National Library of Energy BETA

Sample records for bearing waste sbw

  1. Feasibility Study for Vitrification of Sodium-Bearing Waste

    SciTech Connect (OSTI)

    J. J. Quigley; B. D. Raivo; S. O. Bates; S. M. Berry; D. N. Nishioka; P. J. Bunnell

    2000-09-01

    Treatment of sodium-bearing waste (SBW) at the Idaho Nuclear Technology and Engineering Center (INTEC) within the Idaho National Engineering and Environmental Laboratory is mandated under a Settlement Agreement between the Department of Energy and the State of Idaho. One of the requirements of the Settlement Agreement is the complete calcination (i.e., treatment) of all SBW by December 31, 2012. One of the proposed options for treatment of SBW is vitrification. This study will examine the viability of SBW vitrification. This study describes the process and facilities to treat the SBW, from beginning waste input from INTEC Tank Farm to the final waste forms. Schedules and cost estimates for construction and operation of a Vitrification Facility are included. The study includes a facility layout with drawings, process description and flow diagrams, and preliminary equipment requirements and layouts.

  2. Feed Composition for Sodium-Bearing Waste Treatment Process

    SciTech Connect (OSTI)

    Barnes, C.M.

    2000-10-30

    Treatment of sodium-bearing waste (SBW) at the Idaho Nuclear Technology and Engineering Center (INTEC) within the Idaho National Engineering and Environmental Laboratory is mandated by a Settlement Agreement between the Department of Energy and the State of Idaho. One of the requirements of the Settlement Agreement is to complete treatment of SBW by December 31, 2012. To support both design and development studies for the SBW treatment process, detailed feed compositions are needed. This report contains the expected compositions of these feed streams and the sources and methods used in obtaining these compositions.

  3. Review of FY 2001 Development Work for Vitrification of Sodium Bearing Waste

    SciTech Connect (OSTI)

    Taylor, Dean Dalton; Barnes, Charles Marshall

    2002-09-01

    Treatment of sodium-bearing waste (SBW) at the Idaho Nuclear Technology and Engineering Center (INTEC) within the Idaho National Engineering and Environmental Laboratory is mandated by the Settlement Agreement between the Department of Energy and the State of Idaho. This report discusses significant findings from vitrification technology development during 2001 and their impacts on the design basis for SBW vitrification.

  4. Review of FY2001 Development Work for Vitrification of Sodium Bearing Waste

    SciTech Connect (OSTI)

    Barnes, C.M.; Taylor, D.D.

    2002-09-09

    Treatment of sodium-bearing waste (SBW) at the Idaho Nuclear Technology and Engineering Center (INTEC) within the Idaho National Engineering and Environmental Laboratory is mandated by the Settlement Agreement between the Department of Energy and the State of Idaho. This report discusses significant findings from vitrification technology development during 2001 and their impacts on the design basis for SBW vitrification.

  5. Sodium-Bearing Waste Treatment Alternatives Implementation Study

    SciTech Connect (OSTI)

    Charles M. Barnes; James B. Bosley; Clifford W. Olsen

    2004-07-01

    The purpose of this document is to discuss issues related to the implementation of each of the five down-selected INEEL/INTEC radioactive liquid waste (sodium-bearing waste - SBW) treatment alternatives and summarize information in three main areas of concern: process/technical, environmental permitting, and schedule. Major implementation options for each treatment alternative are also identified and briefly discussed. This report may touch upon, but purposely does not address in detail, issues that are programmatic in nature. Examples of these include how the SBW will be classified with respect to the Nuclear Waste Policy Act (NWPA), status of Waste Isolation Pilot Plant (WIPP) permits and waste storage availability, available funding for implementation, stakeholder issues, and State of Idaho Settlement Agreement milestones. It is assumed in this report that the SBW would be classified as a transuranic (TRU) waste suitable for disposal at WIPP, located in New Mexico, after appropriate treatment to meet transportation requirements and waste acceptance criteria (WAC).

  6. Test Summary Report INEEL Sodium-Bearing Waste Vitrification Demonstration RSM-01-1

    SciTech Connect (OSTI)

    Goles, Ronald W.; Perez, Joseph M.; Macisaac, Brett D.; Siemer, Darryl D.; Mccray, John A.

    2001-05-21

    The U.S. Department of Energy's Idaho National Engineering and Environmental Laboratory is storing large amounts of radioactive and mixed wastes. Most of the sodium-bearing wastes have been calcined, but about a million gallons remain uncalcined, and this waste does not meet current regulatory requirements for long-term storage and/or disposal. As a part of the Settlement Agreement between DOE and the State of Idaho, the tanks currently containing SBW are to be taken out of service by December 31, 2012, which requires removing and treatment the remaining SBW. Vitrification is the option for waste disposal that received the highest weighted score against the criteria used. Beginning in FY 2000, the INEEL high-level waste program embarked on a program for technology demonstration and development that would lead to conceptual design of a vitrification facility in the event that vitrification is the preferred alternative for SBW disposal. The Pacific Northwest National Laborator's Research-Scale Melter was used to conduct these initial melter-flowsheet evaluations. Efforts are underway to reduce the volume of waste vitrified, and during the current test, an overall SBW waste volume-reduction factor of 7.6 was achieved.

  7. EIS-0287: Idaho High-Level Waste & Facilities Disposition

    Broader source: Energy.gov [DOE]

    This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid...

