical apparatus comprising modified disposable rectangular cuvette

    DOE Patents [OSTI]

    Dattelbaum, Andrew M; Gupta, Gautam; Morris, David E

    2013-09-10

    Electrochemical apparatus includes a disposable rectangular cuvette modified with at least one hole through a side and/or the bottom. Apparatus may include more than one cuvette, which in practice is a disposable rectangular glass or plastic cuvette modified by drilling the hole(s) through. The apparatus include two plates and some means of fastening one plate to the other. The apparatus may be interfaced with a fiber optic or microscope objective, and a spectrometer for spectroscopic studies. The apparatus are suitable for a variety of electrochemical experiments, including surface electrochemistry, bulk electrolysis, and flow cell experiments.

  5. Tuba City, Arizona, Disposal Site Community Information

    Office of Legacy Management (LM)

    C O M M U N I T Y I N F O R M A T I O N Tuba City, Arizona, Disposal Site Tuba City Site Background 1954-1955 Tuba City mill is built. 1956-1966 Rare Metals Corporation and El Paso Natural Gas Company operate the uranium- and vanadium-ore processing mill. Chemicals from tailings piles and ponds leak into the soil and groundwater during milling operations. 1988 U.S. Department of Energy (DOE) cleans up materials from former milling operations. 1990 Mill tailings are placed in a disposal cell. A

  6. Oil field waste disposal costs at commercial disposal facilities

    SciTech Connect (OSTI)

    Veil, J.A.

    1997-10-01

    The exploration and production segment of the U.S. oil and gas industry generates millions of barrels of nonhazardous oil field wastes annually. In most cases, operators can dispose of their oil fields wastes at a lower cost on-site than off site and, thus, will choose on-site disposal. However, a significant quantity of oil field wastes are still sent to off-site commercial facilities for disposal. This paper provides information on the availability of commercial disposal companies in different states, the treatment and disposal methods they employ, and how much they charge. There appear to be two major off-site disposal trends. Numerous commercial disposal companies that handle oil field wastes exclusively are located in nine oil-and gas-producing states. They use the same disposal methods as those used for on-site disposal. In addition, the Railroad Commission of Texas has issued permits to allow several salt caverns to be used for disposal of oil field wastes. Twenty-two other oil- and gas-producing states contain few or no disposal companies dedicated to oil and gas industry waste. The only off-site commercial disposal companies available handle general industrial wastes or are sanitary landfills. In those states, operators needing to dispose of oil field wastes off-site must send them to a local landfill or out of state. The cost of off-site commercial disposal varies substantially, depending on the disposal method used, the state in which the disposal company is located, and the degree of competition in the area.

  7. Lakeview, Oregon, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    ... a soilrock matrix layer on the top and rock (riprap) on the side slopes to protect against wind and water erosion. The top of the disposal cell supports native brush and grasses. ...

  8. Shafts Temporarily Covered

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

    3, 2014 Shafts Temporarily Covered Today, workers continued physical preparations for the filter replacement. The Air Intake Shaft and Salt Handling Shaft openings were temporarily covered to further reduce the amount of air entering the underground. Covering these opening helps maintain ventilation balance while continuing to draw surface air down to the waste shaft, and prevents unfiltered air from exiting the underground. Workers not directly involved in the filter replacement efforts

  9. NERSC Journal Cover Stories

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

    | png | 729 KB AGU-WRR2015Cover.png Numerical simulation of the environmental impact of hydraulic fracturing of tightshale gas reservoirs on near-surface groundwater:...

  10. Recommendation 223: Recommendations on Additional Waste Disposal...

    Office of Environmental Management (EM)

    3: Recommendations on Additional Waste Disposal Capacity Recommendation 223: Recommendations on Additional Waste Disposal Capacity ORSSAB's recommendations encourage DOE to...

  11. Transportation, Aging and Disposal Canister System Performance...

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

    Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 ...

  12. Pioneering Nuclear Waste Disposal

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

    PIONEERING NUCLEAR WASTE DISPOSAL U.S. Department of Energy Carlsbad Area Office February 2000 DOE/CAO-00-3124 T h e W a s t e I s o l a t i o n P i l o t P l a n t ii Table of Contents Closing the Circle on Transuranic Waste 1 The Long Road to the WIPP 3 The need for the WIPP The National Academy of Sciences Community leaders suggest Carlsbad as the site for the WIPP Construction of the WIPP The WIPP Land Withdrawal Act Certification by the EPA The National Environmental Policy Act The Resource

  13. Radioactive waste material disposal

    DOE Patents [OSTI]

    Forsberg, Charles W.; Beahm, Edward C.; Parker, George W.

    1995-01-01

    The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

  14. Radioactive waste material disposal

    DOE Patents [OSTI]

    Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

    1995-10-24

    The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

  15. Evapotranspiration Cover for the 92-Acre Area Retired Mixed Waste Pits:Interim CQA Report

    SciTech Connect (OSTI)

    The Delphi Groupe, Inc., and J. A. Cesare and Associates, Inc.

    2011-06-20

    This Interim Construction Quality Assurance (CQA) Report is for the 92-Acre Evapotranspiration Cover, Area 5 Waste Management Division (WMD) Retired Mixed Waste Pits, Nevada National Security Site, Nevada for the period of January 20, 2011 to May 12, 2011. This Interim Construction Quality Assurance (CQA) Report is for the 92-Acre Evapotranspiration Cover, Area 5 Waste Management Division (WMD) Retired Mixed Waste Pits, Nevada National Security Site, Nevada for the period of January 20, 2011 to May 12, 2011. Construction was approved by the Nevada Division of Environmental Protection (NDEP) under the Approval of Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) for Corrective Action Unit (CAU) 111: Area 5 WMD Retired Mixed Waste Pits, Nevada National Security Site, Nevada, on January 6, 2011, pursuant to Subpart XII.8a of the Federal Facility Agreement and Consent Order. The project is located in Area 5 of the Radioactive Waste Management Complex (RWMC) at the Nevada National Security Site (NNSS), formerly known as the Nevada Test Site, located in southern Nevada, approximately 65 miles northwest of Las Vegas, Nevada, in Nye County. The project site, in Area 5, is located in a topographically closed basin approximately 14 additional miles north of Mercury Nevada, in the north-central part of Frenchman Flat. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. The 92-Acre Area encompasses the southern portion of the Area 5 RWMS, which has been designated for the first final closure operations. This area contains 13 Greater Confinement Disposal (GCD) boreholes, 16 narrow trenches, and 9 broader pits. With the exception of two active pits (P03 and P06), all trenches and pits in the 92-Acre Area had operational covers approximately 2.4 meters thick, at a minimum, in most areas when this project began. The units within the 92-Acre Area are grouped into the following six informal categories based on physical location, waste types and regulatory requirements: (1) Pit 3 Mixed Waste Disposal Unit (MWDU); (2) Corrective Action Unit (CAU) 111; (3) CAU 207; (4) Low-level waste disposal units; (5) Asbestiform low-level waste disposal units; and (6) One transuranic (TRU) waste trench.

  16. COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS

    SciTech Connect (OSTI)

    THIELGES, J.R.; CHASTAIN, S.A.

    2007-06-21

    The Disposable Solid Waste Cask (DSWC) is a shielded cask capable of transporting, storing, and disposing of six non-fuel core components or approximately 27 cubic feet of radioactive solid waste. Five existing DSWCs are candidates for use in storing and disposing of non-fuel core components and radioactive solid waste from the Interim Examination and Maintenance Cell, ultimately shipping them to the 200 West Area disposal site for burial. A series of inspections, studies, analyses, and modifications were performed to ensure that these casks can be used to safely ship solid waste. These inspections, studies, analyses, and modifications are summarized and attached in this report. Visual inspection of the casks interiors provided information with respect to condition of the casks inner liners. Because water was allowed to enter the casks for varying lengths of time, condition of the cask liner pipe to bottom plate weld was of concern. Based on the visual inspection and a corrosion study, it was concluded that four of the five casks can be used from a corrosion standpoint. Only DSWC S/N-004 would need additional inspection and analysis to determine its usefulness. The five remaining DSWCs underwent some modification to prepare them for use. The existing cask lifting inserts were found to be corroded and deemed unusable. New lifting anchor bolts were installed to replace the existing anchors. Alternate lift lugs were fabricated for use with the new lifting anchor bolts. The cask tiedown frame was modified to facilitate adjustment of the cask tiedowns. As a result of the above mentioned inspections, studies, analysis, and modifications, four of the five existing casks can be used to store and transport waste from the Interim Examination and Maintenance Cell to the disposal site for burial. The fifth cask, DSWC S/N-004, would require further inspections before it could be used.

  17. Journal Cover Stories

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

    NatureCoverLarge.png High-quality electron beams from a laser wakefield accelerator using plasma-channel guiding September 30, 2004 | Author(s): C. G. R. Geddes, Cs. Toth, J. van Tilborg, E. Esarey, C. B. Schroeder, D. Bruhwiler, C. Nieter, J. Cary & W. P. Leemans | Source: Nature | Category: Fusion Energy | URL: http://dx.doi.org/10.1038/nature02900 Download Image: NatureCoverLarge.png | png | 2.7 MB 30 September 2004, Vol. 431, pp. 541-544 PhysTodayCoverLarge.png Integrated Simulation of

  18. Journal Cover Stories

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

    CEN-Cover.png Graphene Moves Toward Applications November 21, 2011 | Author(s): Donghai Mei, et al. | Category: Chemistry | URL: http://dx.doi.org/10.1021/nl203332e Download Image: CEN-Cover.png | png | 986 KB Hierarchically Porous Graphene as a Lithium-Air Battery Electrode. See also http://pubs.acs.org/NanoLett (2011) 11, 5071-5078 SotirisCoverJPCBLarge.jpg Computational Investigation of the First Solvation Shell Structure of Interfacial and Bulk Aqueous Chloride and Iodide Ions November 14,

  19. Nuke Watch New Mexico Perspective on MDA G Cap and Cover

    Broader source: Energy.gov [DOE]

    At the February 12, 2014 Committee meeting Scott Kovac NWNM, Provided Information pertaining to the Proposed Cap and Cover of Material Disposal Area G and NWNMs perspective on it.

  20. Environmental waste disposal contracts awarded

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

    Environmental contracts awarded locally Environmental waste disposal contracts awarded locally Three small businesses with offices in Northern New Mexico awarded nuclear waste...

  1. Disposal Authorization Statement

    Office of Environmental Management (EM)

    November 2005 Through February 2008 | Department of Energy Dispersivity Testing of Zero-Valent Iron Treatment Cells: Monticello, Utah, November 2005 Through February 2008 Dispersivity Testing of Zero-Valent Iron Treatment Cells: Monticello, Utah, November 2005 Through February 2008 Dispersivity Testing of Zero-Valent Iron Treatment Cells: Monticello, Utah, November 2005 Through February 2008 PDF icon Dispersivity Testing of Zero-Valent Iron Treatment Cells: Monticello, Utah, November 2005

  2. Submergible barge retrievable storage and permanent disposal system for radioactive waste

    DOE Patents [OSTI]

    Goldsberry, Fred L.; Cawley, William E.

    1981-01-01

    A submergible barge and process for submerging and storing radioactive waste material along a seabed. A submergible barge receives individual packages of radwaste within segregated cells. The cells are formed integrally within the barge, preferably surrounded by reinforced concrete. The cells are individually sealed by a concrete decking and by concrete hatch covers. Seawater may be vented into the cells for cooling, through an integral vent arrangement. The vent ducts may be attached to pumps when the barge is bouyant. The ducts are also arranged to promote passive ventilation of the cells when the barge is submerged. Packages of the radwaste are loaded into individual cells within the barge. The cells are then sealed and the barge is towed to the designated disposal-storage site. There, the individual cells are flooded and the barge will begin descent controlled by a powered submarine control device to the seabed storage site. The submerged barge will rest on the seabed permanently or until recovered by a submarine control device.

  3. Melter Disposal Strategic Planning Document

    SciTech Connect (OSTI)

    BURBANK, D.A.

    2000-09-25

    This document describes the proposed strategy for disposal of spent and failed melters from the tank waste treatment plant to be built by the Office of River Protection at the Hanford site in Washington. It describes program management activities, disposal and transportation systems, leachate management, permitting, and safety authorization basis approvals needed to execute the strategy.

  4. Integrated Disposal Facility Risk Assessment

    SciTech Connect (OSTI)

    MANN, F. M.

    2003-06-03

    An environmental risk assessment associated with the disposal of projected Immobilized Low-Activity Waste, solid wastes and failed or decommissioned melters in an Integrated Disposal Facility was performed. Based on the analyses all performance objectives associated with the groundwater, air, and intruder pathways were met.

  5. The Solar Way covers

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

    h o t o v o l t a i c s o n I n d i a n L a n d s ACKNOWLEDGEMENTS Cover Photo Rock formation, Narbona Pass, Chuska Mountain Range, Navajo Nation, New Mexico. Since childhood, Paul Denetclaw of the Navajo Nation has wondered when the small rock cradled at the top of the red bluff might fall. Now his children watch. The cover photo was chosen to symbolize what endures: the sun, power from the sun, the earth, and things on it. (Photo courtesy Roger Hill, Sandia National Laboratories) SAND

  6. Reusable pipe flange covers

    DOE Patents [OSTI]

    Holden, James Elliott; Perez, Julieta

    2001-01-01

    A molded, flexible pipe flange cover for temporarily covering a pipe flange and a pipe opening includes a substantially round center portion having a peripheral skirt portion depending from the center portion, the center portion adapted to engage a front side of the pipe flange and to seal the pipe opening. The peripheral skirt portion is formed to include a plurality of circumferentially spaced tabs, wherein free ends of the flexible tabs are formed with respective through passages adapted to receive a drawstring for pulling the tabs together on a back side of the pipe flange.

  7. Unreviewed Disposal Question Evaluation: Waste Disposal In Engineered Trench #3

    SciTech Connect (OSTI)

    Hamm, L. L.; Smith, F. G. III; Flach, G. P.; Hiergesell, R. A.; Butcher, B. T.

    2013-07-29

    Because Engineered Trench #3 (ET#3) will be placed in the location previously designated for Slit Trench #12 (ST#12), Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

  8. Covered Product Category: Displays

    Broader source: Energy.gov [DOE]

    FEMP provides acquisition guidance and federal efficiency requirements across a variety of product categories, including displays, which are covered by the ENERGY STAR program. Federal laws and requirements mandate that agencies meet these efficiency requirements in all procurement and acquisition actions that are not specifically exempted by law.

  9. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Durango, Colorado Page 4-1 4.0 Durango, Colorado, Disposal Site 4.1 Compliance Summary The Durango, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on June 2, 2015. The disposal cell was in good condition. Vegetation on top of the disposal cell was healthy, and several small shrubs growing on the side slopes will be controlled. A small depression observed in 2014 on the disposal cell side slope was no longer apparent. Inspectors identified no

  10. Paducah Waste Disposal | Department of Energy

    Office of Environmental Management (EM)

    Remediation Paducah Waste Disposal Paducah Waste Disposal The U.S. Department of Energy (DOE) is looking at options to dispose of waste that will be generated from further ...

  11. AFV CoverSheet

    Office of Scientific and Technical Information (OSTI)

    ... Cell lines NIH:OVCAR-3, SKOV3, CHO, MDA-MB-231 and LNCaP cells were pur- chased from American Type Culture Collection ... to make in vivo by other techniques and is normally done ...

  12. Performance Assessment and Composit Analysis Material Disposal...

    Office of Environmental Management (EM)

    Performance Assessment and Composit Analysis Material Disposal Area G Revision 4 Performance Assessment and Composit Analysis Material Disposal Area G Revision 4 Los Alamos...

  13. PROPERTY DISPOSAL RECORDS | Department of Energy

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

    PROPERTY DISPOSAL RECORDS These records pertain to the sales by agencies of real and personal property surplus to the needs of the Government PDF icon PROPERTY DISPOSAL RECORDS...

  14. Recommendation 212: Evaluate additional storage and disposal...

    Office of Environmental Management (EM)

    2: Evaluate additional storage and disposal options Recommendation 212: Evaluate additional storage and disposal options The ORSSAB encourages DOE to evaluate additional storage...

  15. Characterization ReportOperational Closure Covers for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

    SciTech Connect (OSTI)

    Bechtel Nevada Geotechnical Sciences

    2005-06-01

    Bechtel Nevada (BN) manages two low-level Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS) for the U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NNSA/NSO). The Area 3 RWMS is located in south-central Yucca Flat and the Area 5 RWMS is located about 15 miles south, in north-central Frenchman Flat. Though located in two separate topographically closed basins, they are similar in climate and hydrogeologic setting. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste, while the Area 3 RWMS uses subsidence craters formed from underground testing of nuclear weapons for the disposal of packaged and unpackaged bulk waste. Over the next several decades, most waste disposal units at both the Area 3 and Area 5 RWMSs are anticipated to be closed. Closure of the Area 3 and Area 5 RWMSs will proceed through three phases: operational closure, final closure, and institutional control. Many waste disposal units at the Area 5RWMS are operationally closed and final closure has been placed on one unit at the Area 3 RWMS (U-3ax/bl). Because of the similarities between the two sites (e.g., type of wastes, environmental factors, operational closure cover designs, etc.), many characterization studies and data collected at the Area 3 RWMS are relevant and applicable to the Area 5 RWMS. For this reason, data and closure strategies from the Area 3 RWMS are referred to as applicable. This document is an interim Characterization Report – Operational Closure Covers, for the Area 5 RWMS. The report briefly describes the Area 5 RWMS and the physical environment where it is located, identifies the regulatory requirements, reviews the approach and schedule for closing, summarizes the monitoring programs, summarizes characterization studies and results, and then presents conclusions and recommendations.

  16. cover_booked.indd

    Energy Savers [EERE]

    DOE/ME-0060 Editors Notes: This Real Property Asset Management Plan covers the Department of Energy including the National Nuclear Security Administration, the Energy Information Administration, and the Power Marketing Administrations. As an independent regulatory agency, the Federal Energy Regulatory Commission (FERC) prepares separate documents. This document is also available on the Department of Energy's web site: http://www.energy.gov. This plan was produced by the Office of Engineering

  17. Journal Cover Stories

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

    Darmon Chem Science 2015 cover page Increasing the rate of hydrogen oxidation without increasing the overpotential: a bio-inspired iron molecular electrocatalyst with an outer coordination sphere proton relay March 5, 2015 | Author(s): Jonathan M. Darmon, Neeraj Kumar, Elliott B. Hulley, Charles J. Weiss, Simone Raugei, R. Morris Bullocka and Monte L. Helm* Center for Molecular Electrocatalysis, Physical Sciences Division, Pacific Northwest National Laboratory, P.O. Box 999, K2-57, Richland, USA

  18. Optimization of Waste Disposal - 13338

    SciTech Connect (OSTI)

    Shephard, E.; Walter, N.; Downey, H.; Collopy, P.; Conant, J.

    2013-07-01

    From 2009 through 2011, remediation of areas of a former fuel cycle facility used for government contract work was conducted. Remediation efforts were focused on building demolition, underground pipeline removal, contaminated soil removal and removal of contaminated sediments from portions of an on-site stream. Prior to conducting the remediation field effort, planning and preparation for remediation (including strategic planning for waste characterization and disposal) was conducted during the design phase. During the remediation field effort, waste characterization and disposal practices were continuously reviewed and refined to optimize waste disposal practices. This paper discusses strategic planning for waste characterization and disposal that was employed in the design phase, and continuously reviewed and refined to optimize efficiency. (authors)

  19. Disposal phase experimental program plan

    SciTech Connect (OSTI)

    1997-01-31

    The Waste Isolation Pilot Plant (WIPP) facility comprises surface and subsurface facilities, including a repository mined in a bedded salt formation at a depth of 2,150 feet. It has been developed to safely and permanently isolate transuranic (TRU) radioactive wastes in a deep geological disposal site. On April 12, 1996, the DOE submitted a revised Resource Conservation and Recovery Act (RCRA) Part B permit application to the New Mexico Environment Department (NMED). The DOE anticipates receiving an operating permit from the NMED; this permit is required prior to the start of disposal operations. On October 29, 1996, the DOE submitted a Compliance Certification Application (CCA) to the US Environmental Protection Agency (EPA) in accordance with the WIPP land Withdrawal Act (LWA) of 1992 (Public Law 102-579) as amended, and the requirements of Title 40 of the Code of Federal Regulations (40 CFR) Parts 191 and 194. The DOE plans to begin disposal operations at the WIPP in November 1997 following receipt of certification by the EPA. The disposal phase is expected to last for 35 years, and will include recertification activities no less than once every five years. This Disposal Phase Experimental Program (DPEP) Plan outlines the experimental program to be conducted during the first 5-year recertification period. It also forms the basis for longer-term activities to be carried out throughout the 35-year disposal phase. Once the WIPP has been shown to be in compliance with regulatory requirements, the disposal phase gives an opportunity to affirm the compliance status of the WIPP, enhance the operations of the WIPP and the national TRU system, and contribute to the resolution of national and international nuclear waste management technical needs. The WIPP is the first facility of its kind in the world. As such, it provides a unique opportunity to advance the technical state of the art for permanent disposal of long-lived radioactive wastes.

  20. Idaho Crews Overcome Challenges to Safely Dispose 1-Million-Pound...

    Office of Environmental Management (EM)

    1-Million-Pound Hot Cell IDAHO FALLS, Idaho - American Recovery and Reinvestment Act cleanup crews at the Idaho site recently disposed of a hot cell as heavy as nine fully ...

  1. Enhanced cover methods for surface coal refuse reclamation

    SciTech Connect (OSTI)

    Gentile, L.F.; Cargill, K.W.; McGarvie, S.D.

    1997-12-31

    Controlling acid rock drainage (ARD) can be a major component of surface mining reclamation. An enhanced reclamation cover system is being constructed to control infiltration of rain water and generation of ARD from coal-refuse disposal areas at a closed mine in southern Illinois. Development of the mine reclamation plan required consideration of ARD generation in coal refuse disposal areas located adjacent to an alluvial aquifer used for public water supply. An integrated site characterization was performed at the mine to provide information to develop and support the enhanced reclamation plan. The enhanced cover system is similar to covers required for municipal solid waste landfills by the Resource Conversation and Recovery Act (RCRA), Subtitle D regulations. The system comprises a graded and compacted gob layer, overlain by a compacted clay liner, and a protective soil cover. The results of infiltration modeling and analyses showed that the standard reclamation cover is effective in reducing infiltration by about 18 percent compared to an unreclaimed coal-refuse surface. The modeling results showed that the inhanced cover system should reduce infiltration by about 84 percent. The geochemical modeling results showed that the reduction in infiltration would help minimize ARD generation and contribute to an earlier reclamation of the mine site.

  2. SPECIAL ANALYSIS OF OPERATIONAL STORMWATER RUNOFF COVERS OVER SLIT TRENCHES

    SciTech Connect (OSTI)

    Collard, L; Luther Hamm, L

    2008-12-18

    Solid Waste Management (SWM) commissioned this Special Analysis (SA) to determine the effects of placing operational stormwater runoff covers (referred to as covers in the remainder of this document) over slit trench (ST) disposal units ST1 through ST7 (the center set of slit trenches). Previously the United States Department of Energy (DOE) entered into an agreement with the United States Environmental Protection Agency (EPA) and the South Carolina Department of Health and Environmental Control (SCDHEC) to place covers over Slit Trenches 1 and 2 to be able to continue disposing Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) solid waste (see USDOE 2008). Because the covers changed the operating conditions, DOE Order 435.1 (DOE 1999) required that an SA be performed to assess the impact. This Special Analysis has been prepared to determine the effects of placing covers over slit trenches at about years 5, 10 and 15 of the 30-year operational period. Because some slit trenches have already been operational for about 15 years, results from analyzing covers at 5 years and 10 years provide trend analysis information only. This SA also examined alternatives of covering Slit Trenches 1 and 2 with one cover and Slit Trenches 3 and 4 with a second cover versus covering them all with a single cover. Based on modeling results, minimal differences exist between covering Slit Trench groups 1-2 and 3-4 with two covers or one large cover. This SA demonstrates that placement of covers over slit trenches will slow the subsequent release and transport of radionuclides in the vadose zone in the early time periods (from time of placement until about 100 years). Release and transport of some radionuclides in the vadose zone beyond 100 years were somewhat higher than for the case without covers. The sums-of-fractions (SOFs) were examined for the current waste inventory in ST1 and ST2 and for estimated inventories at closure for ST3 through ST7. In all cases SOFs were less than one (except for one SOF for ST5 that remained at one), indicating that there should be no unacceptable impacts on operations from placing covers for the cover alternatives that were analyzed. Minimal operational limits provided in Table 4 should be used as the new set of limits for Slit Trenches 1 through 7. ST1 and ST2 are expected to be covered about 15 years after the first disposal in ST1. Because the time of actual placement of covers over the other slit trenches is unknown, this SA did not consider limit increases, only limit decreases. Thus, each minimal operational limit is the minimum of the Performance Assessment (PA) final limit and the limit calculated in this SA if covers were placed at about 5, 10 or 15 years. If other cover times are desired, further analysis will be required.

  3. Transportation, Aging and Disposal Canister System Performance

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

    Specification: Revision 1 | Department of Energy Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 This document provides specifications for selected system components of the Transportation, Aging and Disposal (TAD) canister-based system. PDF icon Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 More Documents &

  4. International Collaboration Activities in Different Geologic Disposal

    Energy Savers [EERE]

    Environments | Department of Energy Collaboration Activities in Different Geologic Disposal Environments International Collaboration Activities in Different Geologic Disposal Environments This report describes the current status of international collaboration regarding geologic disposal research in the Used Fuel Disposition (UFD) Campaign. To date, UFD's International Disposal R&D Program has established formal collaboration agreements with five international initiatives and several

  5. 2015 Annual Inspection Report for the Parkersburg, West Virginia Disposal Site

    Office of Legacy Management (LM)

    Annual Inspection Report December 2015 Parkersburg, West Virginia Page 1 2015 Annual Inspection Report for the Parkersburg, West Virginia Disposal Site 1.0 Inspection Summary The Parkersburg, West Virginia, Nuclear Waste Policy Act Section 151(c) Disposal Site was inspected on October 29, 2015. The site was in excellent condition. No evidence of erosion or slope instability on the disposal cell was noted during the inspection. A follow-up or contingency inspection is not required. No evidence of

  6. Tank Waste Disposal Program redefinition

    SciTech Connect (OSTI)

    Grygiel, M.L.; Augustine, C.A.; Cahill, M.A.; Garfield, J.S.; Johnson, M.E.; Kupfer, M.J.; Meyer, G.A.; Roecker, J.H.; Holton, L.K.; Hunter, V.L.; Triplett, M.B.

    1991-10-01

    The record of decision (ROD) (DOE 1988) on the Final Environmental Impact Statement, Hanford Defense High-Level, Transuranic and Tank Wastes, Hanford Site, Richland Washington identifies the method for disposal of double-shell tank waste and cesium and strontium capsules at the Hanford Site. The ROD also identifies the need for additional evaluations before a final decision is made on the disposal of single-shell tank waste. This document presents the results of systematic evaluation of the present technical circumstances, alternatives, and regulatory requirements in light of the values of the leaders and constitutents of the program. It recommends a three-phased approach for disposing of tank wastes. This approach allows mature technologies to be applied to the treatment of well-understood waste forms in the near term, while providing time for the development and deployment of successively more advanced pretreatment technologies. The advanced technologies will accelerate disposal by reducing the volume of waste to be vitrified. This document also recommends integration of the double-and single-shell tank waste disposal programs, provides a target schedule for implementation of the selected approach, and describes the essential elements of a program to be baselined in 1992.

  7. The Current Status of Radioactive Waste Management and Planning for Near Surface Disposal in Indonesia

    SciTech Connect (OSTI)

    Purnomo, A. S.

    2003-02-24

    Near surface disposal has been practiced for some decades, with a wide variation in sites, types and amounts of wastes, and facility designs employed. Experience has shown that the effective and safe isolation of waste depends on the performance of the overall disposal system, which is formed by three major components or barriers: the site, the disposal facility and the waste form. Near surface disposal also rely on active institutional controls, such as monitoring and maintenance. The objective of radioactive waste disposal is to isolate waste so that it does not result in undue radiation exposure to humans and the environment. The required degree of isolation can be obtained by implementing various disposal methods, of which near surface disposal represents an option commonly used and demonstrated in several countries. In near surface disposal, the disposal facility is located on or below the ground surface, where the protective covering is generally a few meters thick. The se facilities are intended to contain low and intermediate level waste without appreciable quantities of long-lived radionuclides.

  8. Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site

    SciTech Connect (OSTI)

    D. Wieland, V. Yucel, L. Desotell, G. Shott, J. Wrapp

    2008-04-01

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) plans to close the waste and classified material storage cells in the southeast quadrant of the Area 5 Radioactive Waste Management Site (RWMS), informally known as the '92-Acre Area', by 2011. The 25 shallow trenches and pits and the 13 Greater Confinement Disposal (GCD) borings contain various waste streams including low-level waste (LLW), low-level mixed waste (LLMW), transuranic (TRU), mixed transuranic (MTRU), and high specific activity LLW. The cells are managed under several regulatory and permit programs by the U.S. Department of Energy (DOE) and the Nevada Division of Environmental Protection (NDEP). Although the specific closure requirements for each cell vary, 37 closely spaced cells will be closed under a single integrated monolayer evapotranspirative (ET) final cover. One cell will be closed under a separate cover concurrently. The site setting and climate constrain transport pathways and are factors in the technical approach to closure and performance assessment. Successful implementation of the integrated closure plan requires excellent communication and coordination between NNSA/NSO and the regulators.

  9. Solar module having reflector between cells

    DOE Patents [OSTI]

    Kardauskas, Michael J.

    1999-01-01

    A photovoltaic module comprising an array of electrically interconnected photovoltaic cells disposed in a planar and mutually spaced relationship between a light-transparent front cover member in sheet form and a back sheet structure is provided with a novel light-reflecting means disposed between adjacent cells for reflecting light falling in the areas between cells back toward said transparent cover member for further internal reflection onto the solar cells. The light-reflecting comprises a flexible plastic film that has been embossed so as to have a plurality of small V-shaped grooves in its front surface, and a thin light-reflecting coating on said front surface, the portions of said coating along the sides of said grooves forming light-reflecting facets, said grooves being formed so that said facets will reflect light impinging thereon back into said transparent cover sheet with an angle of incidence greater than the critical angle, whereby substantially all of the reflected light will be internally reflected from said cover sheet back to said solar modules, thereby increasing the current output of the module.

  10. Depleted uranium disposal options evaluation

    SciTech Connect (OSTI)

    Hertzler, T.J.; Nishimoto, D.D.; Otis, M.D.

    1994-05-01

    The Department of Energy (DOE), Office of Environmental Restoration and Waste Management, has chartered a study to evaluate alternative management strategies for depleted uranium (DU) currently stored throughout the DOE complex. Historically, DU has been maintained as a strategic resource because of uses for DU metal and potential uses for further enrichment or for uranium oxide as breeder reactor blanket fuel. This study has focused on evaluating the disposal options for DU if it were considered a waste. This report is in no way declaring these DU reserves a ``waste,`` but is intended to provide baseline data for comparison with other management options for use of DU. To PICS considered in this report include: Retrievable disposal; permanent disposal; health hazards; radiation toxicity and chemical toxicity.

  11. Disposable telemetry cable deployment system

    DOE Patents [OSTI]

    Holcomb, David Joseph (Sandia Park, NM)

    2000-01-01

    A disposable telemetry cable deployment system for facilitating information retrieval while drilling a well includes a cable spool adapted for insertion into a drill string and an unarmored fiber optic cable spooled onto the spool cable and having a downhole end and a stinger end. Connected to the cable spool is a rigid stinger which extends through a kelly of the drilling apparatus. A data transmission device for transmitting data to a data acquisition system is disposed either within or on the upper end of the rigid stinger.

  12. DISPOSAL OF EXCESS REAL PROPERTY

    Office of Legacy Management (LM)

    . . : '* FEB 1972. : . .. - .. ..' *. ,; --.. . *..,,, :. :-, -, ' :.: t:-,...: : ,. -.". .- v ;; -'.1.;, ; . , DISPOSAL OF EXCESS REAL PROPERTY PARCEL 228 " . ;: 'i: .-. ' ' . -- - , *: , ; b;- .;.= ' i .; ,s ' ; .: '- :. ,S,, - ; * ^. ',. *. ;;: : ' " . - .. ,'~', approval is requested to report as excess a 20-acre;tract of landand improvements. The tract is located within the Oak Ridge comnunity near the intersection of Melton Lake Drive and the Oak Ridge Turnpike and is

  13. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    UMTRCA Title I Annual Report March 2016 Grand Junction, Colorado Page 6-1 6.0 Grand Junction, Colorado, Disposal Site 6.1 Compliance Summary The Grand Junction, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on December 8, 2015. A portion of the disposal cell remains open to receive low-level radioactive materials from various sources; the open cell and its supporting structures and facilities are not included in the annual inspection. Ongoing

  14. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Gunnison, Colorado Page 8-1 8.0 Gunnison, Colorado, Disposal Site 8.1 Compliance Summary The Gunnison, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on July 1, 2015. The disposal cell and all associated surface water diversion and drainage structures were in excellent condition and functioning as designed. Six riprap test areas on the cell apron and diversion ditches were visually inspected; no rock degradation was noted when compared to 2012

  15. Disposal of NORM waste in salt caverns

    SciTech Connect (OSTI)

    Veil, J.A.; Smith, K.P.; Tomasko, D.; Elcock, D.; Blunt, D.; Williams, G.P.

    1998-07-01

    Some types of oil and gas production and processing wastes contain naturally occurring radioactive materials (NORM). If NORM is present at concentrations above regulatory levels in oil field waste, the waste requires special disposal practices. The existing disposal options for wastes containing NORM are limited and costly. This paper evaluates the legality, technical feasibility, economics, and human health risk of disposing of NORM-contaminated oil field wastes in salt caverns. Cavern disposal of NORM waste is technically feasible and poses a very low human health risk. From a legal perspective, there are no fatal flaws that would prevent a state regulatory agency from approving cavern disposal of NORM. On the basis of the costs charged by caverns currently used for disposal of nonhazardous oil field waste (NOW), NORM waste disposal caverns could be cost competitive with existing NORM waste disposal methods when regulatory agencies approve the practice.