  8. Process Options Description for Vitrification Flowsheet Model of INEEL Sodium Bearing Waste

    SciTech Connect (OSTI)

    Nichols, Todd Travis; Taylor, Dean Dalton; Lauerhass, Lance; Barnes, Charles Marshall

    2001-02-01

    The purpose of this document is to provide the technical information to Savannah River Site (SRS) personnel that is required for the development of a basic steady-state process simulation of the vitrification treatment train of sodium bearing waste (SBW) at Idaho National Engineering and nvironmental Laboratory (INEEL). INEEL considers simulation to have an important role in the integration/optimization of treatment process trains for the High Level Waste (HLW) Program. This project involves a joint Technical Task Plan (TTP ID77WT31, Subtask C) between SRS and INEEL. The work scope of simulation is different at the two sites. This document addresses only the treatment of SBW at INEEL. The simulation model(s) is to be built by SRS for INEEL in FY-2001.

  9. Sodium-bearing Waste Treatment Technology Evaluation Report

    SciTech Connect (OSTI)

    Charles M. Barnes; Arlin L. Olson; Dean D. Taylor

    2004-05-01

    Sodium-bearing waste (SBW) disposition is one of the U.S. Department of Energy (DOE) Idaho Operation Office’s (NE-ID) and State of Idaho’s top priorities at the Idaho National Engineering and Environmental Laboratory (INEEL). The INEEL has been working over the past several years to identify a treatment technology that meets NE-ID and regulatory treatment requirements, including consideration of stakeholder input. Many studies, including the High-Level Waste and Facilities Disposition Environmental Impact Statement (EIS), have resulted in the identification of five treatment alternatives that form a short list of perhaps the most appropriate technologies for the DOE to select from. The alternatives are (a) calcination with maximum achievable control technology (MACT) upgrade, (b) steam reforming, (c) cesium ion exchange (CsIX) with immobilization, (d) direct evaporation, and (e) vitrification. Each alternative has undergone some degree of applied technical development and preliminary process design over the past four years. This report presents a summary of the applied technology and process design activities performed through February 2004. The SBW issue and the five alternatives are described in Sections 2 and 3, respectively. Details of preliminary process design activities for three of the alternatives (steam reforming, CsIX, and direct evaporation) are presented in three appendices. A recent feasibility study provides the details for calcination. There have been no recent activities performed with regard to vitrification; that section summarizes and references previous work.

  10. Independent Oversight Review, Sodium Bearing Waste Treatment...

    Office of Environmental Management (EM)

    Independent Oversight Review, Sodium Bearing Waste Treatment Project - Contractor - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project - Integrated Waste ...

  11. EIS-0287: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002)

    Broader source: Energy.gov [DOE]

    This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid...

  12. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container...

    Office of Environmental Management (EM)

    Nitrate Salt Bearing Waste Container Isolation Plan Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container Isolation Plan The purpose of this document is to provide the ...

  13. Phase 2 TWR Steam Reforming Test for Sodium-Bearing Waste Treatment

    SciTech Connect (OSTI)

    Nicholas R. Soelberg; Doug Marshall; Dean Taylor; Steven Bates

    2004-01-01

    About one million gallons of acidic, hazardous, and radioactive sodium-bearing waste (SBW) is stored in stainless steel tanks a the Idaho Nuclear Technology and Engineering Center (INTEC), which is a major operating facility of the Idaho National Engineering and Environmental Laboratory (INEEL). Steam reforming is a candidate technology being investigated for converting the SBW into a road ready waste form that can be shipped to the Waste Isolation Pilot Plant in New Mexico for interment. Fluidized bed steam reforming technology, licensed to ThermoChem Waste Remediation, LLC (TWR) by Manufacturing Technology Conversion International, was tested in two phases using an INEEL (Department of Energy) fluidized bed test system located at the Science Applications International Corporation (SAIC) Science and Technology Applications Research Center in Idaho Falls, Idaho. The Phase 1 tests were reported earlier. The Phase 2 tests are reported here. For Phase 2, the process feed rate, reductant stoichiometry, and process temperature were varied to identify and demonstrate how the process might be optimized to improve operation and product characteristics. The first week of testing was devoted primarily to process chemistry and the second week was devoted more toward bed stability and particle size control.

  14. Independent Oversight Review, Sodium Bearing Waste Treatment...

    Office of Environmental Management (EM)

    This report documents the results of an independent review of the Sodium Bearing Waste Treatment Project-Integrated Waste Treatment Unit Federal Operational Readiness Review. ...

  15. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container

    Office of Environmental Management (EM)

    Nitrate Salt Bearing Waste Container Isolation Plan Prepared in Response to New Mexico ... (DOE) and Nuclear Waste Partnership LLC (NWP), collectively referred to as the Permittees. ...

  16. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container Isolation

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

    Plan | Department of Energy Nitrate Salt Bearing Waste Container Isolation Plan Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container Isolation Plan The purpose of this document is to provide the Plan required by the New Mexico Environment Department Administrative Order 05-20001 issued on May 20, 2014 to the U. S. Department of Energy and Nuclear Waste Partnership LLC. The Order, at paragraph 22, requires the Permittees to submit a WIPP Nitrate Salt Bearing Waste Container

  17. EIS-0287: Notice of Preferred Sodium Bearing Waste Treatment...

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

    Preferred Sodium Bearing Waste Treatment Technology EIS-0287: Notice of Preferred Sodium Bearing Waste Treatment Technology Idaho High-Level Waste (HLW) and Facilities Disposition...