  16. Z-Bed Recovery Water Disposal

    Office of Environmental Management (EM)

    Z-Bed Recovery Water Disposal Tritium Programs Engineering Louis Boone Josh Segura ... detailed explanation of the plan to capture and dispose of Z-Bed Recovery (ZR) water. ...

  17. Transmittal Memo for Disposal Authorization Statement

    Broader source: Energy.gov [DOE]

    The Low-Level Waste Disposal Facility Federal Review Group (LFRG) has conducted a review of the Savannah River Site (SRS) Saltstone Disposal Facility (SDF) 2009 performance assessment (PA) in...

  18. Disposal Practices at the Nevada Test Site 2008 | Department...

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

    Disposal Practices at the Nevada Test Site 2008 Disposal Practices at the Nevada Test Site 2008 Full Document and Summary Versions are available for download PDF icon Disposal ...

  19. Electrochemical apparatus comprising modified disposable rectangular

    Office of Scientific and Technical Information (OSTI)

    cuvette (Patent) | SciTech Connect Electrochemical apparatus comprising modified disposable rectangular cuvette Citation Details In-Document Search Title: Electrochemical apparatus comprising modified disposable rectangular cuvette Electrochemical apparatus includes a disposable rectangular cuvette modified with at least one hole through a side and/or the bottom. Apparatus may include more than one cuvette, which in practice is a disposable rectangular glass or plastic cuvette modified by

  20. Falls City, Texas, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Falls City, Texas, Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site located at Falls City, Texas. The site is managed by the U.S. Department of Energy Office of Legacy Management. Location of the Falls City Disposal Site Site Description and History The Falls City disposal site is the location of a former uranium-ore processing facility in Karnes County, Texas, approximately 40 miles southeast of San Antonio

  1. Maxey Flats, Kentucky, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    3 Fact Sheet Maxey Flats, Kentucky, Disposal Site This fact sheet provides information about the Maxey Flats, Kentucky, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under the Comprehensive Environmental Response, Compensation, and Liability Act. Location of the Maxey Flats, Kentucky, Disposal Site Site Description and History The Maxey Flats site is an inactive, low-level radioactive waste disposal site located in eastern Kentucky about 10

  2. Monticello, Utah, Disposal and Processing Sites

    Office of Legacy Management (LM)

    Monticello, Utah, Disposal and Processing Sites This fact sheet provides information about the Monticello, Utah, Disposal and Processing Sites. These sites are managed by the U.S. Department of Energy Office of Legacy Management under the Comprehensive Environmental Response, Compensation, and Liability Act. Location of the Monticello, Utah, Disposal and Processing Sites Site Description and History The Monticello, Utah, Disposal and Processing Sites are located in and near the city of

  3. Sherwood, Washington, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Sherwood, Washington, Disposal Site This fact sheet provides information about the Sherwood, Washington, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under Title II of the Uranium Mill Tailings Radiation Control Act of 1978. Location of the Sherwood, Washington, Disposal Site Site Description and History The Sherwood disposal site is a former uranium-ore processing site operated by Western Nuclear, Inc. The site is in Stevens County near the

  4. Electrochemical Apparatus with Disposable and Modifiable Parts

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

    research Benefits: Incorporates disposable, commercially available cuvettes Modifiable design Allows multiple experiments using a single solution Designed for interface with...

  5. The Future Through the Past: The Use of Analog Sites for Design Criteria and Long Term Performance Assessment of Evapotranspiration Landfill Covers

    SciTech Connect (OSTI)

    Shafer, D. S.; Miller, J. J.; Young, M. H.; Edwards, S. C.; Rawlinson, S. E.

    2002-02-26

    There is growing support for using evapotranspiration (ET) covers for closure of low-level waste (LLW) and other types of waste disposal sites, particularly in the lower latitude arid regions of the western United States. At the Nevada Test Site (NTS), monolayer ET covers are the baseline technology for closure of LLW and mixed LLW cells. To better predict the long-term performance of monolayer ET covers, as well as to identify design criteria that will potentially improve their performance, the properties of, and processes occurring on, analog sites for ET covers on the NTS are being studied. The project is funded through the Subsurface Contaminants Focus Area of the U.S. Department of Energy. Four analog sites on the NTS have been selected to predict performance of ET covers over a 1,000-year compliance period. Two sites are relatively recently disturbed (within the last 50 years) and have been selected to evaluate processes and changes on ET covers for the early period after active cover maintenance is discontinued. Two other sites, late to mid-Holocene in age, are intended as analogs for the end of the compliance period (1,000 years or more); both surfaces are abandoned alluvial/colluvial deposits. The history of the early post-institutional control analog sites are being evaluated by an archaeologist to help determine when the sites were last disturbed or modified, and the mode of disturbance to help set baseline conditions. Similar to other ''landforms,'' ET covers will evolve over time because of pedogenic, biotic, and climatic processes. Properties of analog sites that could affect ET water balance performance will be evaluated to help understand ET cover performance over time.

  6. Disposable remote zero headspace extractor

    DOE Patents [OSTI]

    Hand, Julie J.; Roberts, Mark P.

    2006-03-21

    The remote zero headspace extractor uses a sampling container inside a stainless steel vessel to perform toxicity characteristics leaching procedure to analyze volatile organic compounds. The system uses an in line filter for ease of replacement. This eliminates cleaning and disassembly of the extractor. All connections are made with quick connect fittings which can be easily replaced. After use, the bag can be removed and disposed of, and a new sampling container is inserted for the next extraction.

  7. DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    E. F. Loros

    2000-06-30

    The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from the Waste Package Remediation System. The Disposal Container Handling System begins with new DC preparation, which includes installing collars, tilting the DC upright, and outfitting the container for the specific fuel it is to receive. DCs and their lids are staged in the receipt area for transfer to the needed location. When called for, a DC is put on a cart and sent through an airlock into a hot cell. From this point on, all processes are done remotely. The DC transfer operation moves the DC to the ATS or CTS for loading and then receives the DC for welding. The DC welding operation receives loaded DCs directly from the waste handling lines or from interim lag storage for welding of the lids. The welding operation includes mounting the DC on a turntable, removing lid seals, and installing and welding the inner and outer lids. After the weld process and non-destructive examination are successfully completed, the WP is either staged or transferred to a tilting station. At the tilting station, the WP is tilted horizontally onto a cart and the collars removed. The cart is taken through an air lock where the WP is lifted, surveyed, decontaminated if required, and then moved into the Waste Emplacement/Retrieval System. DCs that do not meet the welding non-destructive examination criteria are transferred to the Waste Package Remediation System for weld preparation or removal of the lids. The Disposal Container Handling System is contained within the Waste Handling Building System. This includes the primary hot cell bounded by the receiving area and WP transport exit air locks; and isolation doors at ATS, CTS, and Waste Package Remediation. The hot cell includes areas for welding, various staging, tilting, and WP transporter loading. There are associated operating galleries and equipment maintenance areas outside the hot cell. These areas operate concurrently to accommodate the DC/WP throughput rates and support system maintenance. The new DC preparation area is located in an unshielded structure. The handling equipment includes DC/WP bridge cranes, tilting stations, and horizontal transfer carts. The welding area includes DC/WP welders and staging stations. Welding operations are supported by remotely operated equipment including a bridge crane and hoists, welder jib cranes, welding turntables, and manipulators. WP transfer includes a transfer/decontamination and transporter load area. The transfer operations are supported by a remotely operated horizontal lifting system, decontamination system, decontamination and inspection manipulator, and a WP horizontal transfer cart. All handling operations are supported by a suite of fixtures including collars, yokes, lift beams, and lid attachments. Remote equipment is designed to facilitate decontamination and maintenance. Interchangeable components are provided where appropriate. Set-aside areas are included, as required, for fixtures and tooling to support off-normal and recovery operations. Semi-automatic, manual, and backup control methods support normal, maintenance, and recovery operations. The system interfaces with the ATS and CTS to provide empty and receive loaded DCs. The Waste Emplacement/Retrieval System interfaces are for loading/unloading WPs on/from the transporter. The system also interfaces with the Waste Package Remediation System for DC/WP repair. The system is housed, shielded, supported, and has ventilation boundaries by the Waste Handling Building (WHB). The system is ventilated by the WHB Ventilation System, which in conjunction with ventilation boundaries ensure that ai

  8. Covered Product Category: Enterprise Servers

    Broader source: Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) provides acquisition guidance and Federal efficiency requirements for enterprise servers, which are covered by the ENERGY STAR program.

  9. Covered Product Category: Commercial Griddles

    Broader source: Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) provides acquisition guidance for commercial griddles, which is a product category covered by the ENERGY STAR program

  10. Covered Product Category: Commercial Fryers

    Broader source: Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) provides acquisition guidance for commercial fryers, which is a product category covered by the ENERGY STAR program.

  11. Recommended Procedures for Measuring Radon Fluxes from Disposal Sites of Residual Radioactive Materials

    SciTech Connect (OSTI)

    Young,, J. A.; Thomas, V. W.; Jackson, P. 0.

    1983-03-01

    This report recornmenrls instrumentation and methods suitable for measuring radon fluxes emanating from covered disposal sites of residual radioactive materials such as uranium mill tailings. Problems of spatial and temporal variations in radon flux are discussed and the advantages and disadvantages of several instruments are examined. A year-long measurement program and a two rnonth measurement rnethodology are then presented based on the inherent difficulties of measuring average radon flux over a cover using the recommended instrumentation.

  12. Covered Product Category: Imaging Equipment

    Broader source: Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) provides acquisition guidance for imaging equipment, a product category covered by the ENERGY STAR program. Federal laws and requirements mandate that agencies buy ENERGY STAR qualified products in all product categories covered by this program and any acquisition actions that are not specifically exempted by law.

  13. Overview of Nevada Test Site Radioactive and Mixed Waste Disposal Operations

    SciTech Connect (OSTI)

    J.T. Carilli; S.K. Krenzien; R.G. Geisinger; S.J. Gordon; B. Quinn

    2009-03-01

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office Environmental Management Program is responsible for carrying out the disposal of on-site and off-site generated low-level radioactive waste (LLW) and low-level radioactive mixed waste (MW) at the Nevada Test Site (NTS). Core elements of this mission are ensuring safe and cost-effective disposal while protecting workers, the public, and the environment. This paper focuses on the impacts of new policies, processes, and opportunities at the NTS related to LLW and MW. Covered topics include: the first year of direct funding for NTS waste disposal operations; zero tolerance policy for non-compliant packages; the suspension of mixed waste disposal; waste acceptance changes; DOE Consolidated Audit Program (DOECAP) auditing; the 92-Acre Area closure plan; new eligibility requirements for generators; and operational successes with unusual waste streams.

  14. Coupled Environmental Processes and Long-term Performance of Landfill Covers in the northern Mojave Desert

    SciTech Connect (OSTI)

    David Shafer; Michael Young; Stephen Zitzer; Eric McDonald; Todd Caldwell

    2004-05-12

    Evapotransiration (ET) covers have gained widespread acceptance as a closure feature for waste disposal sites, particularly in the arid and semi-arid regions of the southwestern U.S. But as landforms, ET covers are subject to change over time because of processes such as pedogenesis, hydrologic processes, vegetation establishment and change, and biological processes. To better understand the effects of coupled process changes to ET covers, a series of four primary analog sites in Yucca Flat on the Nevada Test Site, along with measurements and observations from other locations in the Mojave Desert, were selected to evaluate changes in ET covers over time. The analog sites, of varying ages, were selected to address changes in the early post-institutional control period, the 1,000-year compliance period for disposal of low-level and mixed low-level waste, and the 10,000-year compliance period for transuranic waste sites.

  15. Taiwan industrial cooperation program technology transfer for low-level radioactive waste final disposal - phase I.

    SciTech Connect (OSTI)

    Knowlton, Robert G.; Cochran, John Russell; Arnold, Bill Walter; Jow, Hong-Nian; Mattie, Patrick D.; Schelling, Frank Joseph Jr.

    2007-01-01

    Sandia National Laboratories and the Institute of Nuclear Energy Research, Taiwan have collaborated in a technology transfer program related to low-level radioactive waste (LLW) disposal in Taiwan. Phase I of this program included regulatory analysis of LLW final disposal, development of LLW disposal performance assessment capabilities, and preliminary performance assessments of two potential disposal sites. Performance objectives were based on regulations in Taiwan and comparisons to those in the United States. Probabilistic performance assessment models were constructed based on limited site data using software including GoldSim, BLT-MS, FEHM, and HELP. These software codes provided the probabilistic framework, container degradation, waste-form leaching, groundwater flow, radionuclide transport, and cover infiltration simulation capabilities in the performance assessment. Preliminary performance assessment analyses were conducted for a near-surface disposal system and a mined cavern disposal system at two representative sites in Taiwan. Results of example calculations indicate peak simulated concentrations to a receptor within a few hundred years of LLW disposal, primarily from highly soluble, non-sorbing radionuclides.

  16. 1999 Report on Hanford Site land disposal restriction for mixed waste

    SciTech Connect (OSTI)

    BLACK, D.G.

    1999-03-25

    This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-011. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility.

  17. WIPP - Shipment & Disposal Information

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

    Shipment & Disposal Information Shipments Received As of February 11, 2014 Site Shipments Loaded Miles Argonne National Laboratory 193 331,333 Bettis Atomic Power Laboratory 5 10,955 GE Vallecitos Nuclear Center 32 44,800 Idaho National Laboratory 5,844 8,132,064 Los Alamos National Laboratory 1,344 459,648 Lawrence Livermore National Laboratory 18 24,804 Nevada Test Site 48 57,312 Oak Ridge National Laboratory 131 175,933 Rocky Flats Environmental Technology Site 2,045 1,446,444 Hanford

  18. DOE SPENT NUCLEAR FUEL DISPOSAL CONTAINER

    SciTech Connect (OSTI)

    F. Habashi

    1998-06-26

    The DOE Spent Nuclear Fuel Disposal Container (SNF DC) supports the confinement and isolation of waste within the Engineered Barrier System of the Mined Geologic Disposal System (MGDS). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the access mains, and emplaced in emplacement drifts. The DOE Spent Nuclear Fuel Disposal Container provides long term confinement of DOE SNF waste, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The DOE SNF Disposal Containers provide containment of waste for a designated period of time, and limit radionuclide release thereafter. The disposal containers maintain the waste in a designated configuration, withstand maximum handling and rockfall loads, limit the individual waste canister temperatures after emplacement. The disposal containers also limit the introduction of moderator into the disposal container during the criticality control period, resist corrosion in the expected repository environment, and provide complete or limited containment of waste in the event of an accident. Multiple disposal container designs may be needed to accommodate the expected range of DOE Spent Nuclear Fuel. The disposal container will include outer and inner barrier walls and outer and inner barrier lids. Exterior labels will identify the disposal container and contents. Differing metal barriers will support the design philosophy of defense in depth. The use of materials with different failure mechanisms prevents a single mode failure from breaching the waste package. The corrosion-resistant inner barrier and inner barrier lid will be constructed of a high-nickel alloy and the corrosion-allowance outer barrier and outer barrier lid will be made of carbon steel. The DOE Spent Nuclear Fuel Disposal Containers interface with the emplacement drift environment by transferring heat from the waste to the external environment and by protecting the DOE waste canisters and their contents from damage/degradation by the external environment. The disposal containers also interface with the SNF by limiting access of moderator and oxidizing agents to the waste. The disposal containers interface with the Ex-Container System's emplacement drift disposal container supports. The disposal containers interface with the Canister Transfer System, Waste Emplacement System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and remediation of the disposal container.

  19. Aerosol can waste disposal device

    DOE Patents [OSTI]

    O'Brien, Michael D.; Klapperick, Robert L.; Bell, Chris

    1993-01-01

    Disclosed is a device for removing gases and liquid from containers. The ice punctures the bottom of a container for purposes of exhausting gases and liquid from the container without their escaping into the atmosphere. The device includes an inner cup or cylinder having a top portion with an open end for receiving a container and a bottom portion which may be fastened to a disposal or waste container in a substantially leak-proof manner. A piercing device is mounted in the lower portion of the inner cylinder for puncturing the can bottom placed in the inner cylinder. An outer cylinder having an open end and a closed end fits over the top portion of the inner cylinder in telescoping engagement. A force exerted on the closed end of the outer cylinder urges the bottom of a can in the inner cylinder into engagement with the piercing device in the bottom of the inner cylinder to form an opening in the can bottom, thereby permitting the contents of the can to enter the disposal container.

  20. Aerosol can waste disposal device

    DOE Patents [OSTI]

    O'Brien, M.D.; Klapperick, R.L.; Bell, C.

    1993-12-21

    Disclosed is a device for removing gases and liquid from containers. The device punctures the bottom of a container for purposes of exhausting gases and liquid from the container without their escaping into the atmosphere. The device includes an inner cup or cylinder having a top portion with an open end for receiving a container and a bottom portion which may be fastened to a disposal or waste container in a substantially leak-proof manner. A piercing device is mounted in the lower portion of the inner cylinder for puncturing the can bottom placed in the inner cylinder. An outer cylinder having an open end and a closed end fits over the top portion of the inner cylinder in telescoping engagement. A force exerted on the closed end of the outer cylinder urges the bottom of a can in the inner cylinder into engagement with the piercing device in the bottom of the inner cylinder to form an opening in the can bottom, thereby permitting the contents of the can to enter the disposal container. 7 figures.

  1. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Report March 2016 Canonsburg, Pennsylvania Page 3-1 3.0 Canonsburg, Pennsylvania, Disposal Site 3.1 Compliance Summary The Canonsburg, Pennsylvania, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on October 27, 2015. The site was in excellent condition. No evidence of erosion or slope instability was observed on the disposal cell. A trespass campsite was discovered hidden among the trees in the southwest corner of the property, outside the perimeter

  2. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Lakeview, Oregon Page 9-1 9.0 Lakeview, Oregon, Disposal Site 9.1 Compliance Summary The Lakeview, Oregon, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected September 16 and 17, 2015. Other than some ongoing concern with erosion-control rock riprap degradation, the disposal cell was in good condition. Some minor fence repairs and vegetation removal, and minor erosion repair work along the west site fence is planned. Inspectors identified no other

  3. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Rifle, Colorado Page 14-1 14.0 Rifle, Colorado, Disposal Site 14.1 Compliance Summary The Rifle, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on June 30, 2015. The disposal cell and all associated surface-water diversion and drainage structures were in good condition and functioning as designed. Vegetation on the site was in excellent condition. Minor fence repairs and perimeter sign maintenance will be conducted prior to the next inspection.

  4. cover

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

    counterproliferation NNSA announces retirement of Dr. Steve Aoki, after 33 years of service NNSA Administrator Frank Klotz, Dr. Steve Aoki, and Secretary of Energy Ernest Moniz. Colleagues: It is with mixed emotions that we announce the retirement of Dr. Steve Aoki, Associate Administrator for Counterterrorism and Counterproliferation. Steve officially retired on December 31st after 33... NNSA Releases New Nuclear Prevent, Counter, and Respond Report Comprehensive Overview of NNSA's

  5. Cover

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

    3 Financial Statement Audit OAS-FS-15-02 November 2014 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 November 19, 2014 MEMORANDUM FOR THE ADMINISTRATOR, WESTERN AREA POWER ADMINISTRATION FROM: Daniel M. Weeber Assistant Inspector General for Audits and Administration Office of Inspector General SUBJECT: INFORMATION: Audit Report on "Western Federal Power System's Fiscal Year 2013 Financial Statement

  6. Cover

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

    Year 2015 Financial Statement Audit OAI-FS-16-07 April 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 April 6, 2016 MEMORANDUM FOR THE ADMINISTRATOR, WESTERN AREA POWER ADMINISTRATION FROM: Sarah B. Nelson Assistant Inspector General for Audits and Administration SUBJECT: INFORMATION: Audit Report on "Western Federal Power System's Fiscal Year 2015 Financial Statement Audit" The attached report

  7. Cover

    Energy Savers [EERE]

    Uranium Enrichment Decontamination and Decommissioning Fund's Fiscal Year 2011 Financial Statement Audit OAS-FS-13-01 October 2012 UNITED STATES DEPARTMENT OF ENERGY OFFICE OF ENVIRONMENTAL MANAGEMENT URANIUM ENRICHMENT DECONTAMINATION AND DECOMMISSIONING FUND Financial Statements September 30, 2011 and 2010 (With Independent Auditors' Reports Thereon) UNITED STATES DEPARTMENT OF ENERGY OFFICE OF ENVIRONMENTAL MANAGEMENT URANIUM ENRICHMENT DECONTAMINATION AND DECOMMISSIONING FUND Table of

  8. COVER

    Office of Environmental Management (EM)

    Department of Energy On December 10, 2014, DOE General Counsel Steven P. Croley signed a Notice of Proposed Rulemaking (NOPR), which sets forth proposed regulations to establish the retrospective risk pooling program called for under section 934 of EISA. PDF icon CSC NOPR More Documents & Publications Convention on Supplementary Compensation Rulemaking NEI Request for Extension of Public Comment Period DOE-HQ-201.... NOPR NEI Department of Energy

    After a regulatory action has been

  9. Disposal of tritium-exposed metal hydrides

    SciTech Connect (OSTI)

    Nobile, A.; Motyka, T.

    1991-01-01

    A plan has been established for disposal of tritium-exposed metal hydrides used in Savannah River Site (SRS) tritium production or Materials Test Facility (MTF) R D operations. The recommended plan assumes that the first tritium-exposed metal hydrides will be disposed of after startup of the Solid Waste Disposal Facility (SWDF) Expansion Project in 1992, and thus the plan is consistent with the new disposal requiremkents that will be in effect for the SWDF Expansion Project. Process beds containing tritium-exposed metal hydride powder will be disposed of without removal of the powder from the bed; however, disposal of tritium-exposed metal hydride powder that has been removed from its process vessel is also addressed.

  10. Disposal of tritium-exposed metal hydrides

    SciTech Connect (OSTI)

    Nobile, A.; Motyka, T.

    1991-12-31

    A plan has been established for disposal of tritium-exposed metal hydrides used in Savannah River Site (SRS) tritium production or Materials Test Facility (MTF) R&D operations. The recommended plan assumes that the first tritium-exposed metal hydrides will be disposed of after startup of the Solid Waste Disposal Facility (SWDF) Expansion Project in 1992, and thus the plan is consistent with the new disposal requiremkents that will be in effect for the SWDF Expansion Project. Process beds containing tritium-exposed metal hydride powder will be disposed of without removal of the powder from the bed; however, disposal of tritium-exposed metal hydride powder that has been removed from its process vessel is also addressed.

  11. Low-level Waste Safely Dispositioned Under Runoff Cover at SRS

    Broader source: Energy.gov [DOE]

    AIKEN, S.C. – A $3.5-million American Recovery and Reinvestment Act project at the Savannah River Site (SRS) has placed an operational stormwater runoff cover over the 625,000-square-foot area comprising E-Area Low-Level Waste (LLW) Facility Slit Trench Disposal Units 1-4.

  12. Edgemont, South Dakota, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Edgemont, South Dakota, Disposal Site This fact sheet provides information about the Edgemont, South Dakota, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under Title II of the Uranium Mill Tailings Radiation Control Act of 1978. Location of the Edgemont, South Dakota, Disposal Site Site Description and History The former Edgemont uranium mill is located in Edgemont, South Dakota, in Fall River County near the southwest corner of South Dakota.

  13. Cover Stories | Argonne National Laboratory

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

    In Situ Characterization of Li-ion Battery Electrochemistry via Scanning Ion Conductance Microscopy," Adv. Mater., 23, 5613-5617 (2011). Click to view cover V. G. Pol and...

  14. Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2009-07-31

    Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was implemented. (6) At CAS 09-23-01, Area 9 Gravel Gertie, a UR was implemented. (7) At CAS 09-34-01, Underground Detection Station, no work was performed.

  15. DOE Applauds Opening of Historic Disposal Facility

    Broader source: Energy.gov [DOE]

    ANDREWS, Texas – DOE officials participated in an event today to celebrate the opening of the first commercial disposal facility of its kind.

  16. Green River, Utah, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Green River, Utah, Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site near Green River, Utah. This site is managed by the U.S. Department of Energy Office of Legacy Management. Location of the Green River, Utah, Disposal Site Site Description and History The Green River disposal site is about 0.5 mile east of the Green River and 1.5 miles southeast of the city of Green River, Utah. The site consists of an

  17. WPCF Underground Injection Control Disposal Permit Evaluation...

    Open Energy Info (EERE)

    WPCF Underground Injection Control Disposal Permit Evaluation and Fact Sheet Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: WPCF Underground Injection...

  18. Disposal Systems Evaluations and Tool Development - Engineered...

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

    Rock Status of UFD Campaign International Activities in Disposal Research Evaluation of Generic EBS Design Concepts and Process Models Implications to EBS Design Optimization

  19. Evaluation of soil manipulation to prepare engineered earthen waste covers for revegetation

    SciTech Connect (OSTI)

    Waugh, W. Joseph; Benson, Craig H.; Albright, William H.; Smith, Gregory M.; Bush, Richard P.

    2015-10-21

    Seven ripping treatments designed to improve soil physical conditions for revegetation were compared on a test pad simulating an earthen cover for a waste disposal cell. The field test was part of study of methods to convert compacted-soil waste covers into evapotranspiration covers. The test pad consisted of a compacted layer of fine-textured soil simulating a barrier protection layer overlain by a gravelly sand bedding layer and a cobble armor layer. Treatments included combinations of soil-ripping implements (conventional shank [CS], wing-tipped shank [WTS], and parabolic oscillating shank with wings [POS]), ripping depths, and number of passes. Dimensions, dry density, moisture content, and particle size distribution of disturbance zones were determined in two trenches excavated across rip rows. The goal was to create a root-zone dry density between 1.2 and 1.6 Mg m-3 and a seedbed soil texture ranging from clay loam to sandy loam with low rock content. All treatments created V-shaped disturbance zones as measured on trench faces. Disturbance zone size was most influenced by ripping depth. Winged implements created larger disturbance zones. All treatments lifted fines into the bedding layer, moved gravel and cobble down into the fine-textured protection layer, and thereby disrupted the capillary barrier at the interface. Changes in dry density within disturbance zones were comparable for the CS and WTS treatments but were highly variable among POS treatments. Water content increased in the bedding layer and decreased in the protection layer after ripping. The POS at 1.2-m depth and two passes created the largest zone with a low dry density (1.24 Mg m-3) and the most favorable seedbed soil texture (gravely silt loam). Furthermore, ripping also created large soil aggregates and voids in the protection layer that may produce preferential flow paths and reduce water storage capacity.

  20. VEGETATION COVER ANALYSIS OF HAZARDOUS WASTE SITES IN UTAH AND ARIZONA USING HYPERSPECTRAL REMOTE SENSING

    SciTech Connect (OSTI)

    Serrato, M.; Jungho, I.; Jensen, J.; Jensen, R.; Gladden, J.; Waugh, J.

    2012-01-17

    Remote sensing technology can provide a cost-effective tool for monitoring hazardous waste sites. This study investigated the usability of HyMap airborne hyperspectral remote sensing data (126 bands at 2.3 x 2.3 m spatial resolution) to characterize the vegetation at U.S. Department of Energy uranium processing sites near Monticello, Utah and Monument Valley, Arizona. Grass and shrub species were mixed on an engineered disposal cell cover at the Monticello site while shrub species were dominant in the phytoremediation plantings at the Monument Valley site. The specific objectives of this study were to: (1) estimate leaf-area-index (LAI) of the vegetation using three different methods (i.e., vegetation indices, red-edge positioning (REP), and machine learning regression trees), and (2) map the vegetation cover using machine learning decision trees based on either the scaled reflectance data or mixture tuned matched filtering (MTMF)-derived metrics and vegetation indices. Regression trees resulted in the best calibration performance of LAI estimation (R{sup 2} > 0.80). The use of REPs failed to accurately predict LAI (R{sup 2} < 0.2). The use of the MTMF-derived metrics (matched filter scores and infeasibility) and a range of vegetation indices in decision trees improved the vegetation mapping when compared to the decision tree classification using just the scaled reflectance. Results suggest that hyperspectral imagery are useful for characterizing biophysical characteristics (LAI) and vegetation cover on capped hazardous waste sites. However, it is believed that the vegetation mapping would benefit from the use of 1 higher spatial resolution hyperspectral data due to the small size of many of the vegetation patches (< 1m) found on the sites.

  1. Evaluation of soil manipulation to prepare engineered earthen waste covers for revegetation

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

    Waugh, W. Joseph; Benson, Craig H.; Albright, William H.; Smith, Gregory M.; Bush, Richard P.

    2015-10-21

    Seven ripping treatments designed to improve soil physical conditions for revegetation were compared on a test pad simulating an earthen cover for a waste disposal cell. The field test was part of study of methods to convert compacted-soil waste covers into evapotranspiration covers. The test pad consisted of a compacted layer of fine-textured soil simulating a barrier protection layer overlain by a gravelly sand bedding layer and a cobble armor layer. Treatments included combinations of soil-ripping implements (conventional shank [CS], wing-tipped shank [WTS], and parabolic oscillating shank with wings [POS]), ripping depths, and number of passes. Dimensions, dry density, moisturemore » content, and particle size distribution of disturbance zones were determined in two trenches excavated across rip rows. The goal was to create a root-zone dry density between 1.2 and 1.6 Mg m-3 and a seedbed soil texture ranging from clay loam to sandy loam with low rock content. All treatments created V-shaped disturbance zones as measured on trench faces. Disturbance zone size was most influenced by ripping depth. Winged implements created larger disturbance zones. All treatments lifted fines into the bedding layer, moved gravel and cobble down into the fine-textured protection layer, and thereby disrupted the capillary barrier at the interface. Changes in dry density within disturbance zones were comparable for the CS and WTS treatments but were highly variable among POS treatments. Water content increased in the bedding layer and decreased in the protection layer after ripping. The POS at 1.2-m depth and two passes created the largest zone with a low dry density (1.24 Mg m-3) and the most favorable seedbed soil texture (gravely silt loam). Furthermore, ripping also created large soil aggregates and voids in the protection layer that may produce preferential flow paths and reduce water storage capacity.« less

  2. Covered Product Category: Residential Electric Resistance Water...

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

    Covered Product Category: Residential Electric Resistance Water Heaters Covered Product Category: Residential Electric Resistance Water Heaters The Federal Energy Management ...

  3. Journal Cover Gallery | The Ames Laboratory

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

    Journal Cover Gallery Image Image ACS Victor SunJALA2011_cover Image Image Image Image Image Image

  4. Hanford Landfill Reaches 15 Million Tons Disposed- Waste Disposal Mark Shows Success Cleaning Up River Corridor

    Broader source: Energy.gov [DOE]

    RICHLAND, Wash. – The U.S. Department of Energy (DOE) and its contractors have disposed of 15 million tons of contaminated material at the Environmental Restoration Disposal Facility (ERDF) since the facility began operations in 1996.

  5. Application of Generic Disposal System Models | Department of Energy

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

    Application of Generic Disposal System Models Application of Generic Disposal System Models Two of the high priorities for UFDC disposal R&D are design concept development and disposal system modeling; these are directly addressed in the Generic Disposal Systems Analysis (GDSA) work. This report describes specific GDSA activities during fiscal year 2015 toward the development of the enhanced disposal system modeling and analysis capability for geologic disposal of nuclear waste. The GDSA

  6. Crystalline and Crystalline International Disposal Activities

    SciTech Connect (OSTI)

    Viswanathan, Hari S.; Chu, Shaoping; Reimus, Paul William; Makedonska, Nataliia; Hyman, Jeffrey De'Haven; Karra, Satish; Dittrich, Timothy M.

    2015-12-21

    This report presents the results of work conducted between September 2014 and July 2015 at Los Alamos National Laboratory in the crystalline disposal and crystalline international disposal work packages of the Used Fuel Disposition Campaign (UFDC) for DOE-NE’s Fuel Cycle Research and Development program.

  7. Generic Deep Geologic Disposal Safety Case

    Broader source: Energy.gov [DOE]

    The Generic Deep Geologic Disposal Safety Case presents generic information that is of use in understanding potential deep geologic disposal options (e.g., salt, shale, granite, deep borehole) in the U.S. for used nuclear fuel (UNF) from reactors and high-level radioactive waste (HLW).

  8. Microsoft Word - S08254_CellConditions

    Office of Legacy Management (LM)

    Shiprock, New Mexico, Disposal Cell Internal Water Balance and Cell Conditions February 2012 LMS/SHP/S08254 This page intentionally left blank LMS/SHP/S08254 Shiprock, New Mexico, Disposal Cell Internal Water Balance and Cell Conditions February 2012 This page intentionally left blank U.S. Department of Energy Shiprock Disposal Cell Internal Water Balance and Cell Conditions February 2012 Doc. No.S08254 Page i Contents Abbreviations

  9. New Groundwater Treatment Facility Begins Operation: Boost in Cleanup

    Office of Environmental Management (EM)

    Energy Services » New Facility Will Test Disposal Cell Cover Renovation New Facility Will Test Disposal Cell Cover Renovation New Facility Will Test Disposal Cell Cover Renovation PDF icon New Facility Will Test Disposal Cell Cover Renovation More Documents & Publications Design and Installation of a Disposal Cell Cover Field Test Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance Long-Term Surveillance Operations and Maintenance

  10. COVERING A CORE BY EXTRUSION

    DOE Patents [OSTI]

    Karnie, A.J.

    1963-07-16

    A method of covering a cylindrical fuel core with a cladding metal ms described. The metal is forced between dies around the core from both ends in two opposing skirts, and as these meet the ends turn outward into an annular recess in the dics. By cutting off the raised portion formed by the recess, oxide impurities are eliminated. (AEC)

  11. Large Component Removal/Disposal

    SciTech Connect (OSTI)

    Wheeler, D. M.

    2002-02-27

    This paper describes the removal and disposal of the large components from Maine Yankee Atomic Power Plant. The large components discussed include the three steam generators, pressurizer, and reactor pressure vessel. Two separate Exemption Requests, which included radiological characterizations, shielding evaluations, structural evaluations and transportation plans, were prepared and issued to the DOT for approval to ship these components; the first was for the three steam generators and one pressurizer, the second was for the reactor pressure vessel. Both Exemption Requests were submitted to the DOT in November 1999. The DOT approved the Exemption Requests in May and July of 2000, respectively. The steam generators and pressurizer have been removed from Maine Yankee and shipped to the processing facility. They were removed from Maine Yankee's Containment Building, loaded onto specially designed skid assemblies, transported onto two separate barges, tied down to the barges, th en shipped 2750 miles to Memphis, Tennessee for processing. The Reactor Pressure Vessel Removal Project is currently under way and scheduled to be completed by Fall of 2002. The planning, preparation and removal of these large components has required extensive efforts in planning and implementation on the part of all parties involved.

  12. Summary - Idaho CERCLA Disposal Facility (ICDF) at Idaho National...

    Office of Environmental Management (EM)

    Idaho CERCLA Disposal Facility (ICDF) is a land disposal facility that is used to dispose ... Re-evaluate the Landfill CompactionSubsidence Study to consider the impacts of ...

  13. FACT SHEET: The Path Forward on Nuclear Waste Disposal | Department...

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

    FACT SHEET: The Path Forward on Nuclear Waste Disposal FACT SHEET: The Path Forward on Nuclear Waste Disposal FACT SHEET: The Path Forward on Nuclear Waste Disposal More Documents...

  14. Long-term surveillance plan for the Maybell, Colorado Disposal Site

    SciTech Connect (OSTI)

    1997-12-01

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  15. Long-term surveillance plan for the Maybell, Colorado Disposal Site

    SciTech Connect (OSTI)

    1997-09-01

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  16. DOE - Office of Legacy Management -- Commercial (Burial) Disposal Site

    Office of Legacy Management (LM)

    Maxey Flats Disposal Site - KY 02 Commercial (Burial) Disposal Site Maxey Flats Disposal Site - KY 02 FUSRAP Considered Sites Site: Commercial (Burial) Disposal Site, Maxey Flats Disposal Site (KY.02) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Maxey Flats, Kentucky, Site Documents Related to Commercial (Burial) Disposal Site,

  17. Microsoft Word - cover_Al2000series.doc

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

    with financial support from the Safety, Codes and Standards program element of the Hydrogen, Fuel Cells and Infrastructure program, Office of Energy Efficiency and Renewable...

  18. Method and apparatus for extracting tritium and preparing radioactive waste for disposal

    DOE Patents [OSTI]

    Heung, L.K.

    1994-03-29

    Apparatus is described for heating an object such as a nuclear target bundle to release and recover hydrogen and contain the disposable residue for disposal. The apparatus comprises an inverted furnace, a sleeve/crucible assembly for holding and enclosing the bundle, conveying equipment for placing the sleeve onto the crucible and loading the bundle into the sleeve/crucible, a lift for raising the enclosed bundle into the furnace, and hydrogen recovery equipment including a trap and strippers, all housed in a containment having negative internal pressure. The crucible/sleeve assembly has an internal volume that is sufficient to enclose and hold the bundle before heating; the crucible's internal volume is sufficient by itself to hold and enclose the bundle's volume after heating. The crucible can then be covered and disposed of; the sleeve, on the other hand, can be reused. 4 figures.

  19. Method and apparatus for extracting tritium and preparing radioactive waste for disposal

    DOE Patents [OSTI]

    Heung, Leung K.

    1994-01-01

    Apparatus for heating an object such as a nuclear target bundle to release and recover hydrogen and contain the disposable residue for disposal. The apparatus comprises an inverted furnace, a sleeve/crucible assembly for holding and enclosing the bundle, conveying equipment for placing the sleeve onto the crucible and loading the bundle into the sleeve/crucible, a lift for raising the enclosed bundle into the furnace, and hydrogen recovery equipment including a trap and strippers, all housed in a containment having negative internal pressure. The crucible/sleeve assembly has an internal volume that is sufficient to enclose and hold the bundle before heating; the crucible's internal volume is sufficient by itself to hold and enclose the bundle's volume after heating. The crucible can then be covered and disposed of; the sleeve, on the other hand, can be reused.

  20. Corrugated cover plate for flat plate collector

    DOE Patents [OSTI]

    Hollands, K. G. Terry; Sibbitt, Bruce

    1978-01-01

    A flat plate radiant energy collector is providing having a transparent cover. The cover has a V-corrugated shape which reduces the amount of energy reflected by the cover away from the flat plate absorber of the collector.

  1. Deep Borehole Disposal of Spent Fuel. (Conference) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Deep Borehole Disposal of Spent Fuel. Citation Details In-Document Search Title: Deep Borehole Disposal of Spent Fuel. Abstract not provided. Authors: Brady, Patrick V. Publication...

  2. Deep Borehole Disposal of Nuclear Waste. (Conference) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Deep Borehole Disposal of Nuclear Waste. Citation Details In-Document Search Title: Deep Borehole Disposal of Nuclear Waste. Abstract not provided. Authors: Arnold, Bill Walter ;...

  3. Used Fuel Disposition Campaign Disposal Research and Development...

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

    Disposal Research and Development Roadmap Rev. 01 Used Fuel Disposition Campaign Disposal Research and Development Roadmap Rev. 01 The U.S. Department of Energy Office of Nuclear...

  4. Repository Reference Disposal Concepts and Thermal Load Management...

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

    This report summarizes the work on both enclosed and open mode disposal concepts, thermal analysis of open modes, a range of spent nuclear fuel (SNF) burnup, additional disposal ...

  5. Disposal Practices at the Savannah River Site | Department of...

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

    Practices at the Savannah River Site Disposal Practices at the Savannah River Site Full Document and Summary Versions are available for download PDF icon Disposal Practices at the ...

  6. Deep Borehole Disposal Research: Geological Data Evaluation Alternativ...

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

    Deep Borehole Disposal Research: Geological Data Evaluation Alternative Waste Forms and Borehole Seals Citation Details In-Document Search Title: Deep Borehole Disposal Research:...

  7. Innovative Technique Accelerates Waste Disposal at Idaho Site

    Broader source: Energy.gov [DOE]

    IDAHO FALLS, Idaho – An innovative treatment and disposal technique is enabling the Idaho site to accelerate shipments of legacy nuclear waste for permanent disposal.

  8. Erosion Control and Revegetation at DOE's Lowman Disposal Site...

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

    Erosion Control and Revegetation at DOE's Lowman Disposal Site, Lowman, Idaho Erosion Control and Revegetation at DOE's Lowman Disposal Site, Lowman, Idaho Erosion Control and ...

  9. A Critical Step Toward Sustainable Nuclear Fuel Disposal | Department...

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

    A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal January 26, 2012 - 2:30pm Addthis Secretary Chu Secretary Chu...

  10. Nevada Industrial Solid Waste Disposal Site Permit Application...

    Open Energy Info (EERE)

    Nevada Industrial Solid Waste Disposal Site Permit Application Jump to: navigation, search OpenEI Reference LibraryAdd to library Form: Nevada Industrial Solid Waste Disposal Site...

  11. Title 40 CFR 268 Land Disposal Restrictions | Open Energy Information

    Open Energy Info (EERE)

    disposal and defines those limited circumstances under which an otherwise prohibited waste may continue to be land disposed. Except as specifically provided otherwise in this...

  12. Generic disposal concepts and thermal load management for larger...

    Office of Scientific and Technical Information (OSTI)

    Generic disposal concepts and thermal load management for larger waste packages. Citation Details In-Document Search Title: Generic disposal concepts and thermal load management...

  13. NDAA Section 3116 Waste Determinations with Related Disposal...

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

    NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments Section ...

  14. Design, Performance, and Sustainability of Engineered Covers...

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

    Design, Performance, and Sustainability of Engineered Covers for Uranium Mill Tailings Design, Performance, and Sustainability of Engineered Covers for Uranium Mill Tailings ...

  15. Household Vehicles Energy Use Cover Page

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

    Energy Use Cover Page Glossary Home > Households, Buildings & Industry >Transportation Surveys > Household Vehicles Energy Use Cover Page Contact Us * Feedback * PrivacySecurity *...

  16. Deep Borehole Disposal Research: Demonstration Site Selection...

    Office of Environmental Management (EM)

    The deep borehole disposal concept consists of drilling a borehole on the order of 5,000 m deep, emplacing waste canisters in the lower part of the borehole, and sealing the upper ...

  17. Operational Issues at the Environmental Restoration Disposal...

    Office of Environmental Management (EM)

    Hanford Operations Evaluating Operational Issues at the Environmental Restoration Disposal Facility at Hanford By Craig H. Benson, PhD, PE; William H. Albright, PhD; and David P. ...

  18. Method of Disposing of Corrosive Gases

    DOE Patents [OSTI]

    Burford, W.B. III; Anderson, H.C.

    1950-07-11

    Waste gas containing elemental fluorine is disposed of in the disclosed method by introducing the gas near the top of a vertical chamber under a downward spray of caustic soda solution which contains a small amount of sodium sulfide.

  19. Assessment of Preferred Depleted Uranium Disposal Forms

    SciTech Connect (OSTI)

    Croff, A.G.; Hightower, J.R.; Lee, D.W.; Michaels, G.E.; Ranek, N.L.; Trabalka, J.R.

    2000-06-01

    The Department of Energy (DOE) is in the process of converting about 700,000 metric tons (MT) of depleted uranium hexafluoride (DUF6) containing 475,000 MT of depleted uranium (DU) to a stable form more suitable for long-term storage or disposal. Potential conversion forms include the tetrafluoride (DUF4), oxide (DUO2 or DU3O8), or metal. If worthwhile beneficial uses cannot be found for the DU product form, it will be sent to an appropriate site for disposal. The DU products are considered to be low-level waste (LLW) under both DOE orders and Nuclear Regulatory Commission (NRC) regulations. The objective of this study was to assess the acceptability of the potential DU conversion products at potential LLW disposal sites to provide a basis for DOE decisions on the preferred DU product form and a path forward that will ensure reliable and efficient disposal.

  20. Special Analysis: Naval Reactor Waste Disposal Pad

    SciTech Connect (OSTI)

    Cook, J.R.

    2003-03-31

    This report presents the results of a special study of the Naval Reactor Waste Disposal Pad located within the boundary of the E-Area Low-Level Waste Facility at the Savannah River Site.

  1. Supplement Analysis for Disposal of Polychlorinated Biphenyl...

    Office of Environmental Management (EM)

    Disposal of Polychlorinated Biphenyl-Commingled Transuranic Waste at the Waste Isolation Pilot Plant (DOEEIS-0026-SA02) 1.0 Purpose and Need for Action Transuranic (TRU) waste is...

  2. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Salt Lake City, Utah Page 15-1 15.0 Salt Lake City, Utah, Disposal Site 15.1 Compliance Summary The Salt Lake City, Utah, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on June 22, 2015. The disposal cell was in good condition. Observations of rock quality monitoring plots indicated no obvious change from the previous year. Inspectors did note vegetation buildup along the access road that surrounds the cell. No waste debris or indication of windblown or

  3. Microsoft Word - DisposalInSaltDifferentThanDisposalInWIPP.doc

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

    that have atomic numbers greater than uranium. An article in the August 2009 issue of Scientific American contained discussion about the use of salt formations for disposal of...

  4. Liquid cooled, linear focus solar cell receiver

    DOE Patents [OSTI]

    Kirpich, A.S.

    1983-12-08

    Separate structures for electrical insulation and thermal conduction are established within a liquid cooled, linear focus solar cell receiver for use with parabolic or Fresnel optical concentrators. The receiver includes a V-shaped aluminum extrusion having a pair of outer faces each formed with a channel receiving a string of solar cells in thermal contact with the extrusion. Each cell string is attached to a continuous glass cover secured within the channel with spring clips to isolate the string from the external environment. Repair or replacement of solar cells is effected simply by detaching the spring clips to remove the cover/cell assembly without interrupting circulation of coolant fluid through the receiver. The lower surface of the channel in thermal contact with the cells of the string is anodized to establish a suitable standoff voltage capability between the cells and the extrusion. Primary electrical insulation is provided by a dielectric tape disposed between the coolant tube and extrusion. Adjacent solar cells are soldered to interconnect members designed to accommodate thermal expansion and mismatches. The coolant tube is clamped into the extrusion channel with a releasably attachable clamping strip to facilitate easy removal of the receiver from the coolant circuit.

  5. Liquid cooled, linear focus solar cell receiver

    DOE Patents [OSTI]

    Kirpich, Aaron S.

    1985-01-01

    Separate structures for electrical insulation and thermal conduction are established within a liquid cooled, linear focus solar cell receiver for use with parabolic or Fresnel optical concentrators. The receiver includes a V-shaped aluminum extrusion having a pair of outer faces each formed with a channel receiving a string of solar cells in thermal contact with the extrusion. Each cell string is attached to a continuous glass cover secured within the channel with spring clips to isolate the string from the external environment. Repair or replacement of solar cells is effected simply by detaching the spring clips to remove the cover/cell assembly without interrupting circulation of coolant fluid through the receiver. The lower surface of the channel in thermal contact with the cells of the string is anodized to establish a suitable standoff voltage capability between the cells and the extrusion. Primary electrical insulation is provided by a dielectric tape disposed between the coolant tube and extrusion. Adjacent solar cells are soldered to interconnect members designed to accommodate thermal expansion and mismatches. The coolant tube is clamped into the extrusion channel with a releasably attachable clamping strip to facilitate easy removal of the receiver from the coolant circuit.

  6. Acquisition, Use, and Disposal of Real Estate | Department of Energy

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

    Acquisition, Use, and Disposal of Real Estate Acquisition, Use, and Disposal of Real Estate More Documents & Publications Acquisition Guide Chapter 17.3, Acquisition, Use, and Disposal of Real Estate OPAM Policy Acquisition Guides Acquisition, Use, and Disposal of Real Estate

  7. Title I Disposal Sites Annual Report | Department of Energy

    Energy Savers [EERE]

    I Disposal Sites Annual Report Title I Disposal Sites Annual Report 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites (March 2015) PDF icon 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites (March 2015) More Documents & Publications Title II

  8. Title II Disposal Sites Annual Report | Department of Energy

    Energy Savers [EERE]

    II Disposal Sites Annual Report Title II Disposal Sites Annual Report 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites (November 2014) PDF icon 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites (November 2014) More Documents & Publications Title I

  9. Acquisition, Use, and Disposal of Real Estate | Department of Energy

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

    Acquisition, Use, and Disposal of Real Estate Acquisition, Use, and Disposal of Real Estate PDF icon Acquisition, Use, and Disposal of Real Estate More Documents & Publications OPAM Policy Acquisition Guides Chapter 17 - Special Contracting Methods Acquisition Guide Chapter 17.3, Acquisition, Use, and Disposal of Real Estate

  10. Annual Report for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011

    SciTech Connect (OSTI)

    French, Sean B.; Shuman, Rob

    2012-05-22

    As a condition to the Disposal Authorization Statement issued to Los Alamos National Laboratory (LANL or the Laboratory) on March 17, 2010, a comprehensive performance assessment and composite analysis maintenance program must be implemented for the Technical Area 54, Area G disposal facility. Annual determinations of the adequacy of the performance assessment and composite analysis are to be conducted under the maintenance program to ensure that the conclusions reached by those analyses continue to be valid. This report summarizes the results of the fiscal year 2011 annual review for Area G. Revision 4 of the Area G performance assessment and composite analysis was issued in 2008 and formally approved in 2009. These analyses are expected to provide reasonable estimates of the long-term performance of Area G and, hence, the disposal facility's ability to comply with Department of Energy (DOE) performance objectives. Annual disposal receipt reviews indicate that smaller volumes of waste will require disposal in the pits and shafts at Area G relative to what was projected for the performance assessment and composite analysis. The future inventories are projected to decrease modestly for the pits but increase substantially for the shafts due to an increase in the amount of tritium that is projected to require disposal. Overall, however, changes in the projected future inventories of waste are not expected to compromise the ability of Area G to satisfy DOE performance objectives. The Area G composite analysis addresses potential impacts from all waste disposed of at the facility, as well as other sources of radioactive material that may interact with releases from Area G. The level of knowledge about the other sources included in the composite analysis has not changed sufficiently to call into question the validity of that analysis. Ongoing environmental surveillance activities are conducted at, and in the vicinity of, Area G. However, the information generated by many of these activities cannot be used to evaluate the validity of the performance assessment and composite analysis models because the monitoring data collected are specific to operational releases or address receptors that are outside the domain of the performance assessment and composite analysis. In general, applicable monitoring data are supportive of some aspects of the performance assessment and composite analysis. Several research and development (R and D) efforts have been initiated under the performance assessment and composite analysis maintenance program. These investigations are designed to improve the current understanding of the disposal facility and site, thereby reducing the uncertainty associated with the projections of the long-term performance of Area G. The status and results of R and D activities that were undertaken in fiscal year 2011 are discussed in this report. Special analyses have been conducted to determine the feasibility of disposing of specific waste streams, to address proposed changes in disposal operations, and to consider the impacts of changes to the models used to conduct the performance assessment and composite analysis. These analyses are described and the results of the evaluations are summarized in this report. The Area G disposal facility consists of Material Disposal Area (MDA) G and the Zone 4 expansion area. To date, all disposal operations at Area G have been confined to MDA G. Material Disposal Area G is scheduled to undergo final closure in 2015; disposal of waste in the pits and shafts is scheduled to end in 2013. In anticipation of the closure of MDA G, plans are being made to ship the majority of the waste generated at LANL to off-site locations for disposal. It is not clear at this time if waste that will be disposed of at LANL will be placed in Zone 4 or if disposal operations will move to a new location at the Laboratory. Separately, efforts to optimize the final cover used in the closure of MDA G are underway; a final cover design different than that adopted for the performance assessment and composite analy

  11. Generic Disposal System Modeling, Fiscal Year 2011 Progress Report

    Broader source: Energy.gov [DOE]

    The UFD Campaign is developing generic disposal system models (GDSM) of different disposal environments and waste form options. Currently, the GDSM team is investigating four main disposal environment options: mined repositories in three geologic media (salt, clay, and granite) and the deep borehole concept in crystalline rock (DOE 2010d). Further developed the individual generic disposal system (GDS) models for salt, granite, clay, and deep borehole disposal environments.

  12. Summary - Idaho CERCLA Disposal Facility (ICDF) at Idaho National Laboratory

    Office of Environmental Management (EM)

    INL, Idaho EM Project: Idaho CERCLA Disposal Facility ETR Report Date: December 2007 ETR-10 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Idaho CERCLA Disposal Facility (ICDF) At Idaho National Laboratory (INL) Why DOE-EM Did This Review The Idaho CERCLA Disposal Facility (ICDF) is a land disposal facility that is used to dispose of LLW and MLW generated from remedial activities at the Idaho National Laboratory (INL). Components of

  13. Probabilistic Modeling of Settlement Risk at Land Disposal Facilities - 12304

    SciTech Connect (OSTI)

    Foye, Kevin C.; Soong, Te-Yang

    2012-07-01

    The long-term reliability of land disposal facility final cover systems - and therefore the overall waste containment - depends on the distortions imposed on these systems by differential settlement/subsidence. The evaluation of differential settlement is challenging because of the heterogeneity of the waste mass (caused by inconsistent compaction, void space distribution, debris-soil mix ratio, waste material stiffness, time-dependent primary compression of the fine-grained soil matrix, long-term creep settlement of the soil matrix and the debris, etc.) at most land disposal facilities. Deterministic approaches to long-term final cover settlement prediction are not able to capture the spatial variability in the waste mass and sub-grade properties which control differential settlement. An alternative, probabilistic solution is to use random fields to model the waste and sub-grade properties. The modeling effort informs the design, construction, operation, and maintenance of land disposal facilities. A probabilistic method to establish design criteria for waste placement and compaction is introduced using the model. Random fields are ideally suited to problems of differential settlement modeling of highly heterogeneous foundations, such as waste. Random fields model the seemingly random spatial distribution of a design parameter, such as compressibility. When used for design, the use of these models prompts the need for probabilistic design criteria. It also allows for a statistical approach to waste placement acceptance criteria. An example design evaluation was performed, illustrating the use of the probabilistic differential settlement simulation methodology to assemble a design guidance chart. The purpose of this design evaluation is to enable the designer to select optimal initial combinations of design slopes and quality control acceptance criteria that yield an acceptable proportion of post-settlement slopes meeting some design minimum. For this specific example, relative density, which can be determined through field measurements, was selected as the field quality control parameter for waste placement. This technique can be extended to include a rigorous performance-based methodology using other parameters (void space criteria, debris-soil mix ratio, pre-loading, etc.). As shown in this example, each parameter range, or sets of parameter ranges can be selected such that they can result in an acceptable, long-term differential settlement according to the probabilistic model. The methodology can also be used to re-evaluate the long-term differential settlement behavior at closed land disposal facilities to identify, if any, problematic facilities so that remedial action (e.g., reinforcement of upper and intermediate waste layers) can be implemented. Considering the inherent spatial variability in waste and earth materials and the need for engineers to apply sound quantitative practices to engineering analysis, it is important to apply the available probabilistic techniques to problems of differential settlement. One such method to implement probability-based differential settlement analyses for the design of landfill final covers has been presented. The design evaluation technique presented is one tool to bridge the gap from deterministic practice to probabilistic practice. (authors)

  14. The Salt Defense Disposal Investigations (SDDI)

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

    Salt Defense Disposal Investigations (SDDI) will utilize a newly mined Underground Research Lab (URL) in WIPP to perform a cost effective, proof-of-principle feld test of the emplacement of heat-generating radioactive waste and validate modeling efforts. The goals of the SDDI Thermal Test are to: * Demonstrate a proof-of-principle concept for in-drift disposal in salt. * Investigate, in a specifc emplacement concept, the response of the salt to heat. * Develop a full-scale response for run-of-

  15. Disposal of bead ion exchange resin wastes

    SciTech Connect (OSTI)

    Gay, R.L.; Granthan, L.F.

    1985-12-17

    Bead ion exchange resin wastes are disposed of by a process which involves spray-drying a bead ion exchange resin waste in order to remove substantially all of the water present in such waste, including the water on the surface of the ion exchange resin beads and the water inside the ion exchange resin beads. The resulting dried ion exchange resin beads can then be solidified in a suitable solid matrix-forming material, such as a polymer, which solidifies to contain the dried ion exchange resin beads in a solid monolith suitable for disposal by burial or other conventional means.

  16. Application for Permit to Operate a Class II Solid Waste Disposal Site at the Nevada Test Site - U10c Disposal Site

    SciTech Connect (OSTI)

    NSTec Environmental Programs

    2010-03-31

    The Nevada Test Site (NTS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NTS and National Security Technologies LLC (NSTec) is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The site will be used for the disposal of refuse, rubbish, garbage, sewage sludge, pathological waste, Asbestos-Containing Material (ACM), industrial solid waste, hydrocarbon-burdened soil, hydrocarbon-burdened demolition and construction waste, and other inert waste (hereafter called permissible waste). Waste containing free liquids or regulated under Subtitle C of the Resource Conservation and Recovery Act (RCRA) will not be accepted for disposal at the site. Waste regulated under the Toxic Substance Control Act (TSCA), excluding Polychlorinated Biphenyl [PCB], Bulk Product Waste (see Section 6.2.5) and ACM (see Section 6.2.2.2) will not be accepted for disposal at the site. The disposal site will be used as the sole depository of permissible waste which is: (1) Generated by entities covered under the U.S. Environmental Protection Agency (EPA) Hazardous Waste Generator Identification Number for the NTS; (2) Generated at sites identified in the Federal Facilities Agreement and Consent Order (FFACO); (3) Sensitive records and media, including documents, vugraphs, computer disks, typewriter ribbons, magnetic tapes, etc., generated by NNSA/NSO or its contractors; (4) ACM generated by NNSA/NSO or its contractors according to Section 6.2.2.2, as necessary; (5) Hydrocarbon-burdened soil and solid waste from areas covered under the EPA Hazardous Waste Generator Identification Number for the NTS; (6) Other waste on a case-by-case concurrence by NDEP/BFF. The generator of permissible waste is responsible for preparing documentation related to waste acceptance criteria, waste characterization, and load verification. Waste and Water (WW) personnel are responsible for operating the disposal site and reviewing documentation to determine if the waste is acceptable.

  17. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Green River, Utah Page 7-1 7.0 Green River, Utah, Disposal Site 7.1 Compliance Summary The Green River, Utah, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on March 18, 2015. The disposal cell was in excellent condition. One missing perimeter sign was replaced during the inspection. Inspectors identified no other maintenance needs or cause for a follow-up or contingency inspection. 7.2 Compliance Requirements Requirements for the long-term surveillance

  18. cover_booked.indd | Department of Energy

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

    cover_booked.indd cover_booked.indd PDF icon cover_booked.indd More Documents & Publications Three Year Rolling Timeline Order Module--DOE O 430.1B, REAL PROPERTY ASSET MANAGEMENT The Department of Energy Asset Management Plan (2015)

  19. Low level tank waste disposal study

    SciTech Connect (OSTI)

    Mullally, J.A.

    1994-09-29

    Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site.

  20. Solving the problems of infectious waste disposal

    SciTech Connect (OSTI)

    Hoffman, S.L.; Cabral, N.J. )

    1989-06-01

    Lawmakers are increasing pressures to ensure safe, appropriate disposal of infectious waste. This article discusses the problems, the regulatory climate, innovative approaches, and how to pay for them. The paper discusses the regulatory definition of infectious waste, federal and state regulations, and project finance.

  1. Land Disposal Restrictions (LDR) program overview

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    The Hazardous and Solid Waste Amendments (HSWA) to the Resource Conservation and Recovery Act (RCRA) enacted in 1984 required the Environmental Protection Agency (EPA) to evaluate all listed and characteristic hazardous wastes according to a strict schedule and to develop requirements by which disposal of these wastes would be protective of human health and the environment. The implementing regulations for accomplishing this statutory requirement are established within the Land Disposal Restrictions (LDR) program. The LDR regulations (40 CFR Part 268) impose significant requirements on waste management operations and environmental restoration activities at DOE sites. For hazardous wastes restricted by statute from land disposal, EPA is required to set levels or methods of treatment that substantially reduce the waste`s toxicity or the likelihood that the waste`s hazardous constituents will migrate. Upon the specified LDR effective dates, restricted wastes that do not meet treatment standards are prohibited from land disposal unless they qualify for certain variances or exemptions. This document provides an overview of the LDR Program.

  2. Process for the disposal of alkali metals

    DOE Patents [OSTI]

    Lewis, Leroy C.

    1977-01-01

    Large quantities of alkali metals may be safely reacted for ultimate disposal by contact with a hot concentrated caustic solution. The alkali metals react with water in the caustic solution in a controlled reaction while steam dilutes the hydrogen formed by the reaction to a safe level.

  3. Treatment and Disposal of Unanticipated 'Scavenger' Wastewater

    SciTech Connect (OSTI)

    Payne, W.L.

    2003-09-15

    The Savannah River Site often generates wastewater for disposal that is not included as a source to one of the site's wastewater treatment facilities that are permitted by the South Carolina Department of Health and Environmental Control. The techniques used by the SRS contract operator (Westinghouse Savannah River Company) to evaluate and treat this unanticipated 'scavenger' wastewater may benefit industries and municipalities who experience similar needs. Regulations require that scavenger wastewater be treated and not just diluted. Each of the pollutants that are present must meet effluent permit limitations and/or receiving stream water quality standards. if a scavenger wastewater is classified as 'hazardous' under the Resource Conservation and Recovery Act (RCRA) its disposal must comply with RCRA regulations. Westinghouse Savannah River Company obtained approval from SCDHEC to dispose of scavenger wastewater under specific conditions that are included within the SRS National Pollutant Discharge Elimination System permit. Scavenger wastewater is analyzed in a laboratory to determine its constituency. Pollutant values are entered into spreadsheets that calculate treatment plant removal capabilities and instream concentrations. Disposal rates are computed, ensuring compliance with regulatory requirements and protection of treatment system operating units. Appropriate records are maintained in the event of an audit.

  4. Duluth co-disposal: Lessons learned

    SciTech Connect (OSTI)

    Law, I.J. )

    1988-10-01

    The Western Lake Superior Sanitary District (WLSSD) was formed to combat water pollution, not handle waste disposal. In 1971, the newly formed district hired an engineering firm to design a wastewater treatment facility, which resulted in the design of a 44 million gallon per day treatment plant in Duluth, home of about 70% of the districts residents. Sewage sludge from the wastewater process would be dried and burned in multiple hearth incinerators fired with No. 2 fuel oil. Design work was well underway when the 1973 oil embargo occurred, causing oil prices to quadruple, and oil or natural gas fuel to become non-existant for this type of usage. The engineers considered such fuels as coal, wood chips, and solid waste, and recommended solid waste in the form of refuse-derived fuel (RDF). The district obtained legislative authority in 1974 to control the solid waste stream in the area. All of this delayed design and construction of the sludge disposal portion of the project, but the rest of the treatment plant remained on schedule and was completed in 1978. The co-disposal portion was designed in 1975 and construction was essentially completed by November 1979. The total co-disposal project cost was about $20 million. This paper discusses special features of this system, operating problems, initial modifications, explosion hazards, and later modifications.

  5. Long-term surveillance plan for the Tuba City, Arizona disposal site

    SciTech Connect (OSTI)

    1996-02-01

    This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site at Tuba City, Arizona, describes the site surveillance activities. The U.S. Department of Energy (DOE) will carry out these activities to ensure the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM) (10 CFR {section}40.27).

  6. Summary - Operational Issues at the Environmental Restoration Disposal Facility (ERDF) at Hanford

    Office of Environmental Management (EM)

    ERDF ETR Report Date: June 2007 ETR-6 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Operational Issues at the Environmental Restoration Disposal Facility(ERDF) at Hanford Why DOE-EM Did This Review The ERDF is a large- scale disposal facility authorized to receive waste from Hanford cleanup activities. It contains double-lined cells with a RCRA Subtitle C- type liner and leachate collection system. By 2007, 6.8 million tons of

  7. Wheelspace windage cover plate for turbine

    DOE Patents [OSTI]

    Lathrop, Norman Douglas (Ballston Lake, NY)

    2002-01-01

    Windage cover plates are secured between the wheels and spacer of a turbine rotor to prevent hot flow path gas ingestion into the wheelspace cavities. Each cover plate includes a linear, axially extending body curved circumferentially with a radially outwardly directed wall at one axial end. The wall defines a axially opening recess for receiving a dovetail lug. The cover plate includes an axially extending tongue received in a circumferential groove of the spacer. The cover plate is secured with the tongue in the groove and dovetail lug in the recess. Lap joints between circumferentially adjacent cover plates are provided.

  8. A data base for low-level radioactive waste disposal sites

    SciTech Connect (OSTI)

    Daum, M.L.; Moskowitz, P.D.

    1989-07-01

    A computerized database was developed to assist the US Environmental Protection Agency (EPA) in evaluating methods and data for characterizing health hazards associated with land and ocean disposal options for low-level radioactive wastes. The data cover 1984 to 1987. The types of sites considered include Nuclear Regulatory Commission (NRC) licensed commercial disposal sites, EPA National Priority List (NPL) sites, US Department of Energy (DOE) Formerly Utilized Sites Remedial Action Project (FUSRAP) and DOE Surplus Facilities Management Program (SFMP) sites, inactive US ocean disposal sites, and DOE/Department of Defense facilities. Sources of information include reports from EPA, the US Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC), as well as direct communication with individuals associated with specific programs. The data include site descriptions, waste volumes and activity levels, and physical and radiological characterization of low-level wastes. Additional information on mixed waste, packaging forms, and disposal methods were compiled, but are not yet included in the database. 55 refs., 4 figs., 2 tabs.

  9. Conceptual waste packaging options for deep borehole disposal

    SciTech Connect (OSTI)

    Su, Jiann -Cherng; Hardin, Ernest L.

    2015-07-01

    This report presents four concepts for packaging of radioactive waste for disposal in deep boreholes. Two of these are reference-size packages (11 inch outer diameter) and two are smaller (5 inch) for disposal of Cs/Sr capsules. All four have an assumed length of approximately 18.5 feet, which allows the internal length of the waste volume to be 16.4 feet. However, package length and volume can be scaled by changing the length of the middle, tubular section. The materials proposed for use are low-alloy steels, commonly used in the oil-and-gas industry. Threaded connections between packages, and internal threads used to seal the waste cavity, are common oilfield types. Two types of fill ports are proposed: flask-type and internal-flush. All four package design concepts would withstand hydrostatic pressure of 9,600 psi, with factor safety 2.0. The combined loading condition includes axial tension and compression from the weight of a string or stack of packages in the disposal borehole, either during lower and emplacement of a string, or after stacking of multiple packages emplaced singly. Combined loading also includes bending that may occur during emplacement, particularly for a string of packages threaded together. Flask-type packages would be fabricated and heat-treated, if necessary, before loading waste. The fill port would be narrower than the waste cavity inner diameter, so the flask type is suitable for directly loading bulk granular waste, or loading slim waste canisters (e.g., containing Cs/Sr capsules) that fit through the port. The fill port would be sealed with a tapered, threaded plug, with a welded cover plate (welded after loading). Threaded connections between packages and between packages and a drill string, would be standard drill pipe threads. The internal flush packaging concepts would use semi-flush oilfield tubing, which is internally flush but has a slight external upset at the joints. This type of tubing can be obtained with premium, low-profile threaded connections at each end. The internal-flush design would be suitable for loading waste that arrives from the originating site in weld-sealed, cylindrical canisters. Internal, tapered plugs with sealing filet welds would seal the tubing at each end. The taper would be precisely machined onto both the tubing and the plug, producing a metal-metal sealing surface that is compressed as the package is subjected to hydrostatic pressure. The lower plug would be welded in place before loading, while the upper plug would be placed and welded after loading. Conceptual Waste Packaging Options for Deep Borehole Disposal July 30, 2015 iv Threaded connections between packages would allow emplacement singly or in strings screwed together at the disposal site. For emplacement on a drill string the drill pipe would be connected directly into the top package of a string (using an adapter sub to mate with premium semi-flush tubing threads). Alternatively, for wireline emplacement the same package designs could be emplaced singly using a sub with wireline latch, on the upper end. Threaded connections on the bottom of the lowermost package would allow attachment of a crush box, instrumentation, etc.

  10. Disposal in Crystalline Rocks: FY’15 Progress Report

    Broader source: Energy.gov [DOE]

    The objective of the Crystalline Disposal R&D Work Package is to advance our understanding of long-term disposal of used fuel in crystalline rocks and to develop necessary experimental and...

  11. Strategy for the Management and Disposal of Used Nuclear Fuel...

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

    Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level ...