  18. Fluidized Bed Steam Reforming of INEEL SBW Using THORsm Mineralizing Technology

    SciTech Connect (OSTI)

    Arlin L. Olson; Nicholas R. Soelberg; Douglas W. Marshall; Gary L. Anderson

    2004-12-01

    Sodium bearing waste (SBW) disposition is one of the U.S. Department of Energy (DOE) Idaho Operation Offices (NE-ID) and State of Idahos top priorities at the Idaho National Engineering and Environmental Laboratory (INEEL). Many studies have resulted in the identification of five treatment alternatives that form a short list of perhaps the most appropriate technologies for the DOE to select from. The alternatives are (a) calcination with maximum achievable control technology (MACT) upgrade, (b) steam reforming, (c) cesium ion exchange (CsIX) with immobilization, (d) direct evaporation, and (e) vitrification. Each alternative has undergone some degree of applied technical development and preliminary process design over the past four years. DOE desired further experimental data, with regard to steam reforming technology, to make informed decisions concerning selection of treatment technology for SBW. Mineralizing steam reforming technology, offered by THOR Treatment Technologies, LLC would produce a denitrated, granular mineral waste form using a high-temperature fluidized bed process. A pilot scale demonstration of the technology was performed in a 15-cm-diameter reactor vessel September 27 through October 1, 2004. The pilot scale equipment is owned by the DOE, and located at the Science and Technology Applications Research (STAR) Center in Idaho Falls, ID. Flowsheet chemistry and operational parameters were defined through a collaborative effort involving Idaho National Engineering and Environmental Laboratory, Savannah River National Laboratory (SRNL), and THOR Treatment Technologies personnel. Personnel from Science Applications International Corporation, owners of the STAR Center, operated the pilot plant. The pilot scale test was terminated as planned after achieving a total of 100 hrs of cumulative/continuous processing operation. About 230 kg of SBW surrogate were processed that resulted in about 88 kg of solid product, a mass reduction of about 62%. The

  19. Review of the Sodium Bearing Waste Treatment Project - Integrated...

    Office of Environmental Management (EM)

    Verification Review IWTU Integrated Waste Treatment Unit LCO Limiting Condition for ... Analysis Report SBWTP Sodium Bearing Waste Treatment Project SMP Safety Management ...

  20. Process Options Description for Vitrification Flowsheet Model of INEEL Sodium Bearing Waste

    SciTech Connect (OSTI)

    Nichols, T.T.; Taylor, D.D.; Lauerhass, L.; Barnes, C.M.

    2002-02-21

    The technical information required for the development of a basic steady-state process simulation of the vitrification treatment train of sodium bearing waste (SBW) at Idaho National Engineering and Environmental Laboratory (INEEL) is presented. The objective of the modeling effort is to provide the predictive capability required to optimize an entire treatment train and assess system-wide impacts of local changes at individual unit operations, with the aim of reducing the schedule and cost of future process/facility design efforts. All the information required a priori for engineers to construct and link unit operation modules in a commercial software simulator to represent the alternative treatment trains is presented. The information is of a mid- to high-level nature and consists of the following: (1) a description of twenty-four specific unit operations--their operating conditions and constraints, primary species and key outputs, and the initial modeling approaches that will be used in the first year of the simulation's development; (2) three potential configurations of the unit operations (trains) and their interdependencies via stream connections; and (3) representative stream compositional makeups.

  1. Independent Oversight Review, Sodium Bearing Waste Treatment Project- Federal- June 2012

    Broader source: Energy.gov [DOE]

    Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Federal Operational Readiness Review

  2. Independent Oversight Review, Sodium Bearing Waste Treatment Project- Contractor- June 2012

    Broader source: Energy.gov [DOE]

    Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Contractor Operational Readiness Review

  3. Evaluation of Fluidized Bed Steam Reforming (FBSR) Technology for Sodium Bearing Wastes from Idaho and Hanford Using the Bench-Top Steam Reformer (BSR)

    SciTech Connect (OSTI)

    PAUL, BURKET

    2005-02-28

    Fluidized Bed Steam Reforming (FBSR) is being considered as a potential technology for the immobilization of a wide variety of radioactive wastes, but especially aqueous high sodium wastes at Hanford, Idaho National Engineering and Environmental Laboratory (INEEL), and the Savannah River Site (SRS). To help the Department of Energy (DOE) make informed decisions about this technology for sodium bearing wastes further experimental data are needed. All work described in this study has been performed with non-radioactive simulants and compared to non-radioactive pilot scale testing at other facilities. The desired plan is to provide a laboratory scale system that correlates to the pilot and plant scale systems such that the chemistry of Fluidized Bed Steam Reforming (FBSR) can be optimized on a small scale, then verified at the pilot scale. Once verified, this will enable laboratory scale demonstrations of actual radioactive wastes. The Savannah River National Laboratory (SRNL) developed the Bench-top Steam Reformer (BSR) to fill this need. The development of the BSR is the focus of this study. In addition, the characterization of the FBSR products produced in the BSR from simulants of the INEEL Sodium-Bearing Waste (SBW) stream and the Hanford Low Activity Waste (LAW) stream are documented and compared to pilot scale testing of these same simulants at the INEEL pilot-scale test system located at the Science Applications International Corporation (SAIC) Science and Technology Applications Research (STAR) Center in Idaho Falls, ID.