  12. Moving Forward to Address Nuclear Waste Storage and Disposal...

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

    Moving Forward to Address Nuclear Waste Storage and Disposal Moving Forward to Address Nuclear Waste Storage and Disposal March 24, 2015 - 2:15pm Addthis Three trucks transport ...

  13. Grout treatment facility land disposal restriction management plan

    SciTech Connect (OSTI)

    Hendrickson, D.W.

    1991-04-04

    This document establishes management plans directed to result in the land disposal of grouted wastes at the Hanford Grout Facilities in compliance with Federal, State of Washington, and Department of Energy land disposal restrictions. 9 refs., 1 fig.

  14. DOE Issues Final Environmental Impact Statement for Disposal...

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

    Environmental Impact Statement for Disposal of Greater-Than-Class C Waste DOE Issues Final Environmental Impact Statement for Disposal of Greater-Than-Class C Waste February 25, ...

  15. Operational Issues at the Environmental Restoration Disposal Facility at

    Energy Savers [EERE]

    Hanford | Department of Energy Operational Issues at the Environmental Restoration Disposal Facility at Hanford Operational Issues at the Environmental Restoration Disposal Facility at Hanford Full Document and Summary Versions are available for download PDF icon Operational Issues at the Environmental Restoration Disposal Facility at Hanford PDF icon Summary - Operational Issues at the Environmental Restoration Disposal Facility (ERDF) at Hanford More Documents & Publications Idaho

  16. ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS (Revision 2) |

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

    Department of Energy 4: PROPERTY DISPOSAL RECORDS (Revision 2) ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS (Revision 2) These records pertain to the sales by agencies of real and personal property surplus to the needs of the Government. PDF icon ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS (Revision 2) More Documents & Publications PROPERTY DISPOSAL RECORDS ADMINISTRATIVE RECORDS: PROCUREMENT, SUPPLY, AND GRANT RECORDS ADMINISTRATIVE RECORDS SCHEDULE 3:

  17. Recommendation 223: Recommendations on Additional Waste Disposal Capacity |

    Office of Environmental Management (EM)

    Department of Energy 3: Recommendations on Additional Waste Disposal Capacity Recommendation 223: Recommendations on Additional Waste Disposal Capacity ORSSAB's recommendations encourage DOE to continue planning for an additional on-site disposal facility for low-level waste and that a second facility be placed in an area already used for similar waste disposal. PDF icon Recommendation 223 PDF icon Response to Recommendation 223 More Documents & Publications ORSSAB Meeting - February

  18. Shirley Basin South, Wyoming, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Shirley Basin South, Wyoming, Disposal Site This fact sheet provides information about the Shirley Basin South, Wyoming, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under Title II of the Uranium Mill Tailings Radiation Control Act of 1978. Location of the Shirley Basin South, Wyoming, Disposal Site Site Description and History The Shirley Basin South disposal site is located in rural Carbon County about 60 miles south of Casper and 35 miles

  19. Cover Page of Household Vehicles Energy Use: Latest Data & Trends

    Gasoline and Diesel Fuel Update (EIA)

    Household Vehicles Energy Use Cover Page Cover Page of Household Vehicles Energy Use: Latest Data & Trends...

  20. Application of Generic Disposal System Models

    SciTech Connect (OSTI)

    Mariner, Paul; Hammond, Glenn Edward; Sevougian, S. David; Stein, Emily

    2015-11-01

    This report describes specific GDSA activities in fiscal year 2015 (FY2015) toward the development of the enhanced disposal system modeling and analysis capability for geologic disposal of nuclear waste. The GDSA framework employs the PFLOTRAN thermal-hydrologic-chemical multi-physics code (Hammond et al., 2011) and the Dakota uncertainty sampling and propagation code (Adams et al., 2013). Each code is designed for massively-parallel processing in a high-performance computing (HPC) environment. Multi-physics representations in PFLOTRAN are used to simulate various coupled processes including heat flow, fluid flow, waste dissolution, radionuclide release, radionuclide decay and ingrowth, precipitation and dissolution of secondary phases, and radionuclide transport through the engineered barriers and natural geologic barriers to a well location in an overlying or underlying aquifer. Dakota is used to generate sets of representative realizations and to analyze parameter sensitivity.

  1. Public attitudes toward garbage disposal. Special report

    SciTech Connect (OSTI)

    1990-05-03

    This document is meant to inform the reader about the results of the National Solid Waste Management Association`s opinion research which focused on public attitudes toward recycling, garbage disposal, waste-to-energy, and other waste management concerns. The general public and opinion leaders were asked a wide range of questions about managing our nation`s solid waste and their responses are listed in percentages.

  2. Covered Product Category: Computers | Department of Energy

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

    Computers Covered Product Category: Computers The Federal Energy Management Program (FEMP) provides acquisition guidance for computers, a product category covered by the ENERGY STAR program. Federal laws and requirements mandate that agencies buy ENERGY STAR-qualified products in all product categories covered by this program and any acquisition actions that are not specifically exempted by law. MEETING EFFICIENCY REQUIREMENTS FOR FEDERAL PURCHASES The U.S. Environmental Protection Agency (EPA)

  3. Covered Product Category: Displays | Department of Energy

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

    Displays Covered Product Category: Displays The Federal Energy Management Program (FEMP) provides acquisition guidance for displays, a product category covered by the ENERGY STAR program. Federal laws and requirements mandate that agencies buy ENERGY STAR qualified products in all product categories covered by this program and any acquisition actions that are not specifically exempted by law. MEETING EFFICIENCY REQUIREMENTS FOR FEDERAL PURCHASES The U.S. Environmental Protection Agency (EPA)

  4. Covered Product Category: Data Center Storage

    Broader source: Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) provides acquisition guidance for data center storage, a product category covered by the ENERGY STAR program. Federal laws and requirements mandate that...

  5. Covered Product Category: Commercial Steam Cookers

    Broader source: Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) provides acquisition guidance for commercial steam cookers, which are covered by the ENERGY STAR program.

  6. Covered Product Category: Commercial Refrigerators and Freezers

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Federal Energy Management Program (FEMP) provides acquisition guidance for commercial refrigerators and freezers, which are covered by the ENERGY STAR program.

  7. Covered Product Category: Hot Food Holding Cabinets

    Broader source: Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) provides acquisition guidance for hot food holding cabinets, which are covered by the ENERGY STAR program.

  8. Estimating costs of low-level radioactive waste disposal alternatives for the Commonwealth of Massachusetts

    SciTech Connect (OSTI)

    Not Available

    1994-02-01

    This report was prepared for the Commonwealth of Massachusetts by the Idaho National Engineering Laboratory, National Low-Level Waste Management Program. It presents planning life-cycle cost (PLCC) estimates for four sizes of in-state low-level radioactive waste (LLRW) disposal facilities. These PLCC estimates include preoperational and operational expenditures, all support facilities, materials, labor, closure costs, and long-term institutional care and monitoring costs. It is intended that this report bc used as a broad decision making tool for evaluating one of the several complex factors that must be examined when deciding between various LLRW management options -- relative costs. Because the underlying assumptions of these analyses will change as the Board decides how it will manage Massachusett`s waste and the specific characteristics any disposal facility will have, the results of this study are not absolute and should only be used to compare the relative costs of the options presented. The disposal technology selected for this analysis is aboveground earth-mounded vaults. These vaults are reinforced concrete structures where low-level waste is emplaced and later covered with a multi-layered earthen cap. The ``base case`` PLCC estimate was derived from a preliminary feasibility design developed for the Illinois Low-Level Radioactive Waste Disposal Facility. This PLCC report describes facility operations and details the procedure used to develop the base case PLCC estimate for each facility component and size. Sensitivity analyses were performed on the base case PLCC estimate by varying several factors to determine their influences upon the unit disposal costs. The report presents the results of the sensitivity analyses for the five most significant cost factors.

  9. Field study of disposed solid wastes from advanced coal processes

    SciTech Connect (OSTI)

    Not Available

    1992-01-01

    Radian Corporation and the North Dakota Energy and Environmental Research Center (EERC) are funded to develop information to be used by private industry and government agencies for managing solid wastes produced by advanced coal combustion processes. This information will be developed by conducting several field studies on disposed wastes from these processes. Data will be collected to characterize these wastes and their interactions with the environments in which they are disposed. Three sites were selected for the field studies: Colorado Ute's fluidized bed combustion (FBC) unit in Nucla, Colorado; Ohio Edison's limestone injection multistage burner (LIMB) retrofit in Lorain, Ohio; and Freeman United's mine site in central Illinois with wastes supplied by the nearby Midwest Grain FBC unit. During the past year, field monitoring and sampling of the four landfill test cases constructed in 1989 and 1991 has continued. Option 1 of the contract was approved last year to add financing for the fifth test case at the Freeman United site. The construction of the Test Case 5 cells is scheduled to begin in November, 1992. Work during this past year has focused on obtaining data on the physical and chemical properties of the landfilled wastes, and on developing a conceptual framework for interpreting this information. Results to date indicate that hydration reactions within the landfilled wastes have had a major impact on the physical and chemical properties of the materials but these reactions largely ceased after the first year, and physical properties have changed little since then. Conditions in Colorado remained dry and no porewater samples were collected. In Ohio, hydration reactions and increases in the moisture content of the waste tied up much of the water initially infiltrating the test cells.

  10. Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

    SciTech Connect (OSTI)

    NSTec Environmental Programs

    2010-09-14

    The NTS solid waste disposal sites must be permitted by the state of Nevada Solid Waste Management Authority (SWMA). The SWMA for the NTS is the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). The U.S. Department of Energy's National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as land manager (owner), and National Security Technologies (NSTec), as operator, will store, collect, process, and dispose all solid waste by means that do not create a health hazard, a public nuisance, or cause impairment of the environment. NTS disposal sites will not be included in the Nye County Solid Waste Management Plan. The NTS is located approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada (Figure 1). The U.S. Department of Energy (DOE) is the federal lands management authority for the NTS, and NSTec is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS has signs posted along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The Area 5 RWMS is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NTS (Figure 2), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. A Notice of Intent to operate the disposal site as a Class III site was submitted to the state of Nevada on January 28, 1994, and was acknowledged as being received in a letter to the NNSA/NSO on August 30, 1994. Interim approval to operate a Class III SWDS for regulated asbestiform low-level waste (ALLW) was authorized on August 12, 1996 (in letter from Paul Liebendorfer to Runore Wycoff), with operations to be conducted in accordance with the ''Management Plan for the Disposal of Low-Level Waste with Regulated Asbestos Waste.'' A requirement of the authorization was that on or before October 9, 1999, a permit was required to be issued. Because of NDEP and NNSA/NSO review cycles, the final permit was issued on April 5, 2000, for the operation of the Area 5 Low-Level Waste Disposal Site, utilizing Pit 7 (P07) as the designated disposal cell. The original permit applied only to Pit 7, with a total design capacity of 5,831 cubic yards (yd{sup 3}) (157,437 cubic feet [ft{sup 3}]). NNSA/NSO is expanding the SWDS to include the adjacent Upper Cell of Pit 6 (P06), with an additional capacity of 28,037 yd{sup 3} (756,999 ft{sup 3}) (Figure 3). The proposed total capacity of ALLW in Pit 7 and P06 will be approximately 33,870 yd{sup 3} (0.9 million ft{sup 3}). The site will be used for the disposal of regulated ALLW, small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. The only waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM). The term asbestiform is used throughout this document to describe this waste. Other TSCA waste (i.e., polychlorinated biphenyls [PCBs]) will not be accepted for disposal at the SWDS. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the U.S. Department of Energy, Nevada Operations Office (DOE/NV) 325, Nevada Test Site Waste Acceptance Criteria (NTSWAC, current revision). Approval will be given by NNSA/NSO to generators that have successfully demonstrated through process knowledge (PK) and/or sampling and analysis that the waste is low-level, contains asbestiform material, and does not contain prohibited waste materials. Each waste stream will be approved through the Radioactive Waste Acceptance Program (RWAP), which ensures that the waste meets acceptance requirements outlined in the NTS Class III Permit and the NTSWAC.

  11. Hanford Site waste treatment/storage/disposal integration

    SciTech Connect (OSTI)

    MCDONALD, K.M.

    1999-02-24

    In 1998 Waste Management Federal Services of Hanford, Inc. began the integration of all low-level waste, mixed waste, and TRU waste-generating activities across the Hanford site. With seven contractors, dozens of generating units, and hundreds of waste streams, integration was necessary to provide acute waste forecasting and planning for future treatment activities. This integration effort provides disposition maps that account for waste from generation, through processing, treatment and final waste disposal. The integration effort covers generating facilities from the present through the life-cycle, including transition and deactivation. The effort is patterned after the very successful DOE Complex EM Integration effort. Although still in the preliminary stages, the comprehensive onsite integration effort has already reaped benefits. These include identifying significant waste streams that had not been forecast, identifying opportunities for consolidating activities and services to accelerate schedule or save money; and identifying waste streams which currently have no path forward in the planning baseline. Consolidation/integration of planned activities may also provide opportunities for pollution prevention and/or avoidance of secondary waste generation. A workshop was held to review the waste disposition maps, and to identify opportunities with potential cost or schedule savings. Another workshop may be held to follow up on some of the long-term integration opportunities. A change to the Hanford waste forecast data call would help to align the Solid Waste Forecast with the new disposition maps.

  12. Covered Sites/Populations | Department of Energy

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

    Covered Sites/Populations Covered Sites/Populations Construction Worker Screening Projects Construction Worker Projects, Former Worker Medical Screening Program (FWP) Production Worker Screening Projects Production Worker Projects, Former Worker Medical Screening Program (FWP) National Supplemental Screening Program National Supplemental Screening Program Beryllium Vendor Screening Program Defunct Beryllium Vendor Screening Program

  13. Degradation Of Cementitious Materials Associated With Saltstone Disposal Units

    SciTech Connect (OSTI)

    Flach, G. P; Smith, F. G. III

    2013-03-19

    The Saltstone facilities at the DOE Savannah River Site (SRS) stabilize and dispose of low-level radioactive salt solution originating from liquid waste storage tanks at the site. The Saltstone Production Facility (SPF) receives treated salt solution and mixes the aqueous waste with dry cement, blast furnace slag, and fly ash to form a grout slurry which is mechanically pumped into concrete disposal cells that compose the Saltstone Disposal Facility (SDF). The solidified grout is termed “saltstone”. Cementitious materials play a prominent role in the design and long-term performance of the SDF. The saltstone grout exhibits low permeability and diffusivity, and thus represents a physical barrier to waste release. The waste form is also reducing, which creates a chemical barrier to waste release for certain key radionuclides, notably Tc-99. Similarly, the concrete shell of an SDF disposal unit (SDU) represents an additional physical and chemical barrier to radionuclide release to the environment. Together the waste form and the SDU compose a robust containment structure at the time of facility closure. However, the physical and chemical state of cementitious materials will evolve over time through a variety of phenomena, leading to degraded barrier performance over Performance Assessment (PA) timescales of thousands to tens of thousands of years. Previous studies of cementitious material degradation in the context of low-level waste disposal have identified sulfate attack, carbonation influenced steel corrosion, and decalcification (primary constituent leaching) as the primary chemical degradation phenomena of most relevance to SRS exposure conditions. In this study, degradation time scales for each of these three degradation phenomena are estimated for saltstone and concrete associated with each SDU type under conservative, nominal, and best estimate assumptions. The nominal value (NV) is an intermediate result that is more probable than the conservative estimate (CE) and more defensible than the best estimate (BE). The combined effects of multiple phenomena are then considered to determine the most limiting degradation time scale for each cementitious material. Degradation times are estimated using a combination of analytic solutions from literature and numerical simulation codes provided through the DOE Cementitious Barriers Partnership (CBP) Software Toolbox (http://cementbarriers.org). For the SDU 2 design, the roof, wall, and floor components are projected to become fully degraded under Nominal conditions at 3866, 923, and 1413 years, respectively. For SDU 4 the roof and floor are estimated to be fully degraded under Nominal conditions after 1137 and 1407 years, respectively; the wall is assumed to be fully degraded at time zero in the most recent PA simulations. Degradation of these concrete barriers generally occurs from combined sulfate attack and corrosion of embedded steel following carbonation. Saltstone is projected to degrade very slowly by decalcification, with complete degradation occurring in excess of 200,000 years for any SDU type. Complete results are provided.

  14. First big U.S. reactor dismantled: Project may point the way to a huge market, if sufficient waste disposal sites become available

    SciTech Connect (OSTI)

    Soast, A.,

    1994-07-18

    This article is a review of the Ft. St. Vrain decommissioning efforts. The chain of events leading to actual dismantlement is covered. The projected storage of its fuel at INEL is noted, pending the resolution of legal problems, and the disposal of low-level wastes at Hanford is also noted.

  15. Review of Yucca Mountain Disposal Criticality Studies

    SciTech Connect (OSTI)

    Scaglione, John M [ORNL] [ORNL; Wagner, John C [ORNL] [ORNL

    2011-01-01

    The U.S. Department of Energy (DOE), Office of Civilian Radioactive Waste Management, submitted a license application for construction authorization of a deep geologic repository at Yucca Mountain, Nevada, in June of 2008. The license application is currently under review by the U.S. Nuclear Regulatory Commission. However,on March 3, 2010 the DOE filed a motion requesting withdrawal of the license application. With the withdrawal request and the development of the Blue Ribbon Commission to seek alternative strategies for disposing of spent fuel, the status of the proposed repository at Yucca Mountain is uncertain. What is certain is that spent nuclear fuel (SNF) will continue to be generated and some long-lived components of the SNF will eventually need a disposition path(s). Strategies for the back end of the fuel cycle will continue to be developed and need to include the insights from the experience gained during the development of the Yucca Mountain license application. Detailed studies were performed and considerable progress was made in many key areas in terms of increased understanding of relevant phenomena and issues regarding geologic disposal of SNF. This paper reviews selected technical studies performed in support of the disposal criticality analysis licensing basis and the use of burnup credit. Topics include assembly misload analysis, isotopic and criticality validation, commercial reactor critical analyses, loading curves, alternative waste package and criticality control studies, radial burnup data and effects, and implementation of a conservative application model in the criticality probabilistic evaluation as well as other information that is applicable to operations regarding spent fuel outside the reactor. This paper summarizes the work and significant accomplishments in these areas and provides a resource for future, related activities.

  16. DOE-L.__ PROPOSAL PREPARATION INSTRUCTIONS - COVER LETTER AND

    Office of Environmental Management (EM)

    L. PROPOSAL PREPARATION INSTRUCTIONS - COVER LETTER AND VOLUME I, OFFER AND OTHER DOCUMENTS (a) Instruction - Cover Letter. The cover letter shall include, but not be limited to,...

  17. Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell...

    Office of Legacy Management (LM)

    ... as the basis for a reasonable vegetation management strategy (Waugh and Smith, 1997, 1998). Waugh and Smith (1997, 1998) evaluated the effects of plant root intrusion on radon ...

  18. Graphical methods for evaluating covering arrays

    SciTech Connect (OSTI)

    Kim, Youngil; Jang, Dae -Heung; Anderson-Cook, Christine M.

    2015-08-10

    Covering arrays relax the condition of orthogonal arrays by only requiring that all combination of levels be covered but not requiring that the appearance of all combination of levels be balanced. This allows for a much larger number of factors to be simultaneously considered but at the cost of poorer estimation of the factor effects. To better understand patterns between sets of columns and evaluate the degree of coverage to compare and select between alternative arrays, we suggest several new graphical methods that show some of the patterns of coverage for different designs. These graphical methods for evaluating covering arrays are illustrated with a few examples.

  19. Transuranic waste disposal in the United State

    SciTech Connect (OSTI)

    Thompson, J.D.

    1986-01-01

    The US is unique in having created a special class of radioactive waste disposal based on the concentration of transuranic (TRU) elements in the waste. Since 1970, the US has been placing newly generated TRU waste in retrievable storage. It is intended that these wastes will be placed in a permanent deep geologic repository, the Waste Isolation Pilot Plant (WIPP). The WIPP opening for a demonstration emplacement period is set for October 1988. Transuranic wastes derive from some of the manufacturing and research activities carried out by the US Department of Energy (DOE). The bulk of this waste is generated in plutonium parts fabrication activities. A variety of plutonium-contaminated materials ranging from glove boxes, high-efficiency particulate air filters, and machine tools, to chemical sludges derived from plutonium recovery streams are stored as TRU wastes. Other processes that generate TRU waste are plutonium production operations, preparation for and cleanup from fuel reprocessing, manufacturing of plutonium heat sources, and nuclear fuel cycle research activities. Extensive procedures will be used to examine and prepare waste before it is placed in the WIPP for disposal. After the WIPP opens, certified waste will be transported to it and emplaced in the repository.

  20. REGULATIONS ON PHOTOVOLTAIC MODULE DISPOSAL AND RECYCLING.

    SciTech Connect (OSTI)

    FTHENAKIS,V.

    2001-01-29

    Environmental regulations can have a significant impact on product use, disposal, and recycling. This report summarizes the basic aspects of current federal, state and international regulations which apply to end-of-life photovoltaic (PV) modules and PV manufacturing scrap destined for disposal or recycling. It also discusses proposed regulations for electronics that may set the ground of what is to be expected in this area in the near future. In the US, several states have started programs to support the recycling of electronic equipment, and materials destined for recycling often are excepted from solid waste regulations during the collection, transfer, storage and processing stages. California regulations are described separately because they are different from those of most other states. International agreements on the movement of waste between different countries may pose barriers to cross-border shipments. Currently waste moves freely among country members of the Organization of Economic Cooperation and Development (OECD), and between the US and the four countries with which the US has bilateral agreements. However, it is expected, that the US will adopt the rules of the Basel Convention (an agreement which currently applies to 128 countries but not the US) and that the Convection's waste classification system will influence the current OECD waste-handling system. Some countries adopting the Basel Convention consider end-of-life electronics to be hazardous waste, whereas the OECD countries consider them to be non-hazardous. Also, waste management regulations potentially affecting electronics in Germany and Japan are mentioned in this report.

  1. Study of Factors Affecting Shrub Establishment on the Monticello...

    Office of Environmental Management (EM)

    Study of Factors Affecting Shrub Establishment on the Monticello, Utah, Disposal Cell Cover Study of Factors Affecting Shrub Establishment on the Monticello, Utah, Disposal Cell...

  2. Product Categories Covered by Efficiency Programs

    Office of Energy Efficiency and Renewable Energy (EERE)

    Document shows a list of energy- and water-efficient product categories covered by various efficiency programs, including ENERGY STAR, Federal Energy Management Program (FEMP), Electronic Product Environmental Assessment Tool (EPEAT), FEMP Low Standby Power, and WaterSense.

  3. Six-Year Review of Covered Products

    Broader source: Energy.gov [DOE]

    This memorandum explains that the Energy Independence and Security Act of 2007 (EISA) requires the Department of Energy to re-evaluate efficiency standards for all covered appliances and products...

  4. FEMP Releases Three Updated Covered Product Categories

    Broader source: Energy.gov [DOE]

    By procuring and properly installing efficient products, agencies can meet their requirements, lower energy and water consumption, reduce greenhouse gas emissions, and save money. To help buyers meet these requirements, FEMP has updated three covered product category pages.

  5. Swimming Pool Covers | Department of Energy

    Office of Environmental Management (EM)

    Gas Heating Costs and Savings Use of a pool cover also can help reduce the size of a solar pool heating system, which can save money. How They Work Swimming pools lose energy in...

  6. Swimming Pool Covers | Department of Energy

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

    of heating pools with and without pool covers in different U.S. cities: Estimating Heat Pump Swimming Pool Heater Costs and Savings Estimating Swimming Pool Gas Heating Costs...

  7. The Thermal Collector With Varied Glass Covers

    SciTech Connect (OSTI)

    Luminosu, I.; Pop, N.

    2010-08-04

    The thermal collector with varied glass covers represents an innovation realized in order to build a collector able to reach the desired temperature by collecting the solar radiation from the smallest surface, with the highest efficiency. In the case of the thermal collector with variable cover glasses, the number of the glass plates covering the absorber increases together with the length of the circulation pipe for the working fluid. The thermal collector with varied glass covers compared to the conventional collector better meet user requirements because: for the same temperature increase, has the collecting area smaller; for the same collection area, realizes the highest temperature increase and has the highest efficiency. This works is addressed to researchers in the solar energy and to engineers responsible with air-conditioning systems design or industrial and agricultural products drying.

  8. Defense High Level Waste Disposal Container System Description

    SciTech Connect (OSTI)

    2000-10-12

    The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms (IPWF)) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as 'co-disposal'. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by which to identify the disposal container and its contents. Different materials will be selected for the disposal container inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lids will be a barrier made of high-nickel alloy. The defense HLW disposal container interfaces with the emplacement drift environment and the internal waste by transferring heat from the canisters to the external environment and by protecting the canisters and their contents from damage/degradation by the external environment. The disposal container also interfaces with the canisters by limiting access of moderator and oxidizing agents to the waste. A loaded and sealed disposal container (waste package) interfaces with the Emplacement Drift System's emplacement drift waste package supports upon which the waste packages are placed. The disposal container interfaces with the Canister Transfer System, Waste Emplacement /Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement, and retrieval for the disposal container/waste package.

  9. Repositioning of Covered Stents: The Grip Technique

    SciTech Connect (OSTI)

    Kirby, John Martin; Guo Xiaofeng; Midia, Mehran

    2011-06-15

    Introduction: Retrieval and repositioning of a stent deployed beyond its intended target region may be a difficult technical challenge. Materials and Methods: A balloon-mounted snare technique, a variant of the coaxial loop snare technique, is described. Results: The technique is described for the repositioning of a covered transjugular intrahepatic portosystemic shunt stent and a covered biliary stent. Conclusion: The balloon-mounted snare technique is a useful technique for retrieval of migrated stents.

  10. 2014 Water Power Peer Review Report Cover | Department of Energy

    Office of Environmental Management (EM)

    Peer Review Report Cover 2014 Water Power Peer Review Report Cover 2014 Water Power Peer Review Report Cover.JPG More Documents & Publications NOWEGIS Report Cover Water Power For...

  11. LANL completes excavation of 1940s waste disposal site

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

    LANL completes excavation LANL completes excavation of 1940s waste disposal site The excavation removed about 43,000 cubic yards of contaminated debris and soil from the six-acre site. September 22, 2011 Workers sample contents of LANL's Material Disposal Area B (MDA-B) before excavation Workers sample contents of LANL's Material Disposal Area B (MDA-B) before excavation. Contact Colleen Curran Communications Office (505) 664-0344 Email LOS ALAMOS, New Mexico, September 22, 2011-Los Alamos

  12. Microsoft Word - WIPP Marks A Decade of Safe Disposal

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

    Marks a Decade of Safe Disposal CARLSBAD, N.M., March 25, 2009 - The nation's first and only deep geologic repository for the disposal of defense-related transuranic (TRU) radioactive waste has safely operated for more than 10 years. The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) began disposal operations March 26, 1999 and today serves as an international model for radioactive waste management. "What this project has accomplished is remarkable," said DOE

  13. FY 2006 ANNUAL REVIEW-SALTSTONE DISPOSAL FACILITY PERFORMANCE ASSESSMENT

    SciTech Connect (OSTI)

    Crapse, K; Benjamin Culbertson, B

    2007-03-15

    The Z-Area Saltstone Disposal Facility (SDF) consists of two disposal units, Vaults 1 and 4, described in the Performance Assessment (PA) (WSRC 1992). The FY06 PA Annual Review concludes that both vaults contain much lower levels of radionuclides (curies) than that allowed by the PA. The PA controls established to govern waste operations and monitor disposal facility performance are determined to be adequate.

  14. WIPP Concludes Zone Recovery Activities for Panel 7 Disposal Pathway

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

    24, 2015 WIPP Concludes Zone Recovery Activities for Panel 7 Disposal Pathway After months of catch-up rock bolting and contamination mitigation, zone recovery activities along the pathway to Panel 7 have been completed. Panel 7, which consists of seven disposal rooms (see map below), will be the active disposal area when waste emplacement activities resume. Initial closure of Panel 7 Room 7 was completed in May 2015. Although the pathway has been established, a significant number of activities,

  15. Durango, Colorado, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Durango, Colorado, Processing and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing and disposal sites located at Durango, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Durango Processing and Disposal Sites Site Description and History The Durango processing site is a former uranium-ore processing facility located a quarter of a mile southwest of

  16. Naturita, Colorado, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Naturita, Colorado, Processing and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing and disposal sites located at Naturita, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Naturita, Colorado, Processing and Disposal Sites Site Description and History The Naturita processing site is a former uranium- and vanadium-ore processing facility in western

  17. Rifle, Colorado, Processing Sites and Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    5 Fact Sheet UMTRCA Title I UMTRCA Title I Rifle, Colorado, Processing Sites and Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing sites and disposal site near Rifle, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Rife Processing Sites and Disposal Site Site Description and History Two former uranium and vanadium processing sites are located near the

  18. Slick Rock, Colorado, Processing Sites and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Slick Rock, Colorado, Processing Sites and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing sites and disposal site at Slick Rock, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Slick Rock, Colorado, Processing and Disposal Sites Site Descriptions and History The Slick Rock processing sites consist of two former uranium- and vanadium-ore processing

  19. Section 3116 Waste Determinationfor Salt Disposal at the Savannah River

    Office of Environmental Management (EM)

    Site, signed by Secretary of Energy, Samuel W. Bodman | Department of Energy Section 3116 Waste Determinationfor Salt Disposal at the Savannah River Site, signed by Secretary of Energy, Samuel W. Bodman Section 3116 Waste Determinationfor Salt Disposal at the Savannah River Site, signed by Secretary of Energy, Samuel W. Bodman PDF icon Section 3116 Waste Determinationfor Salt Disposal at the Savannah River Site, signed by Secretary of Energy, Samuel W. Bodman More Documents &

  20. Grand Junction, Colorado, Disposal Site Long-Term Surveillance...

    Office of Legacy Management (LM)

    ... Grand Junction, Colorado, Disposal Site Long-Term Surveillance and Maintenance Program The Grand Junction Office has provided cost-effective and efficient stewardship for more than ...

  1. Deep Borehole Disposal Research: Geological Data Evaluation Alternativ...

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

    much of the enhanced geothermal focus on stimulating fracture development (e.g., fracking) at depth is not directly relevant to deep borehole disposal. For deep borehole...

  2. January 28, 2016 Webinar- Borehole Disposal of Spent Radioactive Sources

    Broader source: Energy.gov [DOE]

    Performance & RIsk Assessment (P&RA) Community of Practice (CoP) Webinar - January 28, 2016 - Borehole Disposal of Spent Radioactive Sources (Dr. Matt Kozak, INTERA).

  3. July 2015 Groundwater Sampling at the Sherwood, Washington, Disposal...

    Office of Legacy Management (LM)

    Sherwood, Washington, Disposal Site October 2015 LMSSHES00715 This page intentionally left blank U.S. Department of Energy DVP-July 2015, Sherwood, Washington October 2015 RIN ...

  4. Summary - Disposal Practices at the Nevada Test Site

    Energy Savers [EERE]

    Area 5 LLRW & MLLW Disposal ETR Report Date: July 2008 ETR-14 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Disposal Practices at the Nevada Test Site Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada Test Site (NTS), other DOE facilities and other federal agencies are disposed of at NTS at two low-level radioactive waste (LLRW) management sites: Areas 3 and 5. Disposal operations at Area 3 have been

  5. An Investigation for Disposal of Drill Cuttings into Unconsolidated...

    Office of Scientific and Technical Information (OSTI)

    Country of Publication: United States Language: English Subject: 02 PETROLEUM; DRILLING FLUIDS; MINERAL WASTES; ROCK MECHANICS; SANDSTONES; CLAYS; DISPOSAL WELLS; ABANDONED WELLS; ...

  6. LOW-LEVEL WASTE DISPOSAL FACILITY FEDERAL REVIEW GROUP EXECUTION...

    Office of Environmental Management (EM)

    LOW-LEVEL WASTE DISPOSAL FACILITY FEDERAL REVIEW GROUP ... 13 9.0 LFRG Management Processes ... Specific Proficiency Checklist in Attachment 3 within one ...

  7. Hazardous Waste Treatment, Storage and Disposal Facilities (TSDF...

    Open Energy Info (EERE)

    Treatment, Storage and Disposal Facilities (TSDF) Guidance Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook:...

  8. Enhancements to Generic Disposal System Modeling Capabilities Rev2

    Broader source: Energy.gov [DOE]

    Contributions are described for the development of an enhanced generic disposal system modeling and analysis capability that takes advantage of high-performance computing (HPC) environments to...

  9. Depleted uranium storage and disposal trade study: Summary report

    SciTech Connect (OSTI)

    Hightower, J.R.; Trabalka, J.R.

    2000-02-01

    The objectives of this study were to: identify the most desirable forms for conversion of depleted uranium hexafluoride (DUF6) for extended storage, identify the most desirable forms for conversion of DUF6 for disposal, evaluate the comparative costs for extended storage or disposal of the various forms, review benefits of the proposed plasma conversion process, estimate simplified life-cycle costs (LCCs) for five scenarios that entail either disposal or beneficial reuse, and determine whether an overall optimal form for conversion of DUF6 can be selected given current uncertainty about the endpoints (specific disposal site/technology or reuse options).

  10. Passive and active plasma deceleration for the compact disposal...

    Office of Scientific and Technical Information (OSTI)

    Passive and active plasma deceleration for the compact disposal of electron beams Citation Details In-Document Search This content will become publicly available on August 11, 2016...

  11. OAK RIDGE CERCLA DISPOSAL FACILITY ACHIEVES SAFETY MILESTONE

    Broader source: Energy.gov [DOE]

    Oak Ridge, TN - The Environmental Management Waste Management Facility (EMWMF) provides the onsite disposal capability for the majority of cleanup-generated wastes on the Oak Ridge Reservation....

  12. Low-Level Waste Disposal Alternatives Analysis Report

    SciTech Connect (OSTI)

    Timothy Carlson; Kay Adler-Flitton; Roy Grant; Joan Connolly; Peggy Hinman; Charles Marcinkiewicz

    2006-09-01

    This report identifies and compares on-site and off-site disposal options for the disposal of contract-handled and remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Potential disposal options are screened for viability by waste type resulting in a short list of options for further consideration. The most crediable option are selected after systematic consideration of cost, schedule constraints, and risk. In order to holistically address the approach for low-level waste disposal, options are compiled into comprehensive disposal schemes, that is, alternative scenarios. Each alternative scenario addresses the disposal path for all low-level waste types over the period of interest. The alternative scenarios are compared and ranked using cost, risk and complexity to arrive at the recommended approach. Schedule alignment with disposal needs is addressed to ensure that all waste types are managed appropriately. The recommended alternative scenario for the disposal of low-level waste based on this analysis is to build a disposal facility at the Idaho National Laboratory Site.

  13. RRC - Injection/Disposal Well Permitting, Testing, and Monitoring...

    Open Energy Info (EERE)

    InjectionDisposal Well Permitting, Testing, and Monitoring manual Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - Guide...

  14. Method for disposing of hazardous wastes

    DOE Patents [OSTI]

    Burton, Frederick G. (West Richland, WA); Cataldo, Dominic A. (Kennewick, WA); Cline, John F. (Prosser, WA); Skiens, W. Eugene (Richland, WA)

    1995-01-01

    A method and system for long-term control of root growth without killing the plants bearing those roots involves incorporating a 2,6-dinitroaniline in a polymer and disposing the polymer in an area in which root control is desired. This results in controlled release of the substituted aniline herbicide over a period of many years. Herbicides of this class have the property of preventing root elongation without translocating into other parts of the plant. The herbicide may be encapsulated in the polymer or mixed with it. The polymer-herbicide mixture may be formed into pellets, sheets, pipe gaskets, pipes for carrying water, or various other forms. The invention may be applied to other protection of buried hazardous wastes, protection of underground pipes, prevention of root intrusion beneath slabs, the dwarfing of trees or shrubs and other applications. The preferred herbicide is 4-difluoromethyl-N,N-dipropyl- 2,6-dinitro-aniline, commonly known as trifluralin.

  15. Transuranic waste disposal in the United States

    SciTech Connect (OSTI)

    Hoffman, R.B.

    1986-01-01

    The United States is unique in having created a special class of radioactive waste disposal based on the concentration of transuranic elements in the waste. Since 1970, the US has been placing newly generated transuranic waste in retrievable storage. It is intended that these wastes will be placed in a permanent deep geologic repository, the Waste Isolation Pilot Plant (WIPP). WIPP opening for a demonstration emplacement period is set for October, 1988. Transuranic wastes derive from some of the manufacturing and research activities carried out by DOE. The bulk of this waste is generated in plutonium parts fabrication activities. A variety of plutonium contaminated materials ranging from glove boxes, HEPA filters, and machine tools, to chemical sludges derived from plutonium recovery streams are stored as TRU wastes. Other processes that generate TRU waste are plutonium production operations, preparation for and cleanup from fuel reprocessing, manufacturing of plutonium heat sources, and nuclear fuel cycle research activities.

  16. Disposable sludge dewatering container and method

    DOE Patents [OSTI]

    Cole, Clifford M.

    1993-01-01

    A device and method for preparing sludge for disposal comprising a box with a thin layer of gravel on the bottom and a thin layer of sand on the gravel layer, an array of perforated piping deployed throughout the gravel layer, and a sump in the gravel layer below the perforated piping array. Standpipes connect the array and sump to an external ion exchanger/fine particulate filter and a pump. Sludge is deposited on the sand layer and dewatered using a pump connected to the piping array, topping up with more sludge as the aqueous component of the sludge is extracted. When the box is full and the free standing water content of the sludge is acceptable, the standpipes are cut and sealed and the lid secured to the box.

  17. Challenges in Disposing of Anthrax Waste

    SciTech Connect (OSTI)

    Lesperance, Ann M.; Stein, Steven L.; Upton, Jaki F.; Toomey, Christopher

    2011-09-01

    Disasters often create large amounts of waste that must be managed as part of both immediate response and long-term recovery. While many federal, state, and local agencies have debris management plans, these plans often do not address chemical, biological, and radiological contamination. The Interagency Biological Restoration Demonstration’s (IBRD) purpose was to holistically assess all aspects of an anthrax incident and assist the development of a plan for long-term recovery. In the case of wide-area anthrax contamination and the follow-on response and recovery activities, a significant amount of material will require decontamination and disposal. Accordingly, IBRD facilitated the development of debris management plans to address contaminated waste through a series of interviews and workshops with local, state, and federal representatives. The outcome of these discussion was the identification of three primary topical areas that must be addressed: 1) Planning; 2) Unresolved research questions, and resolving regulatory issues.

  18. Consolidation and disposal of PWR fuel inserts

    SciTech Connect (OSTI)

    Wakeman, B.H. (Virginia Electric and Power Co., Glen Allen, VA (United States))

    1992-08-01

    Design and licensing of the Surry Power Station Independent Spent Fuel Storage Installation was initiated in 1982 by Virginia Power as part of a comprehensive strategy to increase spent fuel storage capacity at the Station. Designed to use large, metal dry storage casks, the Surry Installation will accommodate 84 such casks with a total storage capacity of 811 MTU of spent pressurized water reactor fuel assemblies. Virginia Power provided three storage casks for testing at the Idaho National Engineerinq Laboratory's Test Area North and the testing results have been published by the Electric Power Research Institute. Sixty-nine spent fuel assemblies were transported in truck casks from the Surry Power Station to Test Area North for testing in the three casks. Because of restrictions imposed by the cask testing equipment at Test Area North, the irradiated insert components stored in these fuel assemblies at Surry were removed prior to transport of the fuel assemblies. Retaining these insert components proved to be a problem because of a shortage of spent fuel assemblies in the spent fuel storage pool that did not already contain insert components. In 1987 Virginia Power contracted with Chem-Nuclear Systems, Inc. to process and dispose of 136 irradiated insert components consisting of 125 burnable poison rod assemblies, 10 thimble plugging devices and 1 part-length rod cluster control assembly. This work was completed in August and September 1987, culminating in the disposal at the Barnwell, SC low-level radioactive waste facility of two CNS 3-55 liners containing the consolidated insert components.

  19. Coupled Environmental Processes in the Mojave Desert and Implications for ET Covers as Stable Landforms

    SciTech Connect (OSTI)

    D. Shafer; M. Y oung; S. Zitzer; E. McDonald; T. Caldwell

    2006-01-18

    Monolayer evapotranspiration (ET) covers are the baseline method for closure of disposal sites for low-level radioactive waste (LLW), mixed LLW, and transuranic (TRU) waste at the Nevada Test Site (NTS). The regulatory timeline is typically 1,000 years for LLW and 10,000 years for TRU waste. Covers for such waste have different technical considerations than those with shorter timelines because they are subject to environmental change for longer periods of time, and because the environmental processes are often coupled. To evaluate these changes, four analog sites (approximately 30, 1,000 to 2,000, 7,000 to 12,500, and 125,000 years in age) on the NTS were analyzed to address the early post-institutional control period (the youngest site), the 1,000-year compliance period for disposal of LLW, and the 10,000-year period for TRU waste. Tests included soil texture, structure, and morphology; surface soil infiltration and hydraulic conductivity; vegetation and faunal surveys; and literature reviews. Separate measurements were made in plant undercanopy and intercanopy areas. The results showed a progressive increase in silt and clay content of surface soils with age. Changes in soil texture and structure led to a fivefold decline in saturated hydraulic conductivity in intercanopy areas, but no change in undercanopies, which were subject to bioturbation. These changes may have been responsible for the reduction in total plant cover, most dramatically in intercanopy areas, primarily because more precipitation either runs off the site or is held nearer to the surface where plant roots are less common. The results suggest that covers may evolve over longer timeframes to stable landforms that minimize the need for active maintenance.

  20. Graphical methods for evaluating covering arrays

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

    Kim, Youngil; Jang, Dae -Heung; Anderson-Cook, Christine M.

    2015-08-10

    Covering arrays relax the condition of orthogonal arrays by only requiring that all combination of levels be covered but not requiring that the appearance of all combination of levels be balanced. This allows for a much larger number of factors to be simultaneously considered but at the cost of poorer estimation of the factor effects. To better understand patterns between sets of columns and evaluate the degree of coverage to compare and select between alternative arrays, we suggest several new graphical methods that show some of the patterns of coverage for different designs. As a result, these graphical methods formore » evaluating covering arrays are illustrated with a few examples.« less

  1. Land Use and Land Cover Change

    SciTech Connect (OSTI)

    Brown, Daniel; Polsky, Colin; Bolstad, Paul V.; Brody, Samuel D.; Hulse, David; Kroh, Roger; Loveland, Thomas; Thomson, Allison M.

    2014-05-01

    A contribution to the 3rd National Climate Assessment report, discussing the following key messages: 1. Choices about land-use and land-cover patterns have affected and will continue to affect how vulnerable or resilient human communities and ecosystems are to the effects of climate change. 2. Land-use and land-cover changes affect local, regional, and global climate processes. 3. Individuals, organizations, and governments have the capacity to make land-use decisions to adapt to the effects of climate change. 4. Choices about land use and land management provide a means of reducing atmospheric greenhouse gas levels.

  2. Covered Product Category: Light Fixtures (Luminaires)

    Broader source: Energy.gov [DOE]

    FEMP provides acquisition guidance and Federal efficiency requirements across a variety of product categories, including luminaires, or light fixtures. The luminaires product category is very broad and covers a wide variety of lighting products. Both ENERGY STAR® and FEMP provide programmatic guidance for various types of luminaires. See table 2 for more information about which types of light fixtures are covered by which program (FEMP or ENERGY STAR). Federal laws and requirements mandate that agencies meet these efficiency requirements in all procurement and acquisition actions that are not specifically exempted by law.

  3. An Evaluation of Long-Term Performance of Liner Systems for Low-Level Waste Disposal Facilities

    SciTech Connect (OSTI)

    Arthur S. Rood; Annette L. Schafer; A. Jeffrey Sondrup

    2011-03-01

    Traditional liner systems consisting of a geosynthetic membrane underlying a waste disposal facility coupled with a leachate collection system have been proposed as a means of containing releases of low-level radioactive waste within the confines of the disposal facility and thereby eliminating migration of radionuclides into the vadose zone and groundwater. However, this type of hydraulic containment liner system is only effective as long as the leachate collection system remains functional or an overlying cover limits the total infiltration to the volumetric pore space of the disposal system. If either the leachate collection system fails, or the overlying cover becomes less effective during the 1,000’s of years of facility lifetime, the liner may fill with water and release contaminated water in a preferential or focused manner. If the height of the liner extends above the waste, the waste will become submerged which could increase the release rate and concentration of the leachate. If the liner extends near land surface, there is the potential for contamination reaching land surface creating a direct exposure pathway. Alternative protective liner systems can be engineered that eliminate radionuclide releases to the vadose zone during operations and minimizing long term migration of radionuclides from the disposal facility into the vadose zone and aquifer. Non-traditional systems include waste containerization in steel or composite materials. This type of system would promote drainage of clean infiltrating water through the facility without contacting the waste. Other alternatives include geochemical barriers designed to transmit water while adsorbing radionuclides beneath the facility. Facility performance for a hypothetical disposal facility has been compared for the hydraulic and steel containerization liner alternatives. Results were compared in terms of meeting the DOE Order 435.1 low-level waste performance objective of 25 mrem/yr all-pathways dose during the 1) institutional control period (0-100 years), compliance period (0-1000 years) and post-compliance period (>1000 years). Evaluation of the all pathway dose included the dose from ingestion and irrigation of contaminated groundwater extracted from a well 100 meters downgradient, in addition to the dose received from direct contact of radionuclides deposited near the surface resulting from facility overflow. Depending on the disposal facility radionuclide inventory, facility design, cover performance, and the location and environment where the facility is situated, the dose from exposure via direct contact of near surface deposited radionuclides can be much greater than the dose received via transport to the groundwater and subsequent ingestion.

  4. Composite analysis E-area vaults and saltstone disposal facilities

    SciTech Connect (OSTI)

    Cook, J.R.

    1997-09-01

    This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.

  5. Generic Argillite/Shale Disposal Reference Case

    SciTech Connect (OSTI)

    Zheng, Liange; Colon, Carlos Jové; Bianchi, Marco; Birkholzer, Jens

    2014-08-08

    Radioactive waste disposal in a deep subsurface repository hosted in clay/shale/argillite is a subject of widespread interest given the desirable isolation properties, geochemically reduced conditions, and widespread geologic occurrence of this rock type (Hansen 2010; Bianchi et al. 2013). Bianchi et al. (2013) provides a description of diffusion in a clay-hosted repository based on single-phase flow and full saturation using parametric data from documented studies in Europe (e.g., ANDRA 2005). The predominance of diffusive transport and sorption phenomena in this clay media are key attributes to impede radionuclide mobility making clay rock formations target sites for disposal of high-level radioactive waste. The reports by Hansen et al. (2010) and those from numerous studies in clay-hosted underground research laboratories (URLs) in Belgium, France and Switzerland outline the extensive scientific knowledge obtained to assess long-term clay/shale/argillite repository isolation performance of nuclear waste. In the past several years under the UFDC, various kinds of models have been developed for argillite repository to demonstrate the model capability, understand the spatial and temporal alteration of the repository, and evaluate different scenarios. These models include the coupled Thermal-Hydrological-Mechanical (THM) and Thermal-Hydrological-Mechanical-Chemical (THMC) models (e.g. Liu et al. 2013; Rutqvist et al. 2014a, Zheng et al. 2014a) that focus on THMC processes in the Engineered Barrier System (EBS) bentonite and argillite host hock, the large scale hydrogeologic model (Bianchi et al. 2014) that investigates the hydraulic connection between an emplacement drift and surrounding hydrogeological units, and Disposal Systems Evaluation Framework (DSEF) models (Greenberg et al. 2013) that evaluate thermal evolution in the host rock approximated as a thermal conduction process to facilitate the analysis of design options. However, the assumptions and the properties (parameters) used in these models are different, which not only make inter-model comparisons difficult, but also compromise the applicability of the lessons learned from one model to another model. The establishment of a reference case would therefore be helpful to set up a baseline for model development. A generic salt repository reference case was developed in Freeze et al. (2013) and the generic argillite repository reference case is presented in this report. The definition of a reference case requires the characterization of the waste inventory, waste form, waste package, repository layout, EBS backfill, host rock, and biosphere. This report mainly documents the processes in EBS bentonite and host rock that are potentially important for performance assessment and properties that are needed to describe these processes, with brief description other components such as waste inventory, waste form, waste package, repository layout, aquifer, and biosphere. A thorough description of the generic argillite repository reference case will be given in Jové Colon et al. (2014).

  6. Electrochemical apparatus comprising modified disposable rectangular...

    Office of Scientific and Technical Information (OSTI)

    The apparatus are suitable for a variety of electrochemical experiments, including surface electrochemistry, bulk electrolysis, and flow cell experiments. Authors: Dattelbaum, ...

  7. Covered Product Category: Refrigerated Beverage Vending Machines

    Broader source: Energy.gov [DOE]

    FEMP provides acquisition guidance and Federal efficiency requirements across a variety of product categories, including refrigerated beverage vending machines, which are covered by the ENERGY STAR® program. Federal laws and requirements mandate that agencies meet these efficiency requirements in all procurement and acquisition actions that are not specifically exempted by law.

  8. Covered Product Category: Commercial Gas Water Heaters

    Broader source: Energy.gov [DOE]

    FEMP provides acquisition guidance and Federal efficiency requirements across a variety of product categories, including commercial gas water heaters, which are covered by the ENERGY STAR® program. Federal laws and requirements mandate that agencies meet these efficiency requirements in all procurement and acquisition actions that are not specifically exempted by law.

  9. L-Bar, New Mexico, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    ... The cover will reestablish with local vegetation, which will assist in mitigating potential erosion damage by wind and water. Drainage from the cover is directed toward a ...

  10. Disposal of Rocky Flats residues as waste

    SciTech Connect (OSTI)

    Dustin, D.F.; Sendelweck, V.S. . Rocky Flats Plant); Rivera, M.A. )

    1993-01-01

    Work is underway at the Rocky Flats Plant to evaluate alternatives for the removal of a large inventory of plutonium-contaminated residues from the plant. One alternative under consideration is to package the residues as transuranic wastes for ultimate shipment to the Waste Isolation Pilot Plant. Current waste acceptance criteria and transportation regulations require that approximately 1000 cubic yards of residues be repackaged to produce over 20,000 cubic yards of WIPP certified waste. The major regulatory drivers leading to this increase in waste volume are the fissile gram equivalent, surface radiation dose rate, and thermal power limits. In the interest of waste minimization, analyses have been conducted to determine, for each residue type, the controlling criterion leading to the volume increase, the impact of relaxing that criterion on subsequent waste volume, and the means by which rules changes may be implemented. The results of this study have identified the most appropriate changes to be proposed in regulatory requirements in order to minimize the costs of disposing of Rocky Flats residues as transuranic wastes.

  11. Disposal of Rocky Flats residues as waste

    SciTech Connect (OSTI)

    Dustin, D.F.; Sendelweck, V.S.; Rivera, M.A.

    1993-03-01

    Work is underway at the Rocky Flats Plant to evaluate alternatives for the removal of a large inventory of plutonium-contaminated residues from the plant. One alternative under consideration is to package the residues as transuranic wastes for ultimate shipment to the Waste Isolation Pilot Plant. Current waste acceptance criteria and transportation regulations require that approximately 1000 cubic yards of residues be repackaged to produce over 20,000 cubic yards of WIPP certified waste. The major regulatory drivers leading to this increase in waste volume are the fissile gram equivalent, surface radiation dose rate, and thermal power limits. In the interest of waste minimization, analyses have been conducted to determine, for each residue type, the controlling criterion leading to the volume increase, the impact of relaxing that criterion on subsequent waste volume, and the means by which rules changes may be implemented. The results of this study have identified the most appropriate changes to be proposed in regulatory requirements in order to minimize the costs of disposing of Rocky Flats residues as transuranic wastes.

  12. Alternative Site Technology Deployment-Monitoring System for the U-3ax/bl Disposal Unit at the Nevada Test Site

    SciTech Connect (OSTI)

    Dixon, J.M.; Levitt, D.G.; Rawlinson, S.E.

    2001-02-01

    In December 2000, a performance monitoring facility was constructed adjacent to the U-3ax/bl mixed waste disposal unit at the Nevada Test Site (NTS). Recent studies conducted in the arid southwestern United States suggest that a vegetated monolayer evapotranspiration (ET) closure cover may be more effective at isolating waste than traditional Resource Conservation and Recovery Act (RCRA) multi-layered designs. The monitoring system deployed next to the U-3ax/bl disposal unit consists of eight drainage lysimeters with three surface treatments: two are left bare; two are revegetated with native species; two are being allowed to revegetate with invader species; and two are reserved for future studies. Soil used in each lysimeter is native alluvium taken from the same location as the soil used for the cover material on U-3ax/bl. The lysimeters were constructed so that any drainage to the bottom can be collected and measured. To provide a detailed evaluation of the cover performance, an ar ray of 16 sensors was installed in each lysimeter to measure soil water content, soil water potential, and soil temperature. Revegetation of the U-3ax/bl closure cover establishes a stable plant community that maximizes water loss through transpiration while at the same time, reduces water and wind erosion and ultimately restores the disposal unit to its surrounding Great Basin Desert environment.

  13. Standardization of DOE Disposal Facilities Waste Acceptance Process

    SciTech Connect (OSTI)

    SHRADER, T.; MACBETH, P.

    2002-01-01

    On February 25, 2000, the US. Department of Energy (DOE) issued the Record of Decision (ROD) for the Waste Management Programmatic Environmental Impact Statement (WM PEIS) for low-level and mixed low-level wastes (LLW/ MLLW) treatment and disposal. The ROD designated the disposal sites at Hanford and the Nevada Test Site (NTS) to dispose of LLWMLLW from sites without their own disposal facilities. DOE's Richland Operations Office (RL) and the National Nuclear Security Administration's Nevada Operations Office (NV) have been charged with effectively implementing the ROD. To accomplish this task NV and RL, assisted by their operating contractors Bechtel Nevada (BN), Fluor Hanford (FH), and Bechtel Hanford (BH) assembled a task team to systematically map out and evaluate the current waste acceptance processes and develop an integrated, standardized process for the acceptance of LLWMLLW. A structured, systematic, analytical process using the Six Sigma system identified disposal process improvements and quantified the associated efficiency gains to guide changes to be implemented. The review concluded that a unified and integrated Hanford/NTS Waste Acceptance Process would be a benefit to the DOE Complex, particularly the waste generators. The Six Sigma review developed quantitative metrics to address waste acceptance process efficiency improvements, and provides an initial look at development of comparable waste disposal cost models between the two disposal sites to allow quantification of the proposed improvements.

  14. Risk-Based Disposal Plan for PCB Paint in the TRA Fluorinel Dissolution Process Mockup and Gamma Facilities Canal

    SciTech Connect (OSTI)

    R. A. Montgomery

    2008-05-01

    This Toxic Substances Control Act Risk-Based Polychlorinated Biphenyl Disposal plan was developed for the Test Reactor Area Fluorinel Dissolution Process Mockup and Gamma Facilities Waste System, located in Building TRA-641 at the Reactor Technology Complex, Idaho National Laboratory Site, to address painted surfaces in the empty canal under 40 CFR 761.62(c) for paint, and under 40 CFR 761.61(c) for PCBs that may have penetrated into the concrete. The canal walls and floor will be painted with two coats of contrasting non-PCB paint and labeled as PCB. The canal is covered with open decking; the access grate is locked shut and signed to indicate PCB contamination in the canal. Access to the canal will require facility manager permission. Protective equipment for personnel and equipment entering the canal will be required. Waste from the canal, generated during ultimate Decontamination and Decommissioning, shall be managed and disposed as PCB Bulk Product Waste.

  15. Environmental monitoring report for commercial low-level radioactive waste disposal sites (1960`s through 1990`s)

    SciTech Connect (OSTI)

    1996-11-01

    During the time period covered in this report (1960`s through early 1990`s), six commercial low-level radioactive waste (LLRW) disposal facilities have been operated in the US. This report provides environmental monitoring data collected at each site. The report summarizes: (1) each site`s general design, (2) each site`s inventory, (3) the environmental monitoring program for each site and the data obtained as the program has evolved, and (4) what the program has indicated about releases to off-site areas, if any, including a statement of the actual health and safety significance of any release. A summary with conclusions is provided at the end of each site`s chapter. The six commercial LLRW disposal sites discussed are located near: Sheffield, Illinois; Maxey Flats, Kentucky; Beatty, Nevada; West Valley, New York; Barnwell, South Carolina; Richland, Washington.

  16. Electrochemical cell stack assembly

    DOE Patents [OSTI]

    Jacobson, Craig P.; Visco, Steven J.; De Jonghe, Lutgard C.

    2010-06-22

    Multiple stacks of tubular electrochemical cells having a dense electrolyte disposed between an anode and a cathode preferably deposited as thin films arranged in parallel on stamped conductive interconnect sheets or ferrules. The stack allows one or more electrochemical cell to malfunction without disabling the entire stack. Stack efficiency is enhanced through simplified gas manifolding, gas recycling, reduced operating temperature and improved heat distribution.

  17. 2009 ECR Report Cover Letter | Department of Energy

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

    9 ECR Report Cover Letter 2009 ECR Report Cover Letter PDF icon 2009_ECR_Report_Cover_Letter.pdf More Documents & Publications DOE_ECR_Report_2006_(2).pdf DOE ECR Report 2006 2009 ECR FINAL REPORT 2010

  18. Water Power For a Clean Energy Future Cover Photo | Department...

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

    For a Clean Energy Future Cover Photo Water Power For a Clean Energy Future Cover Photo Image icon Water Power For a Clean Energy Future Cover.JPG More Documents & Publications ...

  19. Maintenance Guide for DOE Low-Level Waste Disposal Facility | Department of

    Energy Savers [EERE]

    Energy Maintenance Guide for DOE Low-Level Waste Disposal Facility Maintenance Guide for DOE Low-Level Waste Disposal Facility Maintenance Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses PDF icon Maintenance Guide for DOE Low-Level Waste Disposal Facility More Documents & Publications Format and Content Guide for DOE Low-Level Waste Disposal Facility Format and Content Guide for DOE Low-Level Waste Disposal Facility

  20. Municipal garbage disposal: A problem we cannot ignore

    SciTech Connect (OSTI)

    Not Available

    1989-01-01

    In 1980 the US generated 150 million metric tons of municipal solid waste, and this figure is expected to increase to over 200 million metric tons by 1990. This comment discusses the traditional approaches to waste management, as well as current options available for waste disposal and the federal environmental laws that impinge on these options. Next, the national dimensions of the garbage disposal problem, as epitomized by the garbage barge and the international export of waste generated by this country, are discussed. This Comment concludes with recommendations for a change in public policy to foster recycling, taxing non-biodegradable products, as well as more stringent regulatory controls on solid waste disposal.

  1. Analysis of alternatives for immobilized low activity waste disposal

    SciTech Connect (OSTI)

    Burbank, D.A.

    1997-10-28

    This report presents a study of alternative disposal system architectures and implementation strategies to provide onsite near-surface disposal capacity to receive the immobilized low-activity waste produced by the private vendors. The analysis shows that a flexible unit strategy that provides a suite of design solutions tailored to the characteristics of the immobilized low-activity waste will provide a disposal system that best meets the program goals of reducing the environmental, health, and safety impacts; meeting the schedule milestones; and minimizing the life-cycle cost of the program.

  2. Summary - Disposal Practices at the Savannah River Site

    Office of Environmental Management (EM)

    Nevada Test Site, NV EM Project: Area 5 LLRW & MLLW Disposal ETR Report Date: July 2008 ETR-14 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Disposal Practices at the Nevada Test Site Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada Test Site (NTS), other DOE facilities and other federal agencies are disposed of at NTS at two low-level radioactive waste (LLRW) management sites: Areas 3 and 5.

  3. Immobilized low-level waste disposal options configuration study

    SciTech Connect (OSTI)

    Mitchell, D.E.

    1995-02-01

    This report compiles information that supports the eventual conceptual and definitive design of a disposal facility for immobilized low-level waste. The report includes the results of a joint Westinghouse/Fluor Daniel Inc. evaluation of trade-offs for glass manufacturing and product (waste form) disposal. Though recommendations for the preferred manufacturing and disposal option for low-level waste are outside the scope of this document, relative ranking as applied to facility complexity, safety, remote operation concepts and ease of retrieval are addressed.

  4. Reconstruction of Intensity From Covered Samples

    SciTech Connect (OSTI)

    Barabash, Rozaliya; Watkins, Thomas R; Meisner, Roberta Ann; Burchell, Timothy D; Rosseel, Thomas M

    2015-01-01

    The safe handling of activated samples requires containment and covering the sample to eliminate any potential for contamination. Subsequent characterization of the surface with x-rays ideally necessitates a thin film. While many films appear visually transparent, they are not necessarily x-ray transparent. Each film material has a unique beam attenuation and sometimes have amorphous peaks that can superimpose with those of the sample. To reconstruct the intensity of the underlying activated sample, the x-ray attenuation and signal due to the film needs to be removed from that of the sample. This requires the calculation of unique deconvolution parameters for the film. The development of a reconstruction procedure for a contained/covered sample is described.

  5. Climate Effects of Global Land Cover Change

    SciTech Connect (OSTI)

    Gibbard, S G; Caldeira, K; Bala, G; Phillips, T; Wickett, M

    2005-08-24

    There are two competing effects of global land cover change on climate: an albedo effect which leads to heating when changing from grass/croplands to forest, and an evapotranspiration effect which tends to produce cooling. It is not clear which effect would dominate in a global land cover change scenario. We have performed coupled land/ocean/atmosphere simulations of global land cover change using the NCAR CAM3 atmospheric general circulation model. We find that replacement of current vegetation by trees on a global basis would lead to a global annual mean warming of 1.6 C, nearly 75% of the warming produced under a doubled CO{sub 2} concentration, while global replacement by grasslands would result in a cooling of 0.4 C. These results suggest that more research is necessary before forest carbon storage should be deployed as a mitigation strategy for global warming. In particular, high latitude forests probably have a net warming effect on the Earth's climate.

  6. Proposed On-Site Disposal Facility (OSDF) at the Paducah Gaseous...

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

    Disposal Facility (OSDF) at the Paducah Gaseous Diffusion Plant Proposed On-Site Disposal Facility (OSDF) at the Paducah Gaseous Diffusion Plant Full Document and Summary Versions...

  7. Used Fuel Disposal in Crystalline Rocks: Status and FY14 Progress...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Used Fuel Disposal in Crystalline Rocks: Status and FY14 Progress. Citation Details In-Document Search Title: Used Fuel Disposal in Crystalline Rocks: Status and ...

  8. Covered Product Category: Commercial Gas Water Heaters | Department...

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

    Covered Product Category: Commercial Gas Water Heaters Covered Product Category: Commercial Gas Water Heaters The Federal Energy Management Program (FEMP) provides acquisition ...

  9. Performance Evaluation of the Engineered Cover at the Lakeview...

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

    Evaluation of the Engineered Cover at the Lakeview, Oregon, Uranium Mill Tailings Site Performance Evaluation of the Engineered Cover at the Lakeview, Oregon, Uranium Mill Tailings ...

  10. Microsoft Word - Attachment J-1 Covered Site Contractors and...

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

    Covered Sub-Contractors: HPM Corporation (HPMC) (1012012 - present) HPMC Covered Subs: Computer Science Corp (CSC) Advanced Technologies & Laboratories International, Inc. (ATL)...

  11. Fast Company covers "Just Your Typical New Mexico Image Recognition...

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

    Fast Company covers "Just Your Typical New Mexico Image Recognition Startup Spun Off From A ... covers new technique that may make solar panel production less expensive The ...

  12. EERE Template for Microsoft Word Document Standard Cover and...

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

    Template for Microsoft Word Document Standard Cover and Second Page EERE Template for Microsoft Word Document Standard Cover and Second Page This template was designed for print ...

  13. Microsoft Word - FOA cover sheet.doc | Department of Energy

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

    Microsoft Word - FOA cover sheet.doc Recovery Act, Office of the Biomass Program,Funding Opportunity Announcements Special Notice Microsoft Word - FOA cover sheet.doc...

  14. First-ever Hydropower Market Report Covers Hydropower Generation...

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

    First-ever Hydropower Market Report Covers Hydropower Generation Infrastructure First-ever Hydropower Market Report Covers Hydropower Generation Infrastructure May 28, 2015 -...

  15. "PBS NEWSHOUR" covers new technique that may make solar panel...

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

    covers new technique that may make solar panel production less expensive "PBS NEWSHOUR" covers new technique that may make solar panel production less expensive Scientists have ...

  16. Residential Windows and Window Coverings: A Detailed View of...

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

    Residential Windows and Window Coverings: A Detailed View of the Installed Base and User Behavior Residential Windows and Window Coverings: A Detailed View of the Installed Base ...

  17. Vegetation Cover Analysis of Hazardous Waste Sites in Utah and...

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

    Vegetation Cover Analysis of Hazardous Waste Sites in Utah and Arizona Using Hyperspectral Remote Sensing Vegetation Cover Analysis of Hazardous Waste Sites in Utah and Arizona ...

  18. Microsoft Word - coverFerriticSS.doc

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

    with financial support from the Safety, Codes and Standards program element of the Hydrogen, Fuel Cells and Infrastructure program, Office of Energy Efficiency and Renewable...

  19. Microsoft Word - coverAl.doc

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

    with financial support from the Safety, Codes and Standards program element of the Hydrogen, Fuel Cells and Infrastructure program, Office of Energy Efficiency and Renewable...

  20. Microsoft Word - 8100_cover.doc

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

    with financial support from the Safety, Codes and Standards program element of the Hydrogen, Fuel Cells and Infrastructure program, Office of Energy Efficiency and Renewable...

  1. Draft Environmental Impact Statement for the Disposal of Greater...

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

    Friday, February 18, 2011 Draft Environmental Impact Statement for the Disposal of ... many as 50,000 diagnostic medical procedures every day in the U.S. Today, the ...

  2. Disposal Practices at the Nevada Test Site 2008

    Office of Environmental Management (EM)

    Review of Disposal Practices at the Nevada Test Site Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada Test Site (NTS), other DOE facilities and other ...

  3. Final Environmental Impact Statement Brings DOE Closer to Disposing...

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

    geologic repository in New Mexico andor land disposal at ... herself the fifth in a line of GTCC EIS document managers. ... submit your e-mail address below. * indicates required Email ...

  4. Draft Geologic Disposal Requirements Basis for STAD Specification

    SciTech Connect (OSTI)

    Ilgen, Anastasia G.; Bryan, Charles R.; Hardin, Ernest

    2015-03-25

    This document provides the basis for requirements in the current version of Performance Specification for Standardized Transportation, Aging, and Disposal Canister Systems, (FCRD-NFST-2014-0000579) that are driven by storage and geologic disposal considerations. Performance requirements for the Standardized Transportation, Aging, and Disposal (STAD) canister are given in Section 3.1 of that report. Here, the requirements are reviewed and the rationale for each provided. Note that, while FCRD-NFST-2014-0000579 provides performance specifications for other components of the STAD storage system (e.g. storage overpack, transfer and transportation casks, and others), these have no impact on the canister performance during disposal, and are not discussed here.

  5. ORS 466 - Storage, Treatment, and Disposal of Hazardous Waste...

    Open Energy Info (EERE)

    ORS 466 - Storage, Treatment, and Disposal of Hazardous Waste and Materials Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: ORS...

  6. Supporting Calculations For Submerged Bed Scrubber Condensate Disposal Preconceptual Study

    SciTech Connect (OSTI)

    Pajunen, A. J.; Tedeschi, A. R.

    2012-09-18

    This document provides supporting calculations for the preparation of the Submerged Bed Scrubber Condensate Disposal Preconceptual Study report The supporting calculations include equipment sizing, Hazard Category determination, and LAW Melter Decontamination Factor Adjustments.

  7. ORS 454 - Sewage Treatment and Disposal Systems | Open Energy...

    Open Energy Info (EERE)

    54 - Sewage Treatment and Disposal Systems Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: ORS 454 - Sewage Treatment and...

  8. Integration of EBS Models with Generic Disposal System Models

    Broader source: Energy.gov [DOE]

    This report summarizes research activities on engineered barrier system (EBS) model integration with the generic disposal system model (GDSM), and used fuel degradation and radionuclide mobilization (RM) in support of the EBS evaluation and tool development within the UFD campaign.