  4. Solidification of Simulated Liquid Effluents Originating From Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center, FY-03 Report

    SciTech Connect (OSTI)

    S. V. Raman; A. K. Herbst; B. A. Scholes; S. H. Hinckley; R. D. Colby

    2003-09-01

    In this report, the mechanism and methods of fixation of acidic waste effluents in grout form are explored. From the variations in the pH as a function of total solids addition to acidic waste effluent solutions, the stages of gellation, liquefaction, slurry formation and grout development are quantitatively revealed. Experimental results indicate the completion of these reaction steps to be significant for elimination of bleed liquid and for setting of the grout to a dimensionally stable and hardened solid within a reasonable period of about twenty eight days that is often observed in the cement and concrete industry. The reactions also suggest increases in the waste loading in the direction of decreasing acid molarity. Consequently, 1.0 molar SBW-180 waste is contained in higher quantity than the 2.8 molar SBW-189, given the same grout formulation for both effluents. The variations in the formulations involving components of slag, cement, waste and neutralizing agent are represented in the form of a ternary formulation map. The map in turn graphically reveals the relations among the various formulations and grout properties, and is useful in predicting the potential directions of waste loading in grouts with suitable properties such as slurry viscosity, Vicat hardness, and mechanical strength. A uniform formulation for the fixation of both SBW-180 and SBW-189 has emerged from the development of the formulation map. The boundaries for the processing regime on this map are 100 wt% cement to 50 wt% cement / 50 wt% slag, with waste loadings ranging from 55 wt% to 68 wt%. Within these compositional bounds all the three waste streams SBW-180, SBW-189 and Scrub solution are amenable to solidification. A large cost advantage is envisaged to stem from savings in labor, processing time, and processing methodology by adopting a uniform formulation concept for fixation of compositionally diverse waste streams. The experimental efforts contained in this report constitute the

  5. Evaluation of Nitrate-Bearing Transuranic Waste Streams

    Energy Savers [EERE]

    OE-2: 2015-1 June 2015 Evaluation of Nitrate-Bearing Transuranic Waste Streams PURPOSE This Operating Experience Level 2 (OE-2) document provides actions to perform an evaluation...

  6. Independent Oversight Assessment, Idaho Cleanup Project Sodium Bearing Waste Treatment Project- November 2012

    Broader source: Energy.gov [DOE]

    Assessment of Nuclear Safety Culture at the Idaho Cleanup Project Sodium Bearing Waste Treatment Project

  7. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container

    Office of Environmental Management (EM)

    | Department of Energy Isolation Pilot Plant Contractor Receives 86 Percent of Available Fee Waste Isolation Pilot Plant Contractor Receives 86 Percent of Available Fee April 27, 2016 - 12:20pm Addthis Nuclear Waste Partnership received about 86 percent of the available fee for the performance period as the Waste Isolation Pilot Plant management and operations contractor. Nuclear Waste Partnership received about 86 percent of the available fee for the performance period as the Waste

  8. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container

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

    Waste Isolation Pilot Plant (WIPP) Recovery Waste Isolation Pilot Plant (WIPP) Recovery The U.S. Department of Energy’s (DOE) Waste Isolation Pilot Plant (WIPP) is a deep geologic repository for permanent disposal of a specific type of waste that is the byproduct of the nation's nuclear defense program. WIPP is the nation's only repository for the disposal of nuclear waste known as transuranic, or TRU, waste. Two incidents occurred in February 2014 that led to the current shutdown of the

  9. Membrane Treatment of Liquid Salt Bearing Radioactive Wastes

    SciTech Connect (OSTI)

    Dmitriev, S. A.; Adamovich, D. V.; Demkin, V. I.; Timofeev, E. M.

    2003-02-25

    The main fields of introduction and application of membrane methods for preliminary treatment and processing salt liquid radioactive waste (SLRW) can be nuclear power stations (NPP) and enterprises on atomic submarines (AS) utilization. Unlike the earlier developed technology for the liquid salt bearing radioactive waste decontamination and concentrating this report presents the new enhanced membrane technology for the liquid salt bearing radioactive waste processing based on the state-of-the-art membrane unit design, namely, the filtering units equipped with the metal-ceramic membranes of ''TruMem'' brand, as well as the electrodialysis and electroosmosis concentrators. Application of the above mentioned units in conjunction with the pulse pole changer will allow the marked increase of the radioactive waste concentrating factor and the significant reduction of the waste volume intended for conversion into monolith and disposal. Besides, the application of the electrodialysis units loaded with an ion exchange material at the end polishing stage of the radioactive waste decontamination process will allow the reagent-free radioactive waste treatment that meets the standards set for the release of the decontaminated liquid radioactive waste effluents into the natural reservoirs of fish-farming value.

  10. INTEC SBW Solid Sludge Surrogate Recipe and Validation

    SciTech Connect (OSTI)

    Maio, Vince; Janikowski, Stuart; Johnson, Jim; Maio, Vince; Pao, Jenn-Hai

    2004-06-01

    A nonhazardous INTEC tank farm sludge surrogate that incorporated metathesis reactions to generate solids from solutions of known elements present in the radioactive INTEC tank farm sodium-bearing waste sludges was formulated. Elemental analyses, physical property analyses, and filtration testing were performed on waste surrogate and tank farm waste samples, and the results were compared. For testing physical systems associated with moving the tank farm solids, the surrogate described in this report is the best currently available choice. No other available surrogate exhibits the noted similarities in behavior to the sludges. The chemical morphology, particle size distribution, and settling and flow characteristics of the surrogate were similar to those exhibited by the waste sludges. Nonetheless, there is a difference in chemical makeup of the surrogate and the tank farm waste. If a chemical treatment process were to be evaluated for final treatment and disposition of the waste sludges, the surrogate synthesis process would likely require modification to yield a surrogate with a closer matching chemical composition.