  9. Second Panel of Disposal Rooms Completed in WIPP Underground

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

    Second Panel of Disposal Rooms Completed in WIPP Underground CARLSBAD, N.M., October 13, ... Crews working in two shifts completed mining Panel 2 weeks ahead of schedule and under ...

  10. Figure ES2. Annual Indices of Real Disposable Income, Vehicle...

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

    ES2 Figure ES2. Annual Indices of Real Disposable Income, Vehicle-Miles Traveled, Consumer Price Index (CPI-U), and Real Average Retail Gasoline Price, 1978-2004, 1985100...

  11. Laboratory to demolish excavation enclosures at Material Disposal...

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

    Excavation Enclosures At MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP Road Pre-demolition activities are beginning this week and the work...

  12. Long-term surveillance plan for the Falls City Disposal Site, Falls City, Texas. Revision 2

    SciTech Connect (OSTI)

    1996-11-01

    The need for ground water monitoring at the Falls City disposal site was evaluated in accordance with NRC regulations and guidelines established by the DOE in Guidance for Implementing the Long-term Surveillance Program for UMTRA Project Title 1 Disposal Sites (DOE, 1996). Based on evaluation of site characterization data, it has been determined that a program to monitor ground water for demonstration of disposal cell performance based on a set of concentration limits is not appropriate because ground water in the uppermost aquifer is of limited use, and a narrative supplemental standard has been applied to the site that does not include numerical concentration limits or a point of compliance. The limited use designation is based on the fact that ground water in the uppermost aquifer is not currently or potentially a source of drinking water in the area because it contains widespread ambient contamination that cannot be cleaned up using methods reasonably employed by public water supply systems. Background ground water quality varies by orders of magnitude since the aquifer is in an area of redistribution of uranium mineralization derived from ore bodies. The DOE plans to perform post-closure ground water monitoring in the uppermost aquifer as a best management practice (BMP) as requested by the state of Texas.

  13. NDAA Section 3116 Waste Determinations with Related Disposal Performance

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

    Assessments | Department of Energy NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 authorizes the Secretary of Energy, in consultation with the Nuclear Regulatory Commission, to reclassify certain waste from reprocessing spent nuclear fuel from high-level waste to low-level waste

  14. Special Analysis for the Disposal of the Neutron Products Incorporated

    Office of Scientific and Technical Information (OSTI)

    Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada (Technical Report) | SciTech Connect Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada Citation Details In-Document Search Title: Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste

  15. An Investigation for Disposal of Drill Cuttings into Unconsolidated

    Office of Scientific and Technical Information (OSTI)

    Sandstones and Clayey Sands (Technical Report) | SciTech Connect Technical Report: An Investigation for Disposal of Drill Cuttings into Unconsolidated Sandstones and Clayey Sands Citation Details In-Document Search Title: An Investigation for Disposal of Drill Cuttings into Unconsolidated Sandstones and Clayey Sands This project include experimental data and a set of models for relating elastic moduli/porosity/texture and static-to-dynamic moduli to strength and failure relationships for

  16. 17.3 - Acquisition, Use and Disposal of Real Property

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

    Chapter 17.3 (March 2011) 1 Acquisition, Use, and Disposal of Real Estate References DEAR 917.74 - Acquisition, Use, and Disposal of Real Estate DOE Directives DOE Order 413.3B, Program and Project Management for the Acquisition of Capital Assets, or current version DOE Order 430.1B, Real Property Asset Management, or current version Overview This section provides internal Departmental information and DOE and NNSA points of contact for issues dealing with real estate acquisition, use, and

  17. Final Environmental Impact Statement Brings DOE Closer to Disposing Unique

    Energy Savers [EERE]

    Waste | Department of Energy Final Environmental Impact Statement Brings DOE Closer to Disposing Unique Waste Final Environmental Impact Statement Brings DOE Closer to Disposing Unique Waste March 16, 2016 - 12:45pm Addthis Theresa Kliczewski, environmental protection specialist in EM’s Office of Disposition Planning and Policy, explains the GTCC EIS path forward to participants in the Waste Management Symposia 2016 in Phoenix. Theresa Kliczewski, environmental protection specialist in

  18. Salt disposal of heat-generating nuclear waste.

    SciTech Connect (OSTI)

    Leigh, Christi D.; Hansen, Francis D.

    2011-01-01

    This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United States repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, helps define a clear strategy for a heat-generating nuclear waste repository in salt.

  19. Naval Spent Nuclear Fuel disposal Container System Description Document

    SciTech Connect (OSTI)

    N. E. Pettit

    2001-07-13

    The Naval Spent Nuclear Fuel Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers/waste packages are loaded and sealed in the surface waste handling facilities, transferred underground through the access drifts using a rail mounted transporter, and emplaced in emplacement drifts. The Naval Spent Nuclear Fuel Disposal Container System provides long term confinement of the naval spent nuclear fuel (SNF) placed within the disposal containers, and withstands the loading, transfer, emplacement, and retrieval operations. The Naval Spent Nuclear Fuel Disposal Container System provides containment of waste for a designated period of time and limits radionuclide release thereafter. The waste package maintains the waste in a designated configuration, withstands maximum credible handling and rockfall loads, limits the waste form temperature after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Each naval SNF disposal container will hold a single naval SNF canister. There will be approximately 300 naval SNF canisters, composed of long and short canisters. The disposal container will include outer and inner cylinder walls and lids. An exterior label will provide a means by which to identify a disposal container and its contents. Different materials will be selected for the waste package inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and the natural barrier will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel while the outer cylinder and outer cylinder lids will be made of high-nickel alloy.

  20. Grand Junction, Colorado, Processing Site and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Grand Junction, Colorado, Disposal and Processing Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal and processing sites at Grand Junction, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Grand Junction, Colorado, Sites Site Description and History The former Grand Junction processing site, historically known as the Climax uranium mill, sits at an elevation of

  1. Gunnison, Colorado, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Gunnison, Colorado, Processing and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing site and disposal site at Gunnison, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Location of the Gunnison, Colorado, Sites Site Description and History The Gunnison, Colorado, Processing Site is a former uranium-ore processing site on a 61.5-acre tract of land adjacent to the

  2. Scoping survey of perceived concerns, issues, and problems for near-surface disposal of FUSRAP waste

    SciTech Connect (OSTI)

    Robinson, J.E.; Gilbert, T.L.

    1982-12-01

    This report is a scoping summary of concerns, issues, and perceived problems for near-surface disposal of radioactive waste, based on a survey of the current literature. Near-surface disposal means land burial in or within 15 to 20 m of the earth's surface. It includes shallow land burial (burial in trenches, typically about 6 m deep with a 2-m cap and cover) and some intermediate-depth land burial (e.g., trenches and cap similar to shallow land burial, but placed below 10 to 15 m of clean soil). Proposed solutions to anticipated problems also are discussed. The purpose of the report is to provide a better basis for identifying and evaluating the environmental impacts and related factors that must be analyzed and compared in assessing candidate near-surface disposal sites for FUSRAP waste. FUSRAP wastes are of diverse types, and their classification for regulatory purposes is not yet fixed. Most of it may be characterized as low-activity bulk solid waste, and is similar to mill tailings, but with somewhat lower average specific activity. It may also qualify as Class A segregated waste under the proposed 10 CFR 61 rules, but the parent radionuclides of concern in FUSRAP (primarily U-238 and Th-232) have longer half-lives than do the radionuclides of concern in most low-level waste. Most of the references reviewed deal with low-level waste or mill tailings, since there is as yet very little literature in the public domain on FUSRAP per se.

  3. Uncanistered Spent Nuclear fuel Disposal Container System Description Document

    SciTech Connect (OSTI)

    N. E. Pettit

    2001-07-13

    The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident.

  4. Standardization of DOE Disposal Facilities Waste Acceptance Processes

    SciTech Connect (OSTI)

    Shrader, T. A.; Macbeth, P. J.

    2002-02-26

    On February 25, 2000, the U.S. Department of Energy (DOE) issued the Record of Decision (ROD) for the Waste Management Programmatic Environmental Impact Statement (WM PEIS) for low-level and mixed low-level wastes (LLW/ MLLW) treatment and disposal. The ROD designated the disposal sites at Hanford and the Nevada Test Site (NTS) to dispose of LLW/MLLW from sites without their own disposal facilities. DOE's Richland Operations Office (RL) and the National Nuclear Security Administration's Nevada Operations Office (NV) have been charged with effectively implementing the ROD. To accomplish this task NV and RL, assisted by their operating contractors Bechtel Nevada (BN), Fluor Hanford (FH), and Bechtel Hanford (BH) assembled a task team to systematically map out and evaluate the current waste acceptance processes and develop an integrated, standardized process for the acceptance of LLW/MLLW. A structured, systematic, analytical process using the Six Sigma system identified dispos al process improvements and quantified the associated efficiency gains to guide changes to be implemented. The review concluded that a unified and integrated Hanford/NTS Waste Acceptance Process would be a benefit to the DOE Complex, particularly the waste generators. The Six Sigma review developed quantitative metrics to address waste acceptance process efficiency improvements, and provides an initial look at development of comparable waste disposal cost models between the two disposal sites to allow quantification of the proposed improvements.

  5. Bypass diode for a solar cell

    DOE Patents [OSTI]

    Rim, Seung Bum; Kim, Taeseok; Smith, David D.; Cousins, Peter J.

    2012-03-13

    Bypass diodes for solar cells are described. In one embodiment, a bypass diode for a solar cell includes a substrate of the solar cell. A first conductive region is disposed above the substrate, the first conductive region of a first conductivity type. A second conductive region is disposed on the first conductive region, the second conductive region of a second conductivity type opposite the first conductivity type.

  6. Release and disposal of materials during decommissioning of Siemens MOX fuel fabrication plant at Hanau, Germany

    SciTech Connect (OSTI)

    Koenig, Werner; Baumann, Roland

    2007-07-01

    In September 2006, decommissioning and dismantling of the Siemens MOX Fuel Fabrication Plant in Hanau were completed. The process equipment and the fabrication buildings were completely decommissioned and dismantled. The other buildings were emptied in whole or in part, although they were not demolished. Overall, the decommissioning process produced approximately 8500 Mg of radioactive waste (including inactive matrix material); clearance measurements were also performed for approximately 5400 Mg of material covering a wide range of types. All the equipment in which nuclear fuels had been handled was disposed of as radioactive waste. The radioactive waste was conditioned on the basis of the requirements specified for the projected German final disposal site 'Schachtanlage Konrad'. During the pre-conditioning, familiar processes such as incineration, compacting and melting were used. It has been shown that on account of consistently applied activity containment (barrier concept) during operation and dismantling, there has been no significant unexpected contamination of the plant. Therefore almost all the materials that were not a priori destined for radioactive waste were released without restriction on the basis of the applicable legal regulations (chap. 29 of the Radiation Protection Ordinance), along with the buildings and the plant site. (authors)

  7. Fuel cell sub-assembly

    DOE Patents [OSTI]

    Chi, Chang V.

    1983-01-01

    A fuel cell sub-assembly comprising a plurality of fuel cells, a first section of a cooling means disposed at an end of the assembly and means for connecting the fuel cells and first section together to form a unitary structure.

  8. Waste disposal technology transfer matching requirement clusters for waste disposal facilities in China

    SciTech Connect (OSTI)

    Dorn, Thomas; Nelles, Michael; Flamme, Sabine; Jinming, Cai

    2012-11-15

    Highlights: Black-Right-Pointing-Pointer We outline the differences of Chinese MSW characteristics from Western MSW. Black-Right-Pointing-Pointer We model the requirements of four clusters of plant owner/operators in China. Black-Right-Pointing-Pointer We examine the best technology fit for these requirements via a matrix. Black-Right-Pointing-Pointer Variance in waste input affects result more than training and costs. Black-Right-Pointing-Pointer For China technology adaptation and localisation could become push, not pull factors. - Abstract: Even though technology transfer has been part of development aid programmes for many decades, it has more often than not failed to come to fruition. One reason is the absence of simple guidelines or decision making tools that help operators or plant owners to decide on the most suitable technology to adopt. Practical suggestions for choosing the most suitable technology to combat a specific problem are hard to get and technology drawbacks are not sufficiently highlighted. Western counterparts in technology transfer or development projects often underestimate or don't sufficiently account for the high investment costs for the imported incineration plant; the differing nature of Chinese MSW; the need for trained manpower; and the need to treat flue gas, bunker leakage water, and ash, all of which contain highly toxic elements. This article sets out requirements for municipal solid waste disposal plant owner/operators in China as well as giving an attribute assessment for the prevalent waste disposal plant types in order to assist individual decision makers in their evaluation process for what plant type might be most suitable in a given situation. There is no 'best' plant for all needs and purposes, and requirement constellations rely on generalisations meaning they cannot be blindly applied, but an alignment of a type of plant to a type of owner or operator can realistically be achieved. To this end, a four-step approach is suggested and a technology matrix is set out to ease the choice of technology to transfer and avoid past errors. The four steps are (1) Identification of plant owner/operator requirement clusters; (2) Determination of different municipal solid waste (MSW) treatment plant attributes; (3) Development of a matrix matching requirement clusters to plant attributes; (4) Application of Quality Function Deployment Method to aid in technology localisation. The technology transfer matrices thus derived show significant performance differences between the various technologies available. It is hoped that the resulting research can build a bridge between technology transfer research and waste disposal research in order to enhance the exchange of more sustainable solutions in future.

  9. A water balance study of four landfill cover designs varying in slope for semiarid regions

    SciTech Connect (OSTI)

    Nyhan, J.W.; Schofield, T.G.; Salazar, J.A.

    1997-02-01

    The goal of disposing of radioactive and hazardous waste in shallow landfills is to reduce risk to human health and to the environment by isolating contaminants until they no longer pose a hazard. In order to achieve this, the performance of a landfill cover design without an engineered barrier (Conventional Design) was compared with three designs containing either a hydraulic barrier (EPA Design) or a capillary barrier (Loam and Clay Loam Capillary Barrier Designs). Water balance parameters were measured since 1991 at six-hour intervals for four different landfill cover designs in 1.0- by 10.0-m plots with downhill slopes of 5, 10, 15, and 25%. Whereas runoff generally accounted for only 2-3% of the precipitation losses on these designs, similar values for evapotranspiration ranged from 86% to 91%, with increased evapotranspiration occurring with increases in slope. Consequently, interflow and seepage usually decreased with increasing slope for each landfill cover design. Seepage consisted of up to 10% of the precipitation on the Conventional Design, whereas the hydraulic barrier in the EPA Design effectively controlled seepage at all slopes, and both of the capillary designs worked effectively to eliminate seepage at the higher slopes.

  10. 1998 report on Hanford Site land disposal restrictions for mixed waste

    SciTech Connect (OSTI)

    Black, D.G.

    1998-04-10

    This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-01H. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility. The US Department of Energy, its predecessors, and contractors on the Hanford Facility were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated large quantities of liquid and solid mixed waste. This waste is regulated under authority of both the Resource Conservation and Recovery Act of l976 and the Atomic Energy Act of 1954. This report covers only mixed waste. The Washington State Department of Ecology, US Environmental Protection Agency, and US Department of Energy have entered into the Tri-Party Agreement to bring the Hanford Facility operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDR) plan and its annual updates to comply with LDR requirements for mixed waste. This report is the eighth update of the plan first issued in 1990. The Tri-Party Agreement requires and the baseline plan and annual update reports provide the following information: (1) Waste Characterization Information -- Provides information about characterizing each LDR mixed waste stream. The sampling and analysis methods and protocols, past characterization results, and, where available, a schedule for providing the characterization information are discussed. (2) Storage Data -- Identifies and describes the mixed waste on the Hanford Facility. Storage data include the Resource Conservation and Recovery Act of 1976 dangerous waste codes, generator process knowledge needed to identify the waste and to make LDR determinations, quantities stored, generation rates, location and method of storage, an assessment of storage-unit compliance status, storage capacity, and the bases and assumptions used in making the estimates.

  11. In Situ Grouting of Liquid Waste Disposal Trenches and Experimental Reactor Fuel Disposal Wells at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Johnson, Ch.; Cange, J.; Lambert, R. [Bechtel Jacobs Company, LLC, Oak Ridge, TN (United States); Trujillo, E. [BWXT Pantex, LLC, Amarillo, TX (United States); Julius, J. [U.S. DOE, Oak Ridge Operations Office, Oak Ridge, TN (United States)

    2008-07-01

    In the early to mid-1960's, liquid low-level wastes (LLLW) generated at Oak Ridge National Laboratory were disposed of in specially-constructed, gravel-filled trenches within the Melton Valley watershed at the lab. The initial selected remedy for Trenches 5 and 7 was in situ vitrification; however, an amendment to the record of decision changed the remedy to in situ grouting of the trenches. The work was accomplished by filling the void space within the crushed stone section of each trench with cementitious grout. The contaminated soil surrounding the trenches (1-m perimeter) was then grouted with acrylamide grout. At the HRE fuel wells, a 1-m ring of soil surrounding the fuel wells was grouted with acrylamide. The results of the hydraulic conductivity tests ranged from 4.74 x 10{sup -6} to 3.60 x 10{sup -7} cm/sec, values that were well below the 1 x 10{sup -5} cm/sec design criterion. In summary: The ISG Project was conducted to decrease hydraulic conductivity and thereby decrease water flow and contaminate migration from the area of the trenches. The initial remedy for Trenches 5 and 7 in the Melton Valley ROD was for in situ vitrification of the trench matrix. The remedy was changed to in situ grouting of the trenches and HRE fuel wells through an amendment to the ROD after moisture was found in the trenches. The grouting of the trenches was accomplished by filling the void space within the crushed stone section of each trench with cementitious grout. The contaminated soil surrounding the trenches (1-m perimeter) was then grouted with acrylamide grout to further reduce water infiltration. Soil backfill above each of the seven HRE fuel wells was removed to a depth of approximately 1 m by augering, and the soils were replaced with a cement plug to prevent water infiltration from migrating down the original borehole. Soil surrounding the fuel wells was then grouted with acrylamide to ensure water infiltration through the HRE fuel wells is prevented. A summary of the quantities used is shown. After completion of grouting, in-situ hydraulic conductivities of the grouted materials were measured to verify attainment of the design objective. The areas were then covered with multi-layer caps as part of the MV hydrologic isolation project. (authors)

  12. The Environmental Protection Agency's Safety Standards for Disposal of Spent Nuclear Fuel: Potential Path Forward in Response to the Report of the Blue Ribbon Commission on America's Nuclear Future - 13388

    SciTech Connect (OSTI)

    Forinash, Betsy; Schultheisz, Daniel; Peake, Tom

    2013-07-01

    Following the decision to withdraw the Yucca Mountain license application, the Department of Energy created a Blue Ribbon Commission (BRC) on America's Nuclear Future, tasked with recommending a national strategy to manage the back end of the nuclear fuel cycle. The BRC issued its final report in January 2012, with recommendations covering transportation, storage and disposal of spent nuclear fuel (SNF); potential reprocessing; and supporting institutional measures. The BRC recommendations on disposal of SNF and high-level waste (HLW) are relevant to the U.S. Environmental Protection Agency (EPA), which shares regulatory responsibility with the Nuclear Regulatory Commission (NRC): EPA issues 'generally applicable' performance standards for disposal repositories, which are then implemented in licensing. For disposal, the BRC endorses developing one or more geological repositories, with siting based on an approach that is adaptive, staged and consent-based. The BRC recommends that EPA and NRC work cooperatively to issue generic disposal standards-applying equally to all sites-early in any siting process. EPA previously issued generic disposal standards that apply to all sites other than Yucca Mountain. However, the BRC concluded that the existing regulations should be revisited and revised. The BRC proposes a number of general principles to guide the development of future regulations. EPA continues to review the BRC report and to assess the implications for Agency action, including potential regulatory issues and considerations if EPA develops new or revised generic disposal standards. This review also involves preparatory activities to define potential process and public engagement approaches. (authors)

  13. Costs for off-site disposal of nonhazardous oil field wastes: Salt caverns versus other disposal methods

    SciTech Connect (OSTI)

    Veil, J.A.

    1997-09-01

    According to an American Petroleum Institute production waste survey reported on by P.G. Wakim in 1987 and 1988, the exploration and production segment of the US oil and gas industry generated more than 360 million barrels (bbl) of drilling wastes, more than 20 billion bbl of produced water, and nearly 12 million bbl of associated wastes in 1985. Current exploration and production activities are believed to be generating comparable quantities of these oil field wastes. Wakim estimates that 28% of drilling wastes, less than 2% of produced water, and 52% of associated wastes are disposed of in off-site commercial facilities. In recent years, interest in disposing of oil field wastes in solution-mined salt caverns has been growing. This report provides information on the availability of commercial disposal companies in oil-and gas-producing states, the treatment and disposal methods they employ, and the amounts they charge. It also compares cavern disposal costs with the costs of other forms of waste disposal.

  14. Characterization of 618-11 solid waste burial ground, disposed waste, and description of the waste generating facilities

    SciTech Connect (OSTI)

    Hladek, K.L.

    1997-10-07

    The 618-11 (Wye or 318-11) burial ground received transuranic (TRTJ) and mixed fission solid waste from March 9, 1962, through October 2, 1962. It was then closed for 11 months so additional burial facilities could be added. The burial ground was reopened on September 16, 1963, and continued operating until it was closed permanently on December 31, 1967. The burial ground received wastes from all of the 300 Area radioactive material handling facilities. The purpose of this document is to characterize the 618-11 solid waste burial ground by describing the site, burial practices, the disposed wastes, and the waste generating facilities. This document provides information showing that kilogram quantities of plutonium were disposed to the drum storage units and caissons, making them transuranic (TRU). Also, kilogram quantities of plutonium and other TRU wastes were disposed to the three trenches, which were previously thought to contain non-TRU wastes. The site burial facilities (trenches, caissons, and drum storage units) should be classified as TRU and the site plutonium inventory maintained at five kilograms. Other fissile wastes were also disposed to the site. Additionally, thousands of curies of mixed fission products were also disposed to the trenches, caissons, and drum storage units. Most of the fission products have decayed over several half-lives, and are at more tolerable levels. Of greater concern, because of their release potential, are TRU radionuclides, Pu-238, Pu-240, and Np-237. TRU radionuclides also included slightly enriched 0.95 and 1.25% U-231 from N-Reactor fuel, which add to the fissile content. The 618-11 burial ground is located approximately 100 meters due west of Washington Nuclear Plant No. 2. The burial ground consists of three trenches, approximately 900 feet long, 25 feet deep, and 50 feet wide, running east-west. The trenches constitute 75% of the site area. There are 50 drum storage units (five 55-gallon steel drums welded together) buried in three rows in the northeast comer. In addition, five eight-foot diameter caissons are located at the west end of the center row of the drum storage units. Initially, wastes disposed to the caissons and drum storage units were from the 325 and 327 building hot cells. Later, a small amount of remote-handled (RH) waste from the 309 building Plutonium Recycle Test Reactor (PRTR) cells, and the newly built 324 building hot cells, was disposed at the site.

  15. [Cover page, Margins: Left 1 in

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

    can be requested by telephone by dialing 9-911 from any Nortel telephone or 911 from a cell phone. Assembly points, where personnel evacuating US ITER office must congregate in an...

  16. Multi-pack Disposal Concepts for Spent Fuel (Rev. 0)

    SciTech Connect (OSTI)

    Hadgu, Teklu; Hardin, Ernest; Matteo, Edward N.

    2015-12-01

    At the initiation of the Used Fuel Disposition (UFD) R&D campaign, international geologic disposal programs and past work in the U.S. were surveyed to identify viable disposal concepts for crystalline, clay/shale, and salt host media (Hardin et al., 2012). Concepts for disposal of commercial spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing are relatively advanced in countries such as Finland, France, and Sweden. The UFD work quickly showed that these international concepts are all “enclosed,” whereby waste packages are emplaced in direct or close contact with natural or engineered materials . Alternative “open” modes (emplacement tunnels are kept open after emplacement for extended ventilation) have been limited to the Yucca Mountain License Application Design (CRWMS M&O, 1999). Thermal analysis showed that, if “enclosed” concepts are constrained by peak package/buffer temperature, waste package capacity is limited to 4 PWR assemblies (or 9-BWR) in all media except salt. This information motivated separate studies: 1) extend the peak temperature tolerance of backfill materials, which is ongoing; and 2) develop small canisters (up to 4-PWR size) that can be grouped in larger multi-pack units for convenience of storage, transportation, and possibly disposal (should the disposal concept permit larger packages). A recent result from the second line of investigation is the Task Order 18 report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems (EnergySolution, 2015). This report identifies disposal concepts for the small canisters (4-PWR size) drawing heavily on previous work, and for the multi-pack (16-PWR or 36-BWR).

  17. Multi-Pack Disposal Concepts for Spent Fuel (Revision 1)

    SciTech Connect (OSTI)

    Hardin, Ernest; Matteo, Edward N.; Hadgu, Teklu

    2016-01-01

    At the initiation of the Used Fuel Disposition (UFD) R&D campaign, international geologic disposal programs and past work in the U.S. were surveyed to identify viable disposal concepts for crystalline, clay/shale, and salt host media. Concepts for disposal of commercial spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing are relatively advanced in countries such as Finland, France, and Sweden. The UFD work quickly showed that these international concepts are all “enclosed,” whereby waste packages are emplaced in direct or close contact with natural or engineered materials . Alternative “open” modes (emplacement tunnels are kept open after emplacement for extended ventilation) have been limited to the Yucca Mountain License Application Design. Thermal analysis showed that if “enclosed” concepts are constrained by peak package/buffer temperature, that waste package capacity is limited to 4 PWR assemblies (or 9 BWR) in all media except salt. This information motivated separate studies: 1) extend the peak temperature tolerance of backfill materials, which is ongoing; and 2) develop small canisters (up to 4-PWR size) that can be grouped in larger multi-pack units for convenience of storage, transportation, and possibly disposal (should the disposal concept permit larger packages). A recent result from the second line of investigation is the Task Order 18 report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems. This report identifies disposal concepts for the small canisters (4-PWR size) drawing heavily on previous work, and for the multi-pack (16-PWR or 36-BWR).

  18. Location standards for RCRA Treatment, Storage, and Disposal Facilities (TSDFs). RCRA Information Brief

    SciTech Connect (OSTI)

    Not Available

    1993-10-01

    This bulletin describes RCRA location standards for hazardous waste storage and disposal facilities.

  19. Disposal of oil field wastes into salt caverns: Feasibility, legality, risk, and costs

    SciTech Connect (OSTI)

    Veil, J.A.

    1997-10-01

    Salt caverns can be formed through solution mining in the bedded or domal salt formations that are found in many states. Salt caverns have traditionally been used for hydrocarbon storage, but caverns have also been used to dispose of some types of wastes. This paper provides an overview of several years of research by Argonne National Laboratory on the feasibility and legality of using salt caverns for disposing of oil field wastes, the risks to human populations from this disposal method, and the cost of cavern disposal. Costs are compared between the four operating US disposal caverns and other commercial disposal options located in the same geographic area as the caverns. Argonne`s research indicates that disposal of oil field wastes into salt caverns is feasible and legal. The risk from cavern disposal of oil field wastes appears to be below accepted safe risk thresholds. Disposal caverns are economically competitive with other disposal options.

  20. Uncanistered Spent Nuclear fuel Disposal Container System Description Document

    SciTech Connect (OSTI)

    2000-10-12

    The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in the emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Multiple boiling water reactor (BWR) and pressurized water reactor (PWR) disposal container designs are needed to accommodate the expected range of spent fuel assemblies and provide long-term confinement of the commercial SNF. The disposal container will include outer and inner cylinder walls, outer cylinder lids (two on the top, one on the bottom), inner cylinder lids (one on the top, one on the bottom), and an internal metallic basket structure. Exterior labels will provide a means by which to identify the disposal container and its contents. The two metal cylinders, in combination with the cladding, Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lid will be made of high-nickel alloy. The basket will assist criticality control, provide structural support, and improve heat transfer. The Uncanistered SNF Disposal Container System interfaces with the emplacement drift environment and internal waste by transferring heat from the SNF to the external environment and by protecting the SFN assemblies and their contents from damage/degradation by the external environment. The system also interfaces with the SFN by limiting access of moderator and oxidizing agents of the SFN. The waste package interfaces with the Emplacement Drift System's emplacement drift pallets upon which the wasted packages are placed. The disposal container interfaces with the Assembly Transfer System, Waste Emplacement/Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and retrieval of the disposal container/waste package.

  1. Heterojunction solar cell

    DOE Patents [OSTI]

    Olson, Jerry M.

    1994-01-01

    A high-efficiency single heterojunction solar cell wherein a thin emitter layer (preferably Ga.sub.0.52 In.sub.0.48 P) forms a heterojunction with a GaAs absorber layer. The conversion effiency of the solar cell is at least 25.7%. The solar cell preferably includes a passivating layer between the substrate and the absorber layer. An anti-reflection coating is preferably disposed over the emitter layer.

  2. Heterojunction solar cell

    DOE Patents [OSTI]

    Olson, J.M.

    1994-08-30

    A high-efficiency single heterojunction solar cell is described wherein a thin emitter layer (preferably Ga[sub 0.52]In[sub 0.48]P) forms a heterojunction with a GaAs absorber layer. The conversion efficiency of the solar cell is at least 25.7%. The solar cell preferably includes a passivating layer between the substrate and the absorber layer. An anti-reflection coating is preferably disposed over the emitter layer. 1 fig.

  3. Basic research needs for management and disposal of DOE wastes

    SciTech Connect (OSTI)

    Grazis, B.M.; Horwitz, E.P. ); Schulz, W.W. )

    1991-04-01

    This document was chartered by the Department of Energy (DOE), Office of Energy Research. It identifies and describes 87 basic research needs in support of advanced technology for management and disposal of Department of Energy radioactive, hazardous chemical, and mixed wastes. A team of scientists and engineers from several DOE laboratories and sites, from academia, and from industry identified and described the basic research needs called out in this report. Special efforts were made to ensure that basic research needs related to management and disposal of any hazardous chemical wastes generated at nonnuclear DOE sites and facilities were properly identified. It is hoped that scientists in both DOE and nongovernment laboratories and institutions will find this document useful when formulating research efforts relevant to waste management and disposal. For management and disposal of DOE radioactive and mixed wastes, basic research needs are identified in nine separate action areas. Basic research needs for management and disposal of DOE hazardous chemical wastes are identified in five action areas. Sufficient description and background information are provided in the report for each particular research need to enable qualified and imaginative scientists to conceive research efforts and programs that will meet the need. 28 refs., 7 tabs.

  4. Integrated Disposal Facility FY2011 Glass Testing Summary Report

    SciTech Connect (OSTI)

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Westsik, Joseph H.

    2011-09-29

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 x 10{sup 5} m{sup 3} of glass (Certa and Wells 2010). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 8.9 x 10{sup 14} Bq total activity) of long-lived radionuclides, principally {sup 99}Tc (t{sub 1/2} = 2.1 x 10{sup 5}), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2011 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses.

  5. FACT SHEET: The Path Forward on Nuclear Waste Disposal | Department of

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

    Energy FACT SHEET: The Path Forward on Nuclear Waste Disposal FACT SHEET: The Path Forward on Nuclear Waste Disposal PDF icon FACT SHEET: The Path Forward on Nuclear Waste Disposal More Documents & Publications Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Integrated Waste Management and Consent-Based Siting Booklet

  6. shiprock info sheet 08.20.13.cdr

    Office of Legacy Management (LM)

    operations. 1986 Mill tailings are put in a disposal cell and a cover is constructed over the materials. The disposal cell cover is a barrier that prevents radon gas from ...

  7. Decision document for function 4.2.4 dispose waste

    SciTech Connect (OSTI)

    Claghorn, R.D.

    1996-09-23

    This report formally documents the planning assumptions for Function 4.2.4, Dispose Waste, to provide a basis for lower level Tank Waste Remediation System (TWRS) Disposal Program decisions and analyses. The TWRS Environmental Impact Statement (DOE/EIS 1996) and a supplemental Environmental Impact Statement for closure of operable units will provide the ultimate Records of Decision for the TWRS strategy at this level. However, in the interim, this decision document provides a formal basis for the TWRS Dispose Waste planning assumptions. Function 4.2.4 addresses the disposition of immobilized high-level waste (IHLW), the disposition of immobilized low-activity waste (ILAW), and closure of the tank farm operable units.

  8. Decision document for function 4.2.4 dispose waste

    SciTech Connect (OSTI)

    Mcconville, C.M.

    1996-09-23

    This report formally documents the planning assumptions for Function 4.2.4, {ital Dispose Waste} to provide a basis for lower level Tank Waste Remediation System (TWRS) Disposal Program decisions and analyses. The TWRS Environmental Impact Statement (DOE/EIS 1996) and a supplemental Environmental Impact Statement for closure of operable units will provide the ultimate Records of Decision for the TWRS strategy at this level. However, in the interim, this decision document provides a formal basis for the TWRS Dispose Waste planning assumptions. Function 4.2.4 addresses the disposition of immobilized high-level waste (IHLW), the disposition of immobilized low-activity waste (ILAW), and closure of the tank farm operable units.

  9. Geological aspects of the nuclear waste disposal problem

    SciTech Connect (OSTI)

    Laverov, N.P.; Omelianenko, B.L.; Velichkin, V.I.

    1994-06-01

    For the successful solution of the high-level waste (HLW) problem in Russia one must take into account such factors as the existence of the great volume of accumulated HLW, the large size and variety of geological conditions in the country, and the difficult economic conditions. The most efficient method of HLW disposal consists in the maximum use of protective capacities of the geological environment and in using inexpensive natural minerals for engineered barrier construction. In this paper, the principal trends of geological investigation directed toward the solution of HLW disposal are considered. One urgent practical aim is the selection of sites in deep wells in regions where the HLW is now held in temporary storage. The aim of long-term investigations into HLW disposal is to evaluate geological prerequisites for regional HLW repositories.

  10. International Collaboration Activities in Different Geologic Disposal Environments

    SciTech Connect (OSTI)

    Birkholzer, Jens

    2015-09-01

    This report describes the current status of international collaboration regarding geologic disposal research in the Used Fuel Disposition (UFD) Campaign. Since 2012, in an effort coordinated by Lawrence Berkeley National Laboratory, UFD has advanced active collaboration with several international geologic disposal programs in Europe and Asia. Such collaboration allows the UFD Campaign to benefit from a deep knowledge base with regards to alternative repository environments developed over decades, and to utilize international investments in research facilities (such as underground research laboratories), saving millions of R&D dollars that have been and are being provided by other countries. To date, UFD’s International Disposal R&D Program has established formal collaboration agreements with five international initiatives and several international partners, and national lab scientists associated with UFD have conducted specific collaborative R&D activities that align well with its R&D priorities.