  11. WIPP Nitrate Salt Bearing Waste Container Isolation Plan Implementation Update

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

    Nitrate Salt Bearing Waste Container Isolation Plan Implementation Update May 12, 2015 Panel 6 and Panel 7, Room 7 a. Rollback * Contamination Assessment-This prerequisite is complete and therefore status updates are no longer required. * Fixing/Decontamination Activities-Decontaminated equipment has been removed from Room 7 of Panel 7 to prepare for Room 7 closure activities. Remaining items in Panel 7, Room 7 include thirteen empty magnesium oxide racks, about 200 roof bolts, nine messenger

  12. Sodium-Bearing Waste Treatment, Applied Technology Plan

    SciTech Connect (OSTI)

    Lance Lauerhass; Vince C. Maio; S. Kenneth Merrill; Arlin L. Olson; Keith J. Perry

    2003-06-01

    Settlement Agreement between the Department of Energy and the State of Idaho mandates treatment of sodium-bearing waste at the Idaho Nuclear Technology and Engineering Center within the Idaho National Engineering and Environmental Laboratory. One of the requirements of the Settlement Agreement is to complete treatment of sodium-bearing waste by December 31, 2012. Applied technology activities are required to provide the data necessary to complete conceptual design of four identified alternative processes and to select the preferred alternative. To provide a technically defensible path forward for the selection of a treatment process and for the collection of needed data, an applied technology plan is required. This document presents that plan, identifying key elements of the decision process and the steps necessary to obtain the required data in support of both the decision and the conceptual design. The Sodium-Bearing Waste Treatment Applied Technology Plan has been prepared to provide a description/roadmap of the treatment alternative selection process. The plan details the results of risk analyzes and the resulting prioritized uncertainties. It presents a high-level flow diagram governing the technology decision process, as well as detailed roadmaps for each technology. The roadmaps describe the technical steps necessary in obtaining data to quantify and reduce the technical uncertainties associated with each alternative treatment process. This plan also describes the final products that will be delivered to the Department of Energy Idaho Operations Office in support of the office's selection of the final treatment technology.

  13. Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility

    SciTech Connect (OSTI)

    Bonnema, Bruce Edward

    2001-09-01

    This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energys Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

  14. Vitrified waste option study report

    SciTech Connect (OSTI)

    Lopez, D.A.; Kimmitt, R.R.

    1998-02-01

    A {open_quotes}Settlement Agreement{close_quotes} between the Department of Energy and the State of Idaho mandates that all radioactive high-level waste (HLW) now stored at the Idaho Chemical Processing Plant (ICPP) will be treated so that it is ready to be moved out of Idaho for disposal by a target date of 2035. This report investigates vitrification treatment of all ICPP calcine, including the existing and future HLW calcine resulting from calcining liquid Sodium-Bearing Waste (SBW). Currently, the SBW is stored in the tank farm at the ICPP. Vitrification of these wastes is an acceptable treatment method for complying with the Settlement Agreement. This method involves vitrifying the calcined waste and casting the vitrified mass into stainless steel canisters that will be ready to be moved out of the Idaho for disposal by 2035. These canisters will be stored at the Idaho National Engineering and Environmental Laboratory (INEEL) until they are sent to a HLW national repository. The operating period for vitrification treatment will be from 2013 through 2032; all HLW will be treated and in storage by the end of 2032.

  15. DOE/EIS-0287 Idaho High-Level Waste & Facilities Disposition...

    Office of Environmental Management (EM)

    Cesium ion exchange & grouting Cesium ion exchange & grouting NWCF* NWCF* Calcine Mixed transuranic wasteSBW Mixed transuranic wasteNGLW Low-level waste disposa l*** disposa l*** ...

  16. Froth flotation of oil-bearing metal sulfide wastes

    SciTech Connect (OSTI)

    Miller, R.L.; Atwood, R.L.; Ye, Yi

    1991-12-01

    An industrial wastewater, including plating wastes, is treated with sodium sulfide and ferrous sulfate to form a sulfide-oxide precipitate containing chromium and other toxic metals. Hydrocarbons, in the water, coat the sulfide-oxide particles, impeding metal recovery. Froth flotation, without reagent addition, was found to recover 93.9% of the solids from the sludge with simultaneous rejection of 89% of the water. Methyl isobutyl carbinol (MIBC) improved recovery and potassium amyl xanthate improved both recovery and grade. The process design has wastewater feed (without MIBC) to the rougher circuit. The rougher concentrate is conditioned with MIBC and fed to a cleaner circuit to achieve a high grade concentrate. About 95% of the water is recirculated to the waste treatment plant. 3 refs., 3 figs., 4 tabs.

  17. Froth flotation of oil-bearing metal sulfide wastes

    SciTech Connect (OSTI)

    Miller, R.L. ); Atwood, R.L.; Ye, Yi )

    1991-01-01

    An industrial wastewater, including plating wastes, is treated with sodium sulfide and ferrous sulfate to form a sulfide-oxide precipitate containing chromium and other toxic metals. Hydrocarbons, in the water, coat the sulfide-oxide particles, impeding metal recovery. Froth flotation, without reagent addition, was found to recover 93.9% of the solids from the sludge with simultaneous rejection of 89% of the water. Methyl isobutyl carbinol (MIBC) improved recovery and potassium amyl xanthate improved both recovery and grade. The process design has wastewater feed (without MIBC) to the rougher circuit. The rougher concentrate is conditioned with MIBC and fed to a cleaner circuit to achieve a high grade concentrate. About 95% of the water is recirculated to the waste treatment plant. 3 refs., 3 figs., 4 tabs.