  11. Used Fuel Disposal in Crystalline Rocks. FY15 Progress Report

    SciTech Connect (OSTI)

    Wang, Yifeng

    2015-08-20

    The objective of the Crystalline Disposal R&D Work Package is to advance our understanding of long-term disposal of used fuel in crystalline rocks and to develop necessary experimental and computational capabilities to evaluate various disposal concepts in such media. Chapter headings are as follows: Fuel matrix degradation model and its integration with performance assessments, Investigation of thermal effects on the chemical behavior of clays, Investigation of uranium diffusion and retardation in bentonite, Long-term diffusion of U(VI) in bentonite: dependence on density, Sorption and desorption of plutonium by bentonite, Dissolution of plutonium intrinsic colloids in the presence of clay and as a function of temperature, Laboratory investigation of colloid-facilitated transport of cesium by bentonite colloids in a crystalline rock system, Development and demonstration of discrete fracture network model, Fracture continuum model and its comparison with discrete fracture network model.

  12. Earth melter and method of disposing of feed materials

    DOE Patents [OSTI]

    Chapman, C.C.

    1994-10-11

    An apparatus, and method of operating the apparatus is described, wherein a feed material is converted into a glassified condition for subsequent use or disposal. The apparatus is particularly useful for disposal of hazardous or noxious waste materials which are otherwise either difficult or expensive to dispose of. The apparatus is preferably constructed by excavating a melt zone in a quantity of soil or rock, and lining the melt zone with a back fill material if refractory properties are needed. The feed material is fed into the melt zone and, preferably, combusted to an ash, whereupon the heat of combustion is used to melt the ash to a molten condition. Electrodes may be used to maintain the molten feed material in a molten condition, and to maintain homogeneity of the molten materials. 3 figs.

  13. Earth melter and method of disposing of feed materials

    DOE Patents [OSTI]

    Chapman, Christopher C.

    1994-01-01

    An apparatus, and method of operating the apparatus, wherein a feed material is converted into a glassified condition for subsequent use or disposal. The apparatus is particularly useful for disposal of hazardous or noxious waste materials which are otherwise either difficult or expensive to dispose of. The apparatus is preferably constructed by excavating a melt zone in a quantity of soil or rock, and lining the melt zone with a back fill material if refractory properties are needed. The feed material is fed into the melt zone and, preferably, combusted to an ash, whereupon the heat of combustion is used to melt the ash to a molten condition. Electrodes may be used to maintain the molten feed material in a molten condition, and to maintain homogeneity of the molten materials.

  14. Classified Component Disposal at the Nevada National Security Site

    SciTech Connect (OSTI)

    Poling, J.; Arnold, P.; Saad, M.; DiSanza, F.; Cabble, K.

    2012-11-05

    The Nevada National Security Site (NNSS) has added the capability needed for the safe, secure disposal of non-nuclear classified components that have been declared excess to national security requirements. The NNSS has worked with U.S. Department of Energy, National Nuclear Security Administration senior leadership to gain formal approval for permanent burial of classified matter at the NNSS in the Area 5 Radioactive Waste Management Complex owned by the U.S. Department of Energy. Additionally, by working with state regulators, the NNSS added the capability to dispose non-radioactive hazardous and non-hazardous classified components. The NNSS successfully piloted the new disposal pathway with the receipt of classified materials from the Kansas City Plant in March 2012.

  15. Solid oxide fuel cell with single material for electrodes and interconnect

    DOE Patents [OSTI]

    McPheeters, Charles C.; Nelson, Paul A.; Dees, Dennis W.

    1994-01-01

    A solid oxide fuel cell having a plurality of individual cells. A solid oxide fuel cell has an anode and a cathode with electrolyte disposed therebetween, and the anode, cathode and interconnect elements are comprised of substantially one material.

  16. Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

    SciTech Connect (OSTI)

    W. Mahlon Heileson

    2006-10-01

    The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

  17. Evaluate disposable sample chips and complete the (Technical Report) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Evaluate disposable sample chips and complete the Citation Details In-Document Search Title: Evaluate disposable sample chips and complete the Letter Report detailing plastic sample chip design Authors: Julia Tripp Publication Date: 2013-04-01 OSTI Identifier: 1091352 Report Number(s): INL/EXT-13-28796 DOE Contract Number: DE-AC07-05ID14517 Resource Type: Technical Report Research Org: Idaho National Laboratory (INL) Sponsoring Org: DOE - NE Country of Publication: United

  18. Evaluate disposable sample chips and complete the (Technical Report) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Evaluate disposable sample chips and complete the Citation Details In-Document Search Title: Evaluate disposable sample chips and complete the Ă— You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service. Visit OSTI to utilize additional information resources in energy science and technology. A paper copy of this document is also

  19. Laboratory to demolish excavation enclosures at Material Disposal Area B

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

    near DP Road Excavation Enclosures At MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP Road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the

  20. Laboratory to demolish excavation enclosures at Material Disposal Area B

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

    near DP Road Excavation Enclosures At MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP Road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the

  1. D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE

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

    92 10 CFR Ch. X (1-1-12 Edition) Pt. 1022 D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE Siting, construction or expansion, and op- eration of disposal facilities for transuranic (TRU) waste and TRU mixed waste (TRU waste also containing hazardous waste as designated in 40 CFR part 261). D12 INCINERATORS Siting, construction, and operation of in- cinerators, other than research and develop- ment incinerators or incinerators for non- hazardous solid waste (as designated in 40 CFR 261.4(b)).

  2. DOE Issues Final Environmental Impact Statement for Disposal of

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

    Greater-Than-Class C Waste | Department of Energy Environmental Impact Statement for Disposal of Greater-Than-Class C Waste DOE Issues Final Environmental Impact Statement for Disposal of Greater-Than-Class C Waste February 25, 2016 - 3:30pm Addthis WASHINGTON, D.C. - The U.S. Department of Energy (DOE) today issued a Final Environmental Impact Statement (EIS) that evaluates the potential environmental impacts associated with the proposed development, operation, and long-term management of

  3. A Critical Step Toward Sustainable Nuclear Fuel Disposal | Department of

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

    Energy A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal January 26, 2012 - 2:30pm Addthis Secretary Chu Secretary Chu Former Secretary of Energy The Blue Ribbon Commission on America's Nuclear Future was formed at the direction of the President to conduct a comprehensive review of polices for managing the back end of the nuclear fuel cycle. If we are going to ensure that the United States remains at the forefront of nuclear

  4. Deep Borehole Disposal of Nuclear Waste: Science Needs. (Conference) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Deep Borehole Disposal of Nuclear Waste: Science Needs. Citation Details In-Document Search Title: Deep Borehole Disposal of Nuclear Waste: Science Needs. Abstract not provided. Authors: Wang, Yifeng Publication Date: 2014-10-01 OSTI Identifier: 1241821 Report Number(s): SAND2014-18724C 540320 DOE Contract Number: AC04-94AL85000 Resource Type: Conference Resource Relation: Conference: Proposed for presentation at the MS&T 2014 held October 15, 2014 in Pittsbur

  5. 2009 Performance Assessment for the Saltstone Disposal Facility

    Broader source: Energy.gov [DOE]

    This Performance Assessment (PA) for the Savannah River Site (SRS) was prepared to support the operation and eventual closure of the Saltstone Disposal Facility (SDF). This PA was prepared to demonstrate compliance with the pertinent requirements of the United States Department of Energy (DOE) Order 435.1, Change 1, Radioactive Waste Management, Chapter IV, and Title 10, of the Code of Federal Regulations (CFR) Part 61, Licensing Requirements for Land Disposal of Radioactive Waste, Subpart C as required by the Ronald W. Reagan National Defense Authorization Act (NDAA) for Fiscal Year 2005, Section 3116. [DOE O 435.1-1, 10 CFR 61, NDAA_3116

  6. Laboratory to demolish excavation enclosures at Material Disposal Area B

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

    near DP road Excavation enclosures at MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the

  7. INERT-MATRIX FUEL: ACTINIDE ''BURINGIN'' AND DIRECT DISPOSAL

    SciTech Connect (OSTI)

    Rodney C. Ewing; Lumin Wang

    2002-10-30

    Excess actinides result from the dismantlement of nuclear weapons (Pu) and the reprocessing of commercial spent nuclear fuel (mainly 241 Am, 244 Cm and 237 Np). In Europe, Canada and Japan studies have determined much improved efficiencies for burnup of actinides using inert-matrix fuels. This innovative approach also considers the properties of the inert-matrix fuel as a nuclear waste form for direct disposal after one-cycle of burn-up. Direct disposal can considerably reduce cost, processing requirements, and radiation exposure to workers.

  8. EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion

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

    Dollars | Department of Energy Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion Dollars EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion Dollars August 1, 2012 - 12:00pm Addthis For more than 50 years, the uranium-233 (U-233) supply has been stored at the Oak Ridge National Laboratory’s (ORNL) Building 3019. The facility, located near the center of the ORNL campus, is owned by EM and one of the nation’s few repositories for U-233 and other

  9. WIPP Reaches Milestone „ First Disposal Room Filled

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

    WIPP Reaches Milestone - First Disposal Room Filled CARLSBAD, N.M., September 4, 2001 - The U.S. Department of Energy's (DOE) Carlsbad Field Office today announced that Room 7 of Panel 1 at the Waste Isolation Pilot Plant (WIPP), the first underground room used for disposal operations, has been filled to capacity with transuranic waste. The milestone was reached at about 3:30 p.m. on August 24, as Waste Handling personnel emplaced a shipment of waste from the Idaho National Engineering and

  10. Photovoltaic concentrator assembly with optically active cover

    DOE Patents [OSTI]

    Plesniak, Adam P

    2014-01-21

    A photovoltaic concentrator assembly that includes a housing that defines an internal volume and includes a rim, wherein the rim defines an opening into the internal volume, a photovoltaic cell positioned in the internal volume, and an optical element that includes an optically active body and a flange extending outward from the body, wherein the flange is sealingly engaged with the rim of the housing to enclose the internal volume.

  11. Weaving Community and Science

    Broader source: Energy.gov [DOE]

    Weaving Community and Science: Former Summer Intern Is Investigating Plant Uptake of Contaminants on Disposal Cell Covers

  12. Landfill Cover Revegetation at the Rocky Flats Environmental Technology

    Energy Savers [EERE]

    Site | Department of Energy Landfill Cover Revegetation at the Rocky Flats Environmental Technology Site Landfill Cover Revegetation at the Rocky Flats Environmental Technology Site Landfill Cover Revegetation at the Rocky Flats Environmental Technology Site PDF icon Landfill Cover Revegetation at the Rocky Flats Environmental Technology Site More Documents & Publications Revegetation of the Rocky Flats Site Smooth Brome Monitoring at Rocky Flats-2005 Results EIS-0285-SA-134: Supplement

  13. FY 2009 Progress Report for Lightweighting Materials - Cover and Contents |

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

    Department of Energy 09 Progress Report for Lightweighting Materials - Cover and Contents FY 2009 Progress Report for Lightweighting Materials - Cover and Contents The primary Lightweight Materials activity goal is to validate a cost-effective weight reduction in total vehicle weight while maintaining safety, performance, and reliability. PDF icon cover_toc.pdf More Documents & Publications FY 2008 Progress Report for Lightweighting Materials - Cover, Title Page, and Contents WORKSHOP

  14. Monitoring the Performance of an Alternative Cover Using Caisson Lysimeters

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

    | Department of Energy Monitoring the Performance of an Alternative Cover Using Caisson Lysimeters Monitoring the Performance of an Alternative Cover Using Caisson Lysimeters Proceedings of the Waste Management 2004 Symposium. 2004, University of Arizona, Tucson, Arizona. W.J. Waugh, G.M. Smith , P. Mushovic PDF icon Monitoring the Performance of an Alternative Cover Using Caisson Lysimeters More Documents & Publications Design, Performance, and Sustainability of Engineered Covers for

  15. Covered Product Category: Uninterruptible Power Supplies (for Data Center,

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

    Computer, and Telecommunication Applications) | Department of Energy Categories » Covered Product Category: Uninterruptible Power Supplies (for Data Center, Computer, and Telecommunication Applications) Covered Product Category: Uninterruptible Power Supplies (for Data Center, Computer, and Telecommunication Applications) The Federal Energy Management Program (FEMP) provides acquisition guidance for uninterruptible power supplies (UPS), a product category covered by the ENERGY STAR program.

  16. Encapsulant Material For Solar Cell Module And Laminated Glass Applications

    DOE Patents [OSTI]

    Hanoka, Jack I.

    2000-09-05

    An encapsulant material includes a layer of metallocene polyethylene disposed between two layers of ionomer. More specifically, the layer of metallocene polyethylene is disposed adjacent a rear surface of the first ionomer layer, and a second layer of ionomer is disposed adjacent a rear surface of the layer of metallocene polyethylene. The encapsulant material can be used in solar cell module and laminated glass applications.

  17. Encapsulant Material For Solar Cell Module And Laminated Glass Applications

    DOE Patents [OSTI]

    Hanoka, Jack I.; Klemchuk, Peter P.

    2001-02-13

    An encapsulant material includes a layer of metallocene polyethylene disposed between two layers of an acid copolymer of polyethylene. More specifically, the layer of metallocene polyethylene is disposed adjacent a rear surface of the first layer of the acid copolymer of polyethylene, and a second layer of the acid copolymer of polyethlene is disposed adjacent a rear surface of the layer of metallocene polyethylene. The encapsulant material can be used in solar cell module and laminated glass applications.

  18. Combination gas producing and waste-water disposal well

    DOE Patents [OSTI]

    Malinchak, Raymond M.

    1984-01-01

    The present invention is directed to a waste-water disposal system for use in a gas recovery well penetrating a subterranean water-containing and methane gas-bearing coal formation. A cased bore hole penetrates the coal formation and extends downwardly therefrom into a further earth formation which has sufficient permeability to absorb the waste water entering the borehole from the coal formation. Pump means are disposed in the casing below the coal formation for pumping the water through a main conduit towards the water-absorbing earth formation. A barrier or water plug is disposed about the main conduit to prevent water flow through the casing except for through the main conduit. Bypass conduits disposed above the barrier communicate with the main conduit to provide an unpumped flow of water to the water-absorbing earth formation. One-way valves are in the main conduit and in the bypass conduits to provide flow of water therethrough only in the direction towards the water-absorbing earth formation.

  19. Integrated Disposal Facility FY 2012 Glass Testing Summary Report

    SciTech Connect (OSTI)

    Pierce, Eric M.; Kerisit, Sebastien N.; Krogstad, Eirik J.; Burton, Sarah D.; Bjornstad, Bruce N.; Freedman, Vicky L.; Cantrell, Kirk J.; Snyder, Michelle MV; Crum, Jarrod V.; Westsik, Joseph H.

    2013-03-29

    PNNL is conducting work to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility for Hanford immobilized low-activity waste (ILAW). Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program, PNNL is implementing a strategy, consisting of experimentation and modeling, to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. Key activities in FY12 include upgrading the STOMP/eSTOMP codes to do near-field modeling, geochemical modeling of PCT tests to determine the reaction network to be used in the STOMP codes, conducting PUF tests on selected glasses to simulate and accelerate glass weathering, developing a Monte Carlo simulation tool to predict the characteristics of the weathered glass reaction layer as a function of glass composition, and characterizing glasses and soil samples exhumed from an 8-year lysimeter test. The purpose of this report is to summarize the progress made in fiscal year (FY) 2012 and the first quarter of FY 2013 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of LAW glasses.

  20. Deep Borehole Disposal Remediation Costs for Off-Normal Outcomes

    SciTech Connect (OSTI)

    Finger, John T.; Cochran, John R.; Hardin, Ernest

    2015-08-17

    This memo describes rough-order-of-magnitude (ROM) cost estimates for a set of off-normal (accident) scenarios, as defined for two waste package emplacement method options for deep borehole disposal: drill-string and wireline. It summarizes the different scenarios and the assumptions made for each, with respect to fishing, decontamination, remediation, etc.

  1. Remote-Handled Low-Level Waste (RHLLW) Disposal Project Code of Record

    SciTech Connect (OSTI)

    S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

    2010-10-01

    The Remote-Handled Low-Level Waste Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of fiscal year 2015). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability.

  2. Alternative Landfill Cover and Monitoring Systems for Landfills in Arid Environments

    SciTech Connect (OSTI)

    S. E. Rawlinson

    2002-09-01

    In December 2000, a performance monitoring facility was constructed adjacent to the mixed waste disposal unit U-3ax/bl at the Area 3 Radioactive Waste Management Site at the Nevada Test Site. This facility consists of eight drainage lysimeters measuring 10 feet in diameter, 8 feet deep, and backfilled with native soil. The lysimeters have three different surface treatments: two were left bare, two were revegetated with native species, and two were allowed to revegetate with invader species (two are reserved for future studies). The lysimeters are instrumented with an array of soil water content and soil water potential sensors and have sealed bottoms so that any drainage can be measured. All sensors are working properly and indicate that the bare lysimeters are the wettest, as expected. The vegetated lysimeters, both seeded and those allowed to revegetate with invader species, are significantly drier than the bare cover treatments. No drainage has occurred in any of the lysimeters. The Accelerated Site Technology Deployment program under the U.S. Department of Energy's Office of Science and Technology provided the funding for this project with the objective of reducing the uncertainty associated with the performance of monolayer-evapotranspiration waste covers in arid regions such as the one deployed at U-3ax/bl.

  3. Special Analysis: Revision of Saltstone Vault 4 Disposal Limits (U)

    SciTech Connect (OSTI)

    Cook, J

    2005-05-26

    New disposal limits have been computed for Vault 4 of the Saltstone Disposal Facility based on several revisions to the models in the existing Performance Assessment and the Special Analysis issued in 2002. The most important changes are the use of a more rigorous groundwater flow and transport model, and consideration of radon emanation. Other revisions include refinement of the aquifer mesh to more accurately model the footprint of the vault, a new plutonium chemistry model accounting for the different transport properties of oxidation states III/IV and V/VI, use of variable infiltration rates to simulate degradation of the closure system, explicit calculation of gaseous releases and consideration of the effects of settlement and seismic activity on the vault structure. The disposal limits have been compared with the projected total inventory expected to be disposed in Vault 4. The resulting sum-of-fractions of the 1000-year disposal limits is 0.2, which indicates that the performance objectives and requirements of DOE 435.1 will not be exceeded. This SA has not altered the conceptual model (i.e., migration of radionuclides from the Saltstone waste form and Vault 4 to the environment via the processes of diffusion and advection) of the Saltstone PA (MMES 1992) nor has it altered the conclusions of the PA (i.e., disposal of the proposed waste in the SDF will meet DOE performance measures). Thus a PA revision is not required and this SA serves to update the disposal limits for Vault 4. In addition, projected doses have been calculated for comparison with the performance objectives laid out in 10 CFR 61. These doses are 0.05 mrem/year to a member of the public and 21.5 mrem/year to an inadvertent intruder in the resident scenario over a 10,000-year time-frame, which demonstrates that the 10 CFR 61 performance objectives will not be exceeded. This SA supplements the Saltstone PA and supersedes the two previous SAs (Cook et al. 2002; Cook and Kaplan 2003).

  4. Fuel cell system with interconnect

    SciTech Connect (OSTI)

    Goettler, Richard; Liu, Zhien

    2015-08-11

    The present invention includes a fuel cell system having a plurality of adjacent electrochemical cells formed of an anode layer, a cathode layer spaced apart from the anode layer, and an electrolyte layer disposed between the anode layer and the cathode layer. The fuel cell system also includes at least one interconnect, the interconnect being structured to conduct free electrons between adjacent electrochemical cells. Each interconnect includes a primary conductor embedded within the electrolyte layer and structured to conduct the free electrons.

  5. Fuel cell system with interconnect

    SciTech Connect (OSTI)

    Goettler, Richard; Liu, Zhien

    2015-03-10

    The present invention includes a fuel cell system having a plurality of adjacent electrochemical cells formed of an anode layer, a cathode layer spaced apart from the anode layer, and an electrolyte layer disposed between the anode layer and the cathode layer. The fuel cell system also includes at least one interconnect, the interconnect being structured to conduct free electrons between adjacent electrochemical cells. Each interconnect includes a primary conductor embedded within the electrolyte layer and structured to conduct the free electrons.

  6. Fuel cell system with interconnect

    SciTech Connect (OSTI)

    Liu, Zhien; Goettler, Richard

    2015-09-29

    The present invention includes a fuel cell system having a plurality of adjacent electrochemical cells formed of an anode layer, a cathode layer spaced apart from the anode layer, and an electrolyte layer disposed between the anode layer and the cathode layer. The fuel cell system also includes at least one interconnect, the interconnect being structured to conduct free electrons between adjacent electrochemical cells. Each interconnect includes a primary conductor embedded within the electrolyte layer and structured to conduct the free electrons.

  7. Electrically shielded enclosure with magnetically retained removable cover

    DOE Patents [OSTI]

    Rivers, Craig J.; Lee, Roanne A.; Jones, Glenn E.

    1996-01-01

    Disclosed is an electrically shielded enclosure having electrical components therein and a removable electrically shielded cover over an opening in the enclosure with a magnetic securement mechanism provided to removably secure the cover to the enclosure in a manner which will provide easy access, yet also provide an electrical seal between the cover and the enclosure capable of preventing the passage of electrical radiation through the joint between the cover and the enclosure. Magnets are provided on the enclosure peripherally around the opening and facing the cover, and a ferromagnetic surface is provided on the mating surface of the cover facing the magnets, with a continuous electrical seal provided between the magnets and the ferromagnetic surface on the cover to prevent the leakage of electromagnetic radiation therethrough. In one embodiment the electrical seal includes a flexible metal casing or surface, which is attached to the enclosure and positioned between the magnets and the ferromagnetic surface on the cover, and which is sufficiently flexible to be capable of conforming to the ferromagnetic surface to provide an electrical seal between the cover and the enclosure. In another embodiment, the electrical seal includes a metal mesh associated with the enclosure and positioned between the magnets on the enclosure and the ferromagnetic surface on the cover. The metal mesh is also capable of conforming to the surface of the ferromagnetic surface to thereby provide an electrical seal between the cover and the enclosure.

  8. Update on cavern disposal of NORM-contaminated oil field wastes.

    SciTech Connect (OSTI)

    Veil, J. A.

    1998-09-22

    Some types of oil and gas production and processing wastes contain naturally occurring radioactive material (NORM). If NORM is present at concentrations above regulatory levels in oil field waste, the waste requires special disposal practices. The existing disposal options for wastes containing NORM are limited and costly. Argonne National Laboratory has previously evaluated the feasibility, legality, risk and economics of disposing of nonhazardous oil field wastes, other than NORM waste, in salt caverns. Cavern disposal of nonhazardous oil field waste, other than NORM waste, is occurring at four Texas facilities, in several Canadian facilities, and reportedly in Europe. This paper evaluates the legality, technical feasibility, economics, and human health risk of disposing of NORM-contaminated oil field wastes in salt caverns as well. Cavern disposal of NORM waste is technically feasible and poses a very low human health risk. From a legal perspective, a review of federal regulations and regulations from several states indicated that there are no outright prohibitions against NORM disposal in salt caverns or other Class II wells, except for Louisiana which prohibits disposal of radioactive wastes or other radioactive materials in salt domes. Currently, however, only Texas and New Mexico are working on disposal cavern regulations, and no states have issued permits to allow cavern disposal of NORM waste. On the basis of the costs currently charged for cavern disposal of nonhazardous oil field waste (NOW), NORM waste disposal in caverns is likely to be cost competitive with existing NORM waste disposal methods when regulatory agencies approve the practice.

  9. Solare Cell Roof Tile And Method Of Forming Same

    DOE Patents [OSTI]

    Hanoka, Jack I. (Brookline, MA); Real, Markus (Oberberg, CH)

    1999-11-16

    A solar cell roof tile includes a front support layer, a transparent encapsulant layer, a plurality of interconnected solar cells and a backskin layer. The front support layer is formed of light transmitting material and has first and second surfaces. The transparent encapsulant layer is disposed adjacent the second surface of the front support layer. The interconnected solar cells has a first surface disposed adjacent the transparent encapsulant layer. The backskin layer has a first surface disposed adjacent a second surface of the interconnected solar cells, wherein a portion of the backskin layer wraps around and contacts the first surface of the front support layer to form the border region. A portion of the border region has an extended width. The solar cell roof tile may have stand-offs disposed on the extended width border region for providing vertical spacing with respect to an adjacent solar cell roof tile.

  10. Compliant fuel cell system

    DOE Patents [OSTI]

    Bourgeois, Richard Scott; Gudlavalleti, Sauri

    2009-12-15

    A fuel cell assembly comprising at least one metallic component, at least one ceramic component and a structure disposed between the metallic component and the ceramic component. The structure is configured to have a lower stiffness compared to at least one of the metallic component and the ceramic component, to accommodate a difference in strain between the metallic component and the ceramic component of the fuel cell assembly.

  11. Successful Opening and Disposal to-Date of Mixed CERCLA Waste at the ORR-EMWMF

    SciTech Connect (OSTI)

    Corpstein, P.; Hopper, P.; McNutt, R.

    2003-02-25

    On May 28, 2002, the Environmental Management Waste Management Facility (EMWMF) opened for operations on the Department of Energy's Oak Ridge Reservation (ORR). The EMWMF is the centerpiece in the DOE's strategy for ORR environmental cleanup. The 8+ year planned project is an on-site engineered landfill, which is accepting for disposal radioactive, hazardous, toxic and mixed wastes generated by remedial action subcontractors. The opening of the EMWMF on May 28, 2002 marked the culmination of a long development process that began in mid-1980. In late 1999 the Record of Decision was signed and a full year of design for the initial 400, 000-yd3 disposal cell began. In early 2000 Duratek Federal Services, Inc. (Federal Services) began construction. Since then, Federal Services and Bechtel Jacobs Company, LLC (BJC) have worked cooperatively to complete a required DOE readiness evaluation, develop all the Safety Authorization Basis Documentation (ASA's, SER, and UCD's) and prepare procedures and work controlling documents required to safely accept waste. This paper explains the intricacies and economics of designing and constructing the facility.

  12. Hanford Disposal Facility Expands Vertically to Make Room for More Waste

    Broader source: Energy.gov [DOE]

    RICHLAND, Wash. – EM’s Richland Operations Office (RL) and cleanup contractor Washington Closure Hanford (WCH) are working innovatively to safely expand the Environmental Restoration Disposal Facility (ERDF) by disposing additional waste on top of the current landfill.

  13. 16 TAC, part 1, chapter 3, rule 3.9 Disposal Wells | Open Energy...

    Open Energy Info (EERE)

    Disposal Wells Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: 16 TAC, part 1, chapter 3, rule 3.9 Disposal WellsLegal...

  14. Assessment of Disposal Options for DOE-Managed High-Level Radioactive...

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

    Disposal Options for DOE-Managed High-Level Radioactive Waste and Spent Nuclear Fuel Assessment of Disposal Options for DOE-Managed High-Level Radioactive Waste and Spent Nuclear ...

  15. EIS-0375: Disposal of Greater-than-Class-C Low-Level Radioactive...

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

    5: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and Department of Energy GTCC-like Waste EIS-0375: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and ...

  16. Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth...

    Office of Environmental Management (EM)

    Review of the Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant Why DOE-EM Did This Review The On-Site Waste Disposal Facility (OSWDF) is ...

  17. 42 U.S.C. 6901 - Solid Waste Disposal Act | Open Energy Information

    Open Energy Info (EERE)

    6901 - Solid Waste Disposal Act Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: 42 U.S.C. 6901 - Solid Waste Disposal ActLegal...

  18. DOE Completes Disposal Operations In Panel 5 of the WIPP Underground...

    Energy Savers [EERE]

    Disposal Operations In Panel 5 of the WIPP Underground DOE Completes Disposal Operations In Panel 5 of the WIPP Underground August 15, 2011 - 12:00pm Addthis Media Contact Deb Gill ...

  19. Low-Level Waste Disposal Facility Federal Review Group (LFRG) | Department

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

    of Energy Program Management » Compliance » Low-Level Waste Disposal Facility Federal Review Group (LFRG) Low-Level Waste Disposal Facility Federal Review Group (LFRG) The Low-Level Waste Disposal Facility Federal Review Group (LFRG) is an independent group within the Office of Environmental Management (EM) that ensures, through review, that Department of Energy (DOE) (including the National Nuclear Security Administration) radioactive waste disposal facilities are protective of the public

  20. Investigations of Dual-Purpose Canister Direct Disposal Feasibility (FY14)

    Energy Savers [EERE]

    R1 | Department of Energy Investigations of Dual-Purpose Canister Direct Disposal Feasibility (FY14) R1 Investigations of Dual-Purpose Canister Direct Disposal Feasibility (FY14) R1 Results continue to support the earlier conclusion that direct disposal of DPCs is technically feasible, at least for some DPCs, and for some disposal concepts (geologic host media). Much of the work performed has reached a point where site-specific information would be needed for further resolution. Several

  1. Format and Content Guide for DOE Low-Level Waste Disposal Facility Closure Plans

    Broader source: Energy.gov [DOE]

    Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans

  2. Report on Separate Disposal of Defense High-Level Radioactive Waste

    Broader source: Energy.gov [DOE]

    This is a report on the separate disposal of defense high-level radioactive waste and commercial nuclear waste.

  3. Acquisition Guide Chapter 17.3, Acquisition, Use, and Disposal of Real

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

    Estate | Department of Energy 3, Acquisition, Use, and Disposal of Real Estate Acquisition Guide Chapter 17.3, Acquisition, Use, and Disposal of Real Estate The Acquisition Guide Chapter 17.3, Acquisition, Use, and Disposal of Real Estate, is updated to include the involvement of Certified Realty Specialist. PDF icon PF2011-61 Acquisition Guide chapter 17.3, Acquisition, Use, and Disposal of Real Estate More Documents & Publications OPAM Policy Acquisition Guides Acquisition, Use, and

  4. Interface control document between PUREX Plant Transition and Solid Waste Disposal Division

    SciTech Connect (OSTI)

    Carlson, A.B.

    1995-09-01

    The interfacing responsibilities regarding solid waste management are described for the Solid Waste Disposal Division and the PUREX Transition Organization.

  5. Fuel cell generator

    DOE Patents [OSTI]

    Makiel, Joseph M.

    1985-01-01

    A high temperature solid electrolyte fuel cell generator comprising a housing means defining a plurality of chambers including a generator chamber and a combustion products chamber, a porous barrier separating the generator and combustion product chambers, a plurality of elongated annular fuel cells each having a closed end and an open end with the open ends disposed within the combustion product chamber, the cells extending from the open end through the porous barrier and into the generator chamber, a conduit for each cell, each conduit extending into a portion of each cell disposed within the generator chamber, each conduit having means for discharging a first gaseous reactant within each fuel cell, exhaust means for exhausting the combustion product chamber, manifolding means for supplying the first gaseous reactant to the conduits with the manifolding means disposed within the combustion product chamber between the porous barrier and the exhaust means and the manifolding means further comprising support and bypass means for providing support of the manifolding means within the housing while allowing combustion products from the first and a second gaseous reactant to flow past the manifolding means to the exhaust means, and means for flowing the second gaseous reactant into the generator chamber.

  6. River Protection Project (RPP) Tank Waste Retrieval and Disposal Mission Technical Baseline Summary Description

    SciTech Connect (OSTI)

    DOVALLE, O.R.

    1999-12-29

    This document is one of the several documents prepared by Lockheed Martin Hanford Corp. to support the U. S. Department of Energy's Tank Waste Retrieval and Disposal mission at Hanford. The Tank Waste Retrieval and Disposal mission includes the programs necessary to support tank waste retrieval; waste feed, delivery, storage, and disposal of immobilized waste; and closure of the tank farms.

  7. August 2015 Groundwater and Surface Water Sampling at the Tuba City, Arizona, Disposal Site

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Tuba City, Arizona, Disposal Site November 2015 LMS/TUB/S00815 This page intentionally left blank U.S. Department of Energy DVP-August 2015, Tuba City, Arizona, Disposal Site November 2015 RIN 15087262 Page i Contents Sampling Event Summary ...............................................................................................................1 Tuba City, Arizona, Disposal Site, Sample Location Map

  8. Remote-Handled Low Level Waste Disposal Project Alternatives Analysis

    SciTech Connect (OSTI)

    David Duncan

    2010-10-01

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  9. Waste-to-energy: Benefits beyond waste disposal

    SciTech Connect (OSTI)

    Charles, M.A.; Kiser, J.V.L. )

    1995-01-01

    More than 125 waste-to-energy plants operate in North America, providing dependable waste disposal for thousands of communities. But the benefits of waste-to-energy plants go beyond getting rid of the garbage. Here's a look at some of the economic, environmental, and societal benefits that waste-to-energy projects have brought to their communities. The reasons vary considerably as to why communities have selected waste-to-energy as a part of their waste management systems. Common on the lists in many communities are a variety of benefits beyond dependable waste disposal. A look at experiences in four communities reveals environmental, economic, energy, and societal benefits that the projects provide to the communities they serve.

  10. 1994 Characterization report for the state approved land disposal site

    SciTech Connect (OSTI)

    Swanson, L.C.

    1994-09-19

    This report summarizes the results of characterization activities at the proposed state-approved land disposal site (SALDS); it updates the original characterization report with studies completed since the first characterization report. The initial characterization report discusses studies from two characterization boreholes, 699-48-77A and 699-48-77B. This revision includes data from implementation of the Groundwater Monitoring Plan and the Aquifer Test Plan. The primary sources of data are two down-gradient groundwater monitoring wells, 699-48-77C and 699-48-77D, and aquifer testing of three zones in well 699-48-77C. The SALDS is located on the Hanford Site, approximately 183 m north of the 200 West Area on the north side of the 200 Areas Plateau. The SALDS is an infiltration basin proposed for disposal of treated effluents from the 200 Areas of Hanford.

  11. Current and proposed regulations for salt water disposal wells

    SciTech Connect (OSTI)

    Moody, T.