  18. Testing and Disposal Strategy for Secondary Wastes from Vitrification of Sodium-Bearing Waste at Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Herbst, Alan K.

    2002-01-02

    The Idaho National Engineering and Environmental Laboratory (INEEL) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

  19. Testing and Disposal Strategy for Secondary Wastes from Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Herbst, Alan Keith

    2002-01-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

  20. Cost Transfers at the Department's Sodium Bearing Waste Treatment Facility Construction Project

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

    Department of Energy Office of Inspector General Office of Audits and Inspections Audit Report Cost Transfers at the Department's Sodium Bearing Waste Treatment Facility Construction Project OAS-M-13-03 August 2013 Department of Energy Washington, DC 20585 August 8, 2013 MEMORANDUM FOR THE SENIOR ADVISOR FOR ENVIRONMENTAL MANAGEMENT FROM: Rickey R. Hass Deputy Inspector General for Audits and Inspections Office of Inspector General SUBJECT: INFORMATION: Audit Report on "Cost Transfers at

  1. Alternative TRUEX-Based Pretreatment Processing of INEEL Sodium Bearing Waste

    SciTech Connect (OSTI)

    Rapko, Brian M.; Fiskum, Sandra K.; Lumetta, Gregg J.

    2000-09-27

    The goals of this study were to demonstrate a selective complexant for separating mercury from the transuranic (TRU) elements in the transuranic extraction (TRUEX) process and to demonstrate alternative stripping methods to eliminate phosphorus-containing, actinide stripping agents during TRUEX processing. The work described in this report provides the basis for implementing an improved TRUEX-based flowsheet for processing INEEL sodium-bearing waste using only minor modifications to the current Idaho National Engineering and Environmental Laboratory (INEEL) flowsheet design.

  2. DURABILITY TESTING OF FLUIDIZED BED STEAM REFORMER (FBSR) WASTE FORMS

    SciTech Connect (OSTI)

    Jantzen, C

    2006-01-06

    Fluidized Bed Steam Reforming (FBSR) is being considered as a potential technology for the immobilization of a wide variety of high sodium aqueous radioactive wastes. The addition of clay and a catalyst as co-reactants converts high sodium aqueous low activity wastes (LAW) such as those existing at the Hanford and Idaho DOE sites to a granular ''mineralized'' waste form that may be made into a monolith form if necessary. Simulant Hanford and Idaho high sodium wastes were processed in a pilot scale FBSR at Science Applications International Corporation (SAIC) Science and Technology Applications Research (STAR) facility in Idaho Falls, ID. Granular mineral waste forms were made from (1) a basic Hanford Envelope A low-activity waste (LAW) simulant and (2) an acidic INL simulant commonly referred to as sodium-bearing waste (SBW). The FBSR waste forms were characterized and the durability tested via ASTM C1285 (Product Consistency Test), the Environmental Protection Agency (EPA) Toxic Characteristic Leaching Procedure (TCLP), and the Single Pass Flow Through (SPFT) test. The durability of the FBSR waste form products was tested in order to compare the measured durability to previous FBSR waste form testing on Hanford Envelope C waste forms that were made by THOR Treatment Technologies (TTT) and to compare the FBSR durability to vitreous LAW waste forms, specifically the Hanford low activity waste (LAW) glass known as the Low-activity Reference Material (LRM). The durability of the FBSR waste form is comparable to that of the LRM glass for the test responses studied.

  3. Secondary Waste Considerations for Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center FY-2001 Status Report

    SciTech Connect (OSTI)

    Herbst, A.K.; Kirkham, R.J.; Losinski, S.J.

    2002-09-26

    The Idaho Nuclear Technology and Engineering Center (INTEC) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes from the melter off-gas clean up systems. Projected secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

  4. Secondary Waste Considerations for Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Techology and Engineering Center FY-2001 Status Report

    SciTech Connect (OSTI)

    Herbst, Alan Keith; Kirkham, Robert John; Losinski, Sylvester John

    2001-09-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes from the melter off-gas clean up systems. Projected secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

  5. Suitability of Silica Gel to Process INEEL Sodium Bearing Waste - Letter Report

    SciTech Connect (OSTI)

    Kirkham, Robert John; Herbst, Alan Keith

    2000-09-01

    The suitability of using the silica gel process for Idaho National Engineering and Environmental Laboratory (INEEL) sodium bearing waste was investigated during fiscal year 2000. The study was co-funded by the Tanks Focus Area as part of TTP No. ID-77WT-31 and the High Level Waste Program. The task also included the investigation of possible other absorbents. Scoping tests and examination of past work showed that the silica gel absorption/adsorption and drying method was the most promising; thus only silica gel was studied and not other absorbents. The documentation on the Russian silica gel process provided much of the needed information but did not provide some of the processing detail so these facts had to be inferred or gleaned from the literature.

  6. Phase 2 THOR Steam Reforming Tests for Sodium Bearing Waste Treatment

    SciTech Connect (OSTI)

    Nicholas R. Soelberg

    2004-01-01

    About one million gallons of acidic, hazardous, and radioactive sodium-bearing waste is stored in stainless steel tanks at the Idaho Nuclear Technology and Engineering Center (INTEC), which is a major operating facility of the Idaho National Engineering and Environmental Laboratory. Steam reforming is a candidate technology being investigated for converting the waste into a road ready waste form that can be shipped to the Waste Isolation Pilot Plant in New Mexico for interment. A steam reforming technology patented by Studsvik, Inc., and licensed to THOR Treatment Technologies has been tested in two phases using a Department of Energy-owned fluidized bed test system located at the Science Applications International Corporation (SAIC) Science and Technology Applications Research Center located in Idaho Falls, Idaho. The Phase 1 tests were reported earlier in 2003. The Phase 2 tests are reported here. For Phase 2, the process feed rate, stoichiometry, and chemistry were varied to identify and demonstrate process operation and product characteristics under different operating conditions. Two test series were performed. During the first series, the process chemistry was designed to produce a sodium carbonate product. The second series was designed to produce a more leach-resistant, mineralized sodium aluminosilicate product. The tests also demonstrated the performance of a MACT-compliant off-gas system.

  7. Characterization of plutonium-bearing wastes by chemical analysis and analytical electron microscopy

    SciTech Connect (OSTI)

    Behrens, R.G.; Buck, E.C.; Dietz, N.L.; Bates, J.K.; Van Deventer, E.; Chaiko, D.J.

    1995-09-01

    This report summarizes the results of characterization studies of plutonium-bearing wastes produced at the US Department of Energy weapons production facilities. Several different solid wastes were characterized, including incinerator ash and ash heels from Rocky Flats Plant and Los Alamos National Laboratory; sand, stag, and crucible waste from Hanford; and LECO crucibles from the Savannah River Site. These materials were characterized by chemical analysis and analytical electron microscopy. The results showed the presence of discrete PuO{sub 2}PuO{sub 2{minus}x}, and Pu{sub 4}O{sub 7} phases, of about 1{mu}m or less in size, in all of the samples examined. In addition, a number of amorphous phases were present that contained plutonium. In all the ash and ash heel samples examined, plutonium phases were found that were completely surrounded by silicate matrices. Consequently, to achieve optimum plutonium recovery in any chemical extraction process, extraction would have to be coupled with ultrafine grinding to average particle sizes of less than 1 {mu}m to liberate the plutonium from the surrounding inert matrix.

  8. Modeling of NOx Destruction Options for INEEL Sodium-Bearing Waste Vitrification

    SciTech Connect (OSTI)

    Wood, Richard Arthur

    2001-09-01

    Off-gas NOx concentrations in the range of 1-5 mol% are expected as a result of the proposed vitrification of sodium-bearing waste at the Idaho National Engineering and Environmental Laboratory. An existing kinetic model for staged combustion (originally developed for NOx abatement from the calcination process) was updated for application to vitrification offgas. In addition, two new kinetic models were developed to assess the feasibility of using selective non-catalytic reduction (SNCR) or high-temperature alone for NOx abatement. Each of the models was developed using the Chemkin code. Results indicate that SNCR is a viable option, reducing NOx levels to below 1000 ppmv. In addition, SNCR may be capable of simultaneously reducing CO emissions to below 100 ppmv. Results for using high-temperature alone were not as promising, indicating that a minimum NOx concentration of 3950 ppmv is achievable at 3344F.

  9. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... DOE mixed waste streams) including INL "sodium bearing waste" (SBW), liquid "low ... thorium fuel cycles, gas-cooled fast reactors, the reliability of TRISO-coated ...

  10. Fundamental Thermodynamics of Actinide-Bearing Mineral Waste Forms - Final Report

    SciTech Connect (OSTI)

    Williamson, Mark A.; Ebbinghaus, Bartley B.; Navrotsky, Alexandra

    2001-03-01

    The end of the Cold War raised the need for the technical community to be concerned with the disposition of excess nuclear weapon material. The plutonium will either be converted into mixed-oxide fuel for use in nuclear reactors or immobilized in glass or ceramic waste forms and placed in a repository. The stability and behavior of plutonium in the ceramic materials as well as the phase behavior and stability of the ceramic material in the environment is not well established. In order to provide technically sound solutions to these issues, thermodynamic data are essential in developing an understanding of the chemistry and phase equilibria of the actinide-bearing mineral waste form materials proposed as immobilization matrices. Mineral materials of interest include zircon, zirconolite, and pyrochlore. High temperature solution calorimetry is one of the most powerful techniques, sometimes the only technique, for providing the fundamental thermodynamic data needed to establish optimum material fabrication parameters, and more importantly understand and predict the behavior of the mineral materials in the environment. The purpose of this project is to experimentally determine the enthalpy of formation of actinide orthosilicates, the enthalpies of formation of actinide substituted zirconolite and pyrochlore, and develop an understanding of the bonding characteristics and stabilities of these materials.

  11. Cementitious waste option scoping study report

    SciTech Connect (OSTI)

    Lee, A.E.; Taylor, D.D.

    1998-02-01

    A Settlement Agreement between the Department of Energy (DOE) and the State of Idaho mandates that all high-level radioactive waste (HLW) now stored at the Idaho Chemical Processing Plant (ICPP) on the Idaho National Engineering and Environmental Laboratory (INEEL) will be treated so that it is ready to be moved out of Idaho for disposal by a target date of 2035. This study investigates the nonseparations Cementitious Waste Option (CWO) as a means to achieve this goal. Under this option all liquid sodium-bearing waste (SBW) and existing HLW calcine would be recalcined with sucrose, grouted, canisterized, and interim stored as a mixed-HLW for eventual preparation and shipment off-Site for disposal. The CWO waste would be transported to a Greater Confinement Disposal Facility (GCDF) located in the southwestern desert of the US on the Nevada Test Site (NTS). All transport preparation, shipment, and disposal facility activities are beyond the scope of this study. CWO waste processing, packaging, and interim storage would occur over a 5-year period between 2013 and 2017. Waste transport and disposal would occur during the same time period.

  12. Bear Creek Valley characterization area mixed wastes passive in situ treatment technology demonstration project - status report

    SciTech Connect (OSTI)

    Watson, D.; Leavitt, M.; Moss, D.

    1997-03-01

    Historical waste disposal activities within the Bear Creek Valley (BCV) Characterization Area (CA), at the U.S. Department of Energy (DOE) Oak Ridge Y-12 plant, have contaminated groundwater and surface water above human health risk levels and impacted the ecology of Bear Creek. Contaminates include nitrate, radioisotopes, metals, volatile organic chemicals (VOCS), and common ions. This paper provides a status report on a technology demonstration project that is investigating the feasibility of using passive in situ treatment systems to remove these contaminants. Although this technology may be applicable to many locations at the Oak Ridge Y-12 Plant, the project focuses on collecting the information needed to take CERCLA removal actions in 1998 at the S-3 Disposal Ponds site. Phase 1 has been completed and included site characterization, laboratory screening of treatment media (sorbents; and iron), and limited field testing of biological treatment systems. Batch tests using different Y-12 Plant waters were conducted to evaluate the removal efficiencies of most of the media. Phase 1 results suggest that the most promising treatment media are Dowex 21 k resin, peat moss, zero-valent iron, and iron oxides. Phase 2 will include in-field column testing of these media to assess loading rates, and concerns with clogging, by-products, and long-term treatment efficiency and media stability. Continued testing of wetlands and algal mats (MATs) will be conducted to determine if they can be used for in-stream polishing of surface water. Hydraulic testing of a shallow trench and horizontal well will also be completed during Phase 2. 4 refs., 3 tabs.

  13. FLUIDIZED BED STEAM REFORMED MINERAL WASTE FORMS: CHARACTERIZATION AND DURABILITY TESTING

    SciTech Connect (OSTI)

    Jantzen, C; Troy Lorier, T; John Pareizs, J; James Marra, J

    2007-03-31

    Fluidized Bed Steam Reforming (FBSR) is being considered as a potential technology for the immobilization of a wide variety of high sodium low activity wastes (LAW) such as those existing at the Hanford site, at the Idaho National Laboratory (INL), and the Savannah River Site (SRS). The addition of clay, charcoal, and a catalyst as co-reactants with the waste denitrates the aqueous wastes and forms a granular mineral waste form that can subsequently be made into a monolith for disposal if necessary. The waste form produced is a multiphase mineral assemblage of Na-Al-Si (NAS) feldspathoid minerals with cage and ring structures and iron bearing spinel minerals. The mineralization occurs at moderate temperatures between 650-750 C in the presence of superheated steam. The cage and ring structured feldspathoid minerals atomically bond radionuclides like Tc-99 and Cs-137 and anions such as SO4, I, F, and Cl. The spinel minerals stabilize Resource Conservation and Recovery Act (RCRA) hazardous species such as Cr and Ni. Granular mineral waste forms were made from (1) a basic Hanford Envelope A low-activity waste (LAW) simulant and (2) an acidic INL simulant commonly referred to as sodium bearing waste (SBW) in pilot scale facilities at the Science Applications International Corporation (SAIC) Science and Technology Applications Research (STAR) facility in Idaho Falls, ID. The FBSR waste forms were characterized and the durability tested via ASTM C1285 (Product Consistency Test), the Environmental Protection Agency (EPA) Toxic Characteristic Leaching Procedure (TCLP), and the Single Pass Flow Through (SPFT) test. The results of the SPFT testing and the activation energies for dissolution are discussed in this study.

  14. FLUIDIZED BED STEAM REFORMED MINERAL WASTE FORMS: CHARACTERIZATION AND DURABILITY TESTING

    SciTech Connect (OSTI)

    Jantzen, C; Troy Lorier, T; John Pareizs, J; James Marra, J

    2006-12-06

    Fluidized Bed Steam Reforming (FBSR) is being considered as a potential technology for the immobilization of a wide variety of high sodium low activity wastes (LAW) such as those existing at the Hanford site, at the Idaho National Laboratory (INL), and the Savannah River Site (SRS). The addition of clay, charcoal, and a catalyst as co-reactants with the waste denitrates the aqueous wastes and forms a granular mineral waste form that can subsequently be made into a monolith for disposal if necessary. The waste form produced is a multiphase mineral assemblage of Na-Al-Si (NAS) feldspathoid minerals with cage and ring structures and iron bearing spinel minerals. The mineralization occurs at moderate temperatures between 650-750 C in the presence of superheated steam. The cage and ring structured feldspathoid minerals atomically bond radionuclides like Tc-99 and Cs-137 and anions such as SO{sub 4}, I, F, and Cl. The spinel minerals stabilize Resource Conservation and Recovery Act (RCRA) hazardous species such as Cr and Ni. Granular mineral waste forms were made from (1) a basic Hanford Envelope A low activity waste (LAW) simulant and (2) an acidic INL simulant commonly referred to as sodium bearing waste (SBW) in pilot scale facilities at the Science Applications International Corporation (SAIC) Science and Technology Applications Research (STAR) facility in Idaho Falls, ID. The FBSR waste forms were characterized and the durability tested via ASTM C1285 (Product Consistency Test), the Environmental Protection Agency (EPA) Toxic Characteristic Leaching