    1994-09-01

    In recent years, all aspects of hydrocarbon exploration and production (E & P) activities have drawn closer scrutiny in terms of existing and potential impairment of the environment. In addition to drilling, production, and transportation activities, the USEPA has focused on the nature of E & P generated wastes, and the subsequent management of both hazardous and nonhazardous E & P wastes. Approximately 98% of all of the volume of wastes generated by E & P activities is salt water associated with the recovery of hydrocarbons. By far the majority of this waste is disposed of in class II salt water disposal wells. Due to the tremendous volume of salt water generated, the USEPA continues to reevaluate the federal class II salt water injection well program, offering comments, revising its interpretation of existing regulations, and promulgating new regulations. The purpose of the presentation will be to provide a review of existing class II federal regulations, and to provide an overview of potential or newly promulgated regulations.

  12. DOE Proposes Requirement for Certification of Admissibility for Covered

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

    Products and Equipment | Department of Energy Proposes Requirement for Certification of Admissibility for Covered Products and Equipment DOE Proposes Requirement for Certification of Admissibility for Covered Products and Equipment February 22, 2016 - 6:26pm Addthis DOE has issued a Notice of Proposed Rulemaking (NOPR) in which it proposes to require that a person importing into the United States any covered product or equipment subject to an applicable energy conservation standard provide,

  13. Integrated Used Nuclear Fuel Storage, Transportation, and Disposal Canister

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

    System - Energy Innovation Portal Storage Energy Storage Electricity Transmission Electricity Transmission Advanced Materials Advanced Materials Find More Like This Return to Search Integrated Used Nuclear Fuel Storage, Transportation, and Disposal Canister System Oak Ridge National Laboratory Contact ORNL About This Technology Publications: PDF Document Publication 11-G00239_ID2603 (2).pdf (847 KB) Technology Marketing Summary Researchers at ORNL have developed an integrated system that

  14. Special Analysis for the Disposal of the Lawrence Livermore National

    Office of Scientific and Technical Information (OSTI)

    Laboratory EnergyX Macroencapsulated Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada (Program Document) | SciTech Connect EnergyX Macroencapsulated Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada Citation Details In-Document Search Title: Special Analysis for the Disposal of the Lawrence Livermore National Laboratory EnergyX Macroencapsulated Waste Stream at the

  15. Special Analysis for the Disposal of the Lawrence Livermore National

    Office of Scientific and Technical Information (OSTI)

    Laboratory EnergyX Macroencapsulated Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada (Program Document) | SciTech Connect EnergyX Macroencapsulated Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada Citation Details In-Document Search Title: Special Analysis for the Disposal of the Lawrence Livermore National Laboratory EnergyX Macroencapsulated Waste Stream at the

  16. Special Analysis for the Disposal of the Lawrence Livermore National

    Office of Scientific and Technical Information (OSTI)

    Laboratory Low Activity Beta/Gamma Sources Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada (Program Document) | SciTech Connect Low Activity Beta/Gamma Sources Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada Citation Details In-Document Search Title: Special Analysis for the Disposal of the Lawrence Livermore National Laboratory Low Activity Beta/Gamma Sources Waste

  17. Special Analysis for the Disposal of the Lawrence Livermore National

    Office of Scientific and Technical Information (OSTI)

    Laboratory Low Activity Beta/Gamma Sources Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada (Program Document) | SciTech Connect Low Activity Beta/Gamma Sources Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada Citation Details In-Document Search Title: Special Analysis for the Disposal of the Lawrence Livermore National Laboratory Low Activity Beta/Gamma Sources Waste

  18. Special Analysis for the Disposal of the Neutron Products Incorporated

    Office of Scientific and Technical Information (OSTI)

    Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada (Technical Report) | SciTech Connect Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada Citation Details In-Document Search Title: Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste

  19. Special Analysis for the Disposal of the Idaho National Laboratory

    Office of Scientific and Technical Information (OSTI)

    Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada (Technical Report) | SciTech Connect Idaho National Laboratory Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada Citation Details In-Document Search Title: Special Analysis for the Disposal of the Idaho

  20. Anaerobic digestion as a waste disposal option for American Samoa

    SciTech Connect (OSTI)

    Rivard, C

    1993-01-01

    Tuna sludge and municipal solid waste (MSW) generated on Tutuila Island, American Samoa, represent an ongoing disposal problem as well as an emerging opportunity for use in renewable fuel production. This research project focuses on the biological conversion of the organic fraction of these wastes to useful products including methane and fertilizer-grade residue through anaerobic high solids digestion. In this preliminary study, the anaerobic bioconversion of tuna sludge with MSW appears promising.

  1. CLASSIFICATION OF THE MGR NON-FUEL COMPONENTS DISPOSAL CONTAINER

    SciTech Connect (OSTI)

    J.A. Ziegler

    1999-08-31

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) non-fuel components disposal container system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

  2. Special Analysis for the Disposal of the Idaho National Laboratory

    Office of Scientific and Technical Information (OSTI)

    Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada (Technical Report) | SciTech Connect Special Analysis for the Disposal of the Idaho National Laboratory Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada Citation Details In-Document Search Title: Special

  3. Subseabed Disposal Program. Annual report, January-December 1978

    SciTech Connect (OSTI)

    Talbert, D.M.

    1980-02-01

    This is the fifth annual report describing the progress and evaluating the status of the Subseabed Disposal Program (SDP), which was begun in June 1973. The program was initiated by Sandia Laboratories to explore the utility of stable, uniform, and relatively unproductive areas of the world as possible repositories for high-level nuclear wastes. The program, now international in scope, is currently focused on the stable submarine geologic formations under the deep oceans.

  4. FY 2009 Progress Report for Lightweighting Materials - Cover...

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

    FY 2009 Progress Report for Lightweighting Materials - Cover and Contents The primary Lightweight Materials activity goal is to validate a cost-effective weight reduction in total ...

  5. Covered Product Category: Residential Heat Pump Water Heaters...

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

    Heat Pump Water Heaters Covered Product Category: Residential Heat Pump Water Heaters The Federal Energy Management Program (FEMP) provides acquisition guidance and Federal ...

  6. Covered Product Category: Water-Cooled Electric Chillers | Department...

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

    Covered Product Category: Water-Cooled Electric Chillers The Federal Energy Management Program (FEMP) provides acquisition guidance and Federal efficiency requirements for water-co...

  7. Covered Product Category: Water-Cooled Ice Machines | Department...

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

    Covered Product Category: Water-Cooled Ice Machines The Federal Energy Management Program (FEMP) provides acquisition guidance and federal efficiency requirements for water-cooled ...

  8. USGS-Land Cover Institute (LCI) | Open Energy Information

    Open Energy Info (EERE)

    USGS currently houses the institute at the Center for Earth Resources Observation and Science (EROS) in Sioux Falls, South Dakota. The LCI will address land cover topics from...

  9. Microsoft Word - DOE_Staffing_Study_Cover.doc | Department of...

    Office of Environmental Management (EM)

    Word - DOEStaffingStudyCover.doc More Documents & Publications 2010 DOE Strategic Sustainability Performance Plan - Report to the White House Council on Environmental...

  10. "List of Covered Electric Utilities" under the Public Utility...

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

    6 Revised "List of Covered Electric Utilities" under the Public Utility Regulatory Policies Act of 1978 (PURPA) - 2006 Revised Under Title I of the Public Utility Regulatory...

  11. Providing Diurnal Sky Cover Data at ARM Sites (Technical Report...

    Office of Scientific and Technical Information (OSTI)

    Other data products discussed in this report include the sky cover derived from ASIVA's visible channel and precipitable water vapor, cloud temperature (both brightness and color), ...

  12. FY 2008 Progress Report for Lightweighting Materials - Cover...

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

    FY 2008 Progress Report for Lightweighting Materials - Cover, Title Page, and Contents Lightweighting Materials focuses on the development and validation of advanced materials and ...

  13. "List of Covered Electric Utilities" under the Public Utility...

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

    "List of Covered Electric Utilities" under the Public Utility Regulatory Policies Act of 1978 (PURPA) - 2009 Under Title I, Sec. 102(c) of the Public Utility Regulatory Policies ...

  14. Covered Product Category: Air-Cooled Ice Machines

    Broader source: Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) provides acquisition guidance for air-cooled ice machines, which are covered by the ENERGY STAR program.

  15. Proceedings of the 1981 subseabed disposal program. Annual workshop

    SciTech Connect (OSTI)

    Not Available

    1982-01-01

    The 1981 Annual Workshop was the twelfth meeting of the principal investigators and program management personnel participating in the Subseabed Disposal Program (SDP). The first workshop was held in June 1973, to address the development of a program (initially known as Ocean Basin Floors Program) to assess the deep sea disposal of nuclear wastes. Workshops were held semi-annually until late 1977. Since November 1977, the workshops have been conducted following the end of each fiscal year so that the program participants could review and critique the total scope of work. This volume contains a synopsis, as given by each Technical Program Coordinator, abstracts of each of the talks, and copies of the visual materials, as presented by each of the principal investigators, for each of the technical elements of the SDP for the fiscal year 1981. The talks were grouped under the following categories; general topics; site studies; thermal response studies; emplacement studies; systems analysis; chemical response studies; biological oceanography studies; physical oceanographic studies; instrumentation development; transportation studies; social environment; and international seabed disposal.

  16. The NUMO Strategy for HLW and TRU Waste Disposal

    SciTech Connect (OSTI)

    Kitayama, K.; Oda, Y. [Nuclear Waste Management Organization of Japan (NUMO), Tokyo (Japan)

    2008-07-01

    Shortly after the Nuclear Waste Management Organization of Japan (NUMO) was established, we initiated an open call to all municipalities, requesting volunteers to host a repository for vitrified HLW. The first volunteer applied for a preliminary literature survey phase last January but, unfortunately, it withdrew the application in April. This failure provided an invaluable lesson for both the relevant authorities and NUMO; subsequently the Atomic Energy Commission of Japan and associated organizations are examining a support plan to back up NUMO's open solicitation. On another front, a recent amendment of 'The Specified Radioactive Waste Final Disposal Act' also allocates specific 'TRU' waste for deep geological disposal, requiring a demonstration of safety to a similar level as that for HLW. To implement the radioactive waste disposal project, NUMO has developed a methodology appropriate to our specific boundary conditions - the NUMO Structured Approach. This takes into account, in particular, our need to balance competing goals, such as operational safety, post-closure safety and cost, during repository tailoring to specific sites. The most important challenge for NUMO is, however, to attract volunteers. We believe that our open and structured R and D program is critical to demonstrate technical competence which, in turn, enhances the credibility of our various public relations activities. (authors)

  17. Disposal of Draeger Tubes at Savannah River Site

    SciTech Connect (OSTI)

    Malik, N.P.

    2000-10-13

    The Savannah River Site (SRS) is a Department of Energy (DOE) facility located in Aiken, South Carolina that is operated by the Westinghouse Savannah River Company (WSRC). At SRS Draeger tubes are used to identify the amount and type of a particular chemical constituent in the atmosphere. Draeger tubes rely on a chemical reaction to identify the nature and type of a particular chemical constituent in the atmosphere. Disposal practices for these tubes were identified by performing a hazardous waste evaluation per the Resource Conservation and Recovery Act (RCRA). Additional investigations were conducted to provide guidance for their safe handling, storage and disposal. A list of Draeger tubes commonly used at SRS was first evaluated to determine if they contained any material that could render them as a RCRA hazardous waste. Disposal techniques for Draeger tubes that contained any of the toxic contaminants listed in South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79. 261.24 (b) and/or contained an acid in the liquid form were addressed.

  18. A critical comparison of ten disposable cup LCAs

    SciTech Connect (OSTI)

    Harst, Eugenie van der, E-mail: eugenie.vanderharst@wur.nl [Environmental Systems Analysis Group, Wageningen University, P.O. Box 47, NL-6700 AA Wageningen (Netherlands); Potting, José, E-mail: jose.potting@wur.nl [Environmental Systems Analysis Group, Wageningen University, P.O. Box 47, NL-6700 AA Wageningen (Netherlands) [Environmental Systems Analysis Group, Wageningen University, P.O. Box 47, NL-6700 AA Wageningen (Netherlands); Environmental Strategies Research (fms), KTH Royal Institute of Technology, SE-110 44 Stockholm (Sweden)

    2013-11-15

    Disposable cups can be made from conventional petro-plastics, bioplastics, or paperboard (coated with petro-plastics or bioplastics). This study compared ten life cycle assessment (LCA) studies of disposable cups with the aim to evaluate the robustness of their results. The selected studies have only one impact category in common, namely climate change with global warming potential (GWP) as its category indicator. Quantitative GWP results of the studies were closer examined. GWPs within and across each study show none of the cup materials to be consistently better than the others. Comparison of the absolute GWPs (after correction for the cup volume) also shows no consistent better or worse cup material. An evaluation of the methodological choices and the data sets used in the studies revealed their influence on the GWP. The differences in GWP can be attributed to a multitude of factors, i.e., cup material and weight, production processes, waste processes, allocation options, and data used. These factors basically represent different types of uncertainty. Sensitivity and scenario analyses provided only the influence of one factor at once. A systematic and simultaneous use of sensitivity and scenario analyses could, in a next research, result in more robust outcomes. -- Highlights: • Conflicting results from life cycle assessment (LCA) on disposable cups • GWP results of LCAs did not point to a best or worst cup material. • Differences in GWP results are due to methodological choices and data sets used. • Standardized LCA: transparency of LCA studies, but still different in approaches.

  19. Pyramiding tumuli waste disposal site and method of construction thereof

    DOE Patents [OSTI]

    Golden, Martin P.

    1989-01-01

    An improved waste disposal site for the above-ground disposal of low-level nuclear waste as disclosed herein. The disposal site is formed from at least three individual waste-containing tumuli, wherein each tumuli includes a central raised portion bordered by a sloping side portion. Two of the tumuli are constructed at ground level with adjoining side portions, and a third above-ground tumulus is constructed over the mutually adjoining side portions of the ground-level tumuli. Both the floor and the roof of each tumulus includes a layer of water-shedding material such as compacted clay, and the clay layer in the roofs of the two ground-level tumuli form the compacted clay layer of the floor of the third above-ground tumulus. Each tumulus further includes a shield wall, preferably formed from a solid array of low-level handleable nuclear wate packages. The provision of such a shield wall protects workers from potentially harmful radiation when higher-level, non-handleable packages of nuclear waste are stacked in the center of the tumulus.

  20. The Remote Handled Immobilization Low Activity Waste Disposal Facility Environmental Permits & Approval Plan

    SciTech Connect (OSTI)

    DEFFENBAUGH, M.L.

    2000-08-01

    The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement or record of decision shall result in shutdown of an operational disposal facility or disapproval to initiate construction of a new facility.''

  1. Integrated Disposal Facility FY2010 Glass Testing Summary Report

    SciTech Connect (OSTI)

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Serne, R Jeffrey; Mattigod, Shas V.

    2010-09-30

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 × 105 m3 of glass (Puigh 1999). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 0.89 × 1018 Bq total activity) of long-lived radionuclides, principally 99Tc (t1/2 = 2.1 × 105), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessement (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2010 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses. The emphasis in FY2010 was the completing an evaluation of the most sensitive kinetic rate law parameters used to predict glass weathering, documented in Bacon and Pierce (2010), and transitioning from the use of the Subsurface Transport Over Reactive Multi-phases to Subsurface Transport Over Multiple Phases computer code for near-field calculations. The FY2010 activities also consisted of developing a Monte Carlo and Geochemical Modeling framework that links glass composition to alteration phase formation by 1) determining the structure of unreacted and reacted glasses for use as input information into Monte Carlo calculations, 2) compiling the solution data and alteration phases identified from accelerated weathering tests conducted with ILAW glass by PNNL and Viteous State Laboratory/Catholic University of America as well as other literature sources for use in geochemical modeling calculations, and 3) conducting several initial calculations on glasses that contain the four major components of ILAW-Al2O3, B2O3, Na2O, and SiO2.

  2. Used Fuel Disposal in Crystalline Rocks: Status and FY14 Progress |

    Energy Savers [EERE]

    Department of Energy Disposal in Crystalline Rocks: Status and FY14 Progress Used Fuel Disposal in Crystalline Rocks: Status and FY14 Progress The objective of the Crystalline Disposal R&D work is to advance our understanding of long-term disposal of used fuel in crystalline rocks and to develop necessary experimental and computational capabilities to evaluate various disposal concepts in such media. The major accomplishments during the year include: 1) R&D plan was developed for

  3. Covered Product Category: Residential Electric Resistance Water Heaters |

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

    Department of Energy Covered Product Category: Residential Electric Resistance Water Heaters Covered Product Category: Residential Electric Resistance Water Heaters The Federal Energy Management Program (FEMP) sets federal efficiency requirements and provides acquisition guidance for residential electric resistance water heaters. Federal laws and requirements mandate that agencies meet these efficiency requirements in all procurement and acquisition actions that are not specifically exempted

  4. Summary - Disposal Practices at the Savannah River Site

    Office of Environmental Management (EM)

    isolated in place with grout and all wastes will be covered with a cap that includes a hydraulic barrier to limit precipitation infiltration. The objective of this review was to...

  5. 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    SciTech Connect (OSTI)

    2014-03-01

    This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) in 2013 at 19 uranium mill tailings disposal sites established under Title I of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978.1 These activities verified that the UMTRCA Title I disposal sites remain in compliance with license requirements. DOE operates 18 UMTRCA Title I sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) in accordance with Title 10 Code of Federal Regulations Part 40.27 (10 CFR 40.27). As required under the general license, a long-term surveillance plan (LTSP) for each site was prepared by DOE and accepted by NRC. The Grand Junction, Colorado, Disposal Site, one of the 19 Title I sites, will not be included under the general license until the open, operating portion of the cell is closed. The open portion will be closed either when it is filled or in 2023. This site is inspected in accordance with an interim LTSP. Long-term surveillance and maintenance services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective actions; and performing administrative, records, stakeholder relations, and other regulatory stewardship functions. Annual site inspections and monitoring are conducted in accordance with site-specific LTSPs and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up or contingency inspections, or corrective action in accordance with the LTSP. LTSPs and site compliance reports are available on the Internet at http://www.lm.doe.gov/.

  6. Chemical and biological warfare: Protection, decontamination, and disposal. (Latest citations from the NTIS bibliographic database). Published Search

    SciTech Connect (OSTI)

    1997-11-01

    The bibliography contains citations concerning the means to defend against chemical and biological agents used in military operations, and to eliminate the effects of such agents on personnel, equipment, and grounds. Protection is accomplished through protective clothing and masks, and in buildings and shelters through filtration. Elimination of effects includes decontamination and removal of the agents from clothing, equipment, buildings, grounds, and water, using chemical deactivation, incineration, and controlled disposal of material in injection wells and ocean dumping. Other Published Searches in this series cover chemical warfare detection; defoliants; general studies; biochemistry and therapy; and biology, chemistry, and toxicology associated with chemical warfare agents.(Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  7. Chemical and biological warfare: Protection, decontamination, and disposal. (Latest citations from the NTIS bibliographic database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1994-07-01

    The bibliography contains citations concerning the means to defend against chemical and biological agents used in military operations, and to eliminate the effects of such agents on personnel, equipment, and grounds. Protection is accomplished through protective clothing and masks, and in buildings and shelters through filtration. Elimination of effects includes decontamination and removal of the agents from clothing, equipment, buildings, grounds, and water, using chemical deactivation, incineration, and controlled disposal of material in injection wells and ocean dumping. Other Published Searches in this series cover chemical warfare detection; defoliants; general studies; biochemistry and therapy; and biology, chemistry, and toxicology associated with chemical warfare agents. (Contains 250 citations and includes a subject term index and title list.)

  8. Compact disposal of high-energy electron beams using passive or laser-driven plasma decelerating stage

    SciTech Connect (OSTI)

    Bonatto, A.; Schroeder, C.B.; Vay, J.-L.; Geddes, C.R.; Benedetti, C.; Esarey and, E.; Leemans, W.P.

    2014-07-13

    A plasma decelerating stage is investigated as a compact alternative for the disposal of high-energy beams (beam dumps). This could benefit the design of laser-driven plasma accelerator (LPA) applications that require transportability and or high-repetition-rate operation regimes. Passive and laser-driven (active) plasma-based beam dumps are studied analytically and with particle-in-cell (PIC) simulations in a 1D geometry. Analytical estimates for the beam energy loss are compared to and extended by the PIC simulations, showing that with the proposed schemes a beam can be efficiently decelerated in a centimeter-scale distance.

  9. Evaluation of Low-Level Waste Disposal Receipt Data for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011

    SciTech Connect (OSTI)

    French, Sean B. [Los Alamos National Laboratory; Shuman, Robert [WPS: WASTE PROJECTS AND SERVICES

    2012-04-17

    The Los Alamos National Laboratory (LANL or the Laboratory) generates radioactive waste as a result of various activities. Operational or institutional waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D and D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. U.S. Department of Energy (DOE) Order 435.1 (DOE, 2001) requires that radioactive waste be managed in a manner that protects public health and safety, and the environment. To comply with this order, DOE field sites must prepare and maintain site-specific radiological performance assessments for LLW disposal facilities that accept waste after September 26, 1988. Furthermore, sites are required to conduct composite analyses that account for the cumulative impacts of all waste that has been (or will be) disposed of at the facilities and other sources of radioactive material that may interact with the facilities. Revision 4 of the Area G performance assessment and composite analysis was issued in 2008 (LANL, 2008). These analyses estimate rates of radionuclide release from the waste disposed of at the facility, simulate the movement of radionuclides through the environment, and project potential radiation doses to humans for several on-site and off-site exposure scenarios. The assessments are based on existing site and disposal facility data and on assumptions about future rates and methods of waste disposal. The accuracy of the performance assessment and composite analysis depends upon the validity of the data used and assumptions made in conducting the analyses. If changes in these data and assumptions are significant, they may invalidate or call into question certain aspects of the analyses. For example, if the volumes and activities of waste disposed of during the remainder of the disposal facility's lifetime differ significantly from those projected, the doses projected by the analyses may no longer apply. DOE field sites are required to implement a performance assessment and composite analysis maintenance program. The purpose of this program is to ensure the continued applicability of the analyses through incremental improvement of the level of understanding of the disposal site and facility. Site personnel are required to conduct field and experimental work to reduce the uncertainty in the data and models used in the assessments. Furthermore, they are required to conduct periodic reviews of waste receipts, comparing them to projected waste disposal rates. The radiological inventory for Area G was updated in conjunction with Revision 4 of the performance assessment and composite analysis (Shuman, 2008). That effort used disposal records and other sources of information to estimate the quantities of radioactive waste that have been disposed of at Area G from 1959, the year the facility started receiving waste on a routine basis, through 2007. It also estimated the quantities of LLW that will require disposal from 2008 through 2044, the year in which it is assumed that disposal operations at Area G will cease. This report documents the fourth review of Area G disposal receipts since the inventory was updated and examines information for waste placed in the ground during fiscal years (FY) 2008 through 2011. The primary objective of the disposal receipt review is to ensure that the future waste inventory projections developed for the performance assessment and composite analysis are consistent with the actual types and quantities of waste being disposed of at Area G. Toward this end, the disposal data that are the subject of this review are used to update the future waste inventory projections for the disposal facility. These projections are compared to the future inventory projections that were develope

  10. Eolian cover sands: a sedimentologic model and paleoenvironmental implications

    SciTech Connect (OSTI)

    Lea, P.D.

    1985-01-01

    In periglacial areas, accumulations of eolian sand commonly form low-relief blankets without well-developed dunes. Internally, these sandsheet deposits exhibit subhorizontal lamination rather than high-angle cross-bedding. Such cover sands of late-Pleistocene age mantle extensive areas in northern Europe, but have been reported more rarely from North America. The processes by which cover sands, as opposed to dunes, accumulate have not yet been determined conclusively. Wind ripples and sand dunes do not form a continuum; flow separation and avalanching and negligible in the former and vital in the latter. Accretion of a sand patch into a mound sufficient to cause flow separation and dune growth requires a consistently available supply of loose sand. In cover-sand areas, sand may be immobilized prior to dune development by several factors: (1) a sparse vegetation cover, (2) moist ground conditions, (3) snow cover, and (4) a shallow permafrost table and/or an ice-cemented active layer. Detailed sedimentologic studies may allow discrimination among these various controls. The importance of the individual controlling factors can vary seasonally in a given deposit, as well as between deposits in different paleogeographic settings. However, all factors imply more mesic conditions than those associated with many dune deposits. The association of cover sands with paraboloid dunes is also consistent with somewhat moist conditions. The relatively mesic nature of cover sands controls their Pleistocene distribution; they become decreasingly important relative to dunes in maritime-to-continental transects across Alaska and northern Europe.

  11. Deep borehole disposal of high-level radioactive waste.

    SciTech Connect (OSTI)

    Stein, Joshua S.; Freeze, Geoffrey A.; Brady, Patrick Vane; Swift, Peter N.; Rechard, Robert Paul; Arnold, Bill Walter; Kanney, Joseph F.; Bauer, Stephen J.

    2009-07-01

    Preliminary evaluation of deep borehole disposal of high-level radioactive waste and spent nuclear fuel indicates the potential for excellent long-term safety performance at costs competitive with mined repositories. Significant fluid flow through basement rock is prevented, in part, by low permeabilities, poorly connected transport pathways, and overburden self-sealing. Deep fluids also resist vertical movement because they are density stratified. Thermal hydrologic calculations estimate the thermal pulse from emplaced waste to be small (less than 20 C at 10 meters from the borehole, for less than a few hundred years), and to result in maximum total vertical fluid movement of {approx}100 m. Reducing conditions will sharply limit solubilities of most dose-critical radionuclides at depth, and high ionic strengths of deep fluids will prevent colloidal transport. For the bounding analysis of this report, waste is envisioned to be emplaced as fuel assemblies stacked inside drill casing that are lowered, and emplaced using off-the-shelf oilfield and geothermal drilling techniques, into the lower 1-2 km portion of a vertical borehole {approx}45 cm in diameter and 3-5 km deep, followed by borehole sealing. Deep borehole disposal of radioactive waste in the United States would require modifications to the Nuclear Waste Policy Act and to applicable regulatory standards for long-term performance set by the US Environmental Protection Agency (40 CFR part 191) and US Nuclear Regulatory Commission (10 CFR part 60). The performance analysis described here is based on the assumption that long-term standards for deep borehole disposal would be identical in the key regards to those prescribed for existing repositories (40 CFR part 197 and 10 CFR part 63).

  12. Module level solutions to solar cell polarization

    DOE Patents [OSTI]

    Xavier, Grace , Li; Bo

    2012-05-29

    A solar cell module includes interconnected solar cells, a transparent cover over the front sides of the solar cells, and a backsheet on the backsides of the solar cells. The solar cell module includes an electrical insulator between the transparent cover and the front sides of the solar cells. An encapsulant protectively packages the solar cells. To prevent polarization, the insulator has resistance suitable to prevent charge from leaking from the front sides of the solar cells to other portions of the solar cell module by way of the transparent cover. The insulator may be attached (e.g., by coating) directly on an underside of the transparent cover or be a separate layer formed between layers of the encapsulant. The solar cells may be back junction solar cells.

  13. Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

    SciTech Connect (OSTI)

    Armstrong, D.L.

    1994-08-01

    This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment.

  14. SENSITIVITY ANALYSIS FOR SALTSTONE DISPOSAL UNIT COLUMN DEGRADATION ANALYSES

    SciTech Connect (OSTI)

    Flach, G.

    2014-10-28

    PORFLOW related analyses supporting a Sensitivity Analysis for Saltstone Disposal Unit (SDU) column degradation were performed. Previous analyses, Flach and Taylor 2014, used a model in which the SDU columns degraded in a piecewise manner from the top and bottom simultaneously. The current analyses employs a model in which all pieces of the column degrade at the same time. Information was extracted from the analyses which may be useful in determining the distribution of Tc-99 in the various SDUs throughout time and in determining flow balances for the SDUs.

  15. Disposal of oil field wastes and NORM wastes into salt caverns.

    SciTech Connect (OSTI)

    Veil, J. A.

    1999-01-27

    Salt caverns can be formed through solution mining in the bedded or domal salt formations that are found in many states. Salt caverns have traditionally been used for hydrocarbon storage, but caverns have also been used to dispose of some types of wastes. This paper provides an overview of several years of research by Argonne National Laboratory on the feasibility and legality of using salt caverns for disposing of nonhazardous oil field wastes (NOW) and naturally occurring radioactive materials (NORM), the risk to human populations from this disposal method, and the cost of cavern disposal. Costs are compared between the four operating US disposal caverns and other commercial disposal options located in the same geographic area as the caverns. Argonne's research indicates that disposal of NOW into salt caverns is feasible and, in most cases, would not be prohibited by state agencies (although those agencies may need to revise their wastes management regulations). A risk analysis of several cavern leakage scenarios suggests that the risk from cavern disposal of NOW and NORM wastes is below accepted safe risk thresholds. Disposal caverns are economically competitive with other disposal options.

  16. The residuals analysis project: Evaluating disposal options for treated mixed low-level waste

    SciTech Connect (OSTI)

    Waters, R.D.; Gruebel, M.M.; Case, J.T.; Letourneau, M.J.

    1997-03-01

    For almost four years, the U.S. Department of Energy (DOE) through its Federal Facility Compliance Act Disposal Workgroup has been working with state regulators and governors` offices to develop an acceptable configuration for disposal of its mixed low-level waste (MLLW). These interactions have resulted in screening the universe of potential disposal sites from 49 to 15 and conducting ``performance evaluations`` for those fifteen sites to estimate their technical capabilities for disposal of MLLW. In the residuals analysis project, we estimated the volume of DOE`s MLLW that will require disposal after treatment and the concentrations of radionuclides in the treated waste. We then compared the radionuclide concentrations with the disposal limits determined in the performance evaluation project for each of the fifteen sites. The results are a scoping-level estimate of the required volumetric capacity for MLLW disposal and the identification of waste streams that may pose problems for disposal based on current treatment plans. The analysis provides technical information for continued discussions between the DOE and affected States about disposal of MLLW and systematic input to waste treatment developers on disposal issues.

  17. DOE/WIPP 02-3196 - Waste Isolation Pilot Plant Initial Report for PCB Disposal Authorization, March 19, 2002

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

    2-3196 Waste Isolation Pilot Plant Initial Report for PCB Disposal Authorization (40 CFR § 761.75[c]) March 19, 2002 Waste Isolation Pilot Plant Initial Report for PCB Disposal Authorization DOE/WIPP 02-3196 TABLE OF CONTENTS 1.0 INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 LOCATION OF THE DISPOSAL FACILITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3.0 DETAILED DESCRIPTION OF THE DISPOSAL

  18. Disposal of NORM-Contaminated Oil Field Wastes in Salt Caverns

    SciTech Connect (OSTI)

    Blunt, D.L.; Elcock, D.; Smith, K.P.; Tomasko, D.; Viel, J.A.; and Williams, G.P.

    1999-01-21

    In 1995, the U.S. Department of Energy (DOE), Office of Fossil Energy, asked Argonne National Laboratory (Argonne) to conduct a preliminary technical and legal evaluation of disposing of nonhazardous oil field waste (NOW) into salt caverns. That study concluded that disposal of NOW into salt caverns is feasible and legal. If caverns are sited and designed well, operated carefully, closed properly, and monitored routinely, they can be a suitable means of disposing of NOW (Veil et al. 1996). Considering these findings and the increased U.S. interest in using salt caverns for NOW disposal, the Office of Fossil Energy asked Argonne to conduct further research on the cost of cavern disposal compared with the cost of more traditional NOW disposal methods and on preliminary identification and investigation of the risks associated with such disposal. The cost study (Veil 1997) found that disposal costs at the four permitted disposal caverns in the United States were comparable to or lower than the costs of other disposal facilities in the same geographic area. The risk study (Tomasko et al. 1997) estimated that both cancer and noncancer human health risks from drinking water that had been contaminated by releases of cavern contents were significantly lower than the accepted risk thresholds. Since 1992, DOE has funded Argonne to conduct a series of studies evaluating issues related to management and disposal of oil field wastes contaminated with naturally occurring radioactive material (NORM). Included among these studies were radiological dose assessments of several different NORM disposal options (Smith et al. 1996). In 1997, DOE asked Argonne to conduct additional analyses on waste disposal in salt caverns, except that this time the wastes to be evaluated would be those types of oil field wastes that are contaminated by NORM. This report describes these analyses. Throughout the remainder of this report, the term ''NORM waste'' is used to mean ''oil field waste contaminated by NORM''.

  19. Innovative permeable cover system to reduce risks at a chemical munitions burial site

    SciTech Connect (OSTI)

    Powels, C.C.; Bon, I.; Okusu, N.M.

    1997-12-31

    An innovative permeable sand cover with various integrated systems has been designed to contain and treat the Old O-Field chemical munitions landfill at Aberdeen Proving Ground, Maryland. The 18,200 m{sup 2} (4.5 acre) landfill was used from the mid 1930s to the mid 1950s for the disposal of chemical, incendiary, and explosive munitions from domestic and foreign origins, together with contaminated wastes associated with the development and production of chemical warfare agents (CWA). The site is suspected to be contaminated with white phosphorous (WP) (which when dry, spontaneously burns when exposed to air), shock sensitive picric acid fuses and has the potential to contain large quantities of CWA-filled munitions. Historically, one to three explosions or fires occurred per ten-year period at the landfill. Such events have the potential to cause a CWA release to the environment, which could potentially affect densely populated areas. Recovery and decontamination projects conducted at the site in the late 1940s and early 1950s used large amounts of decontamination chemicals (containing solvents) and fuels which further contaminated the area. The groundwater downgradient of the landfill is contaminated with volatile organic compounds, metals, explosives and CWA degradation compounds and is currently being contained by a groundwater extraction and treatment system. This report describes a remedial action program for the site.

  20. Solar cell with silicon oxynitride dielectric layer

    DOE Patents [OSTI]

    Shepherd, Michael; Smith, David D

    2015-04-28

    Solar cells with silicon oxynitride dielectric layers and methods of forming silicon oxynitride dielectric layers for solar cell fabrication are described. For example, an emitter region of a solar cell includes a portion of a substrate having a back surface opposite a light receiving surface. A silicon oxynitride (SiO.sub.xN.sub.y, 0disposed on the back surface of the portion of the substrate. A semiconductor layer is disposed on the silicon oxynitride dielectric layer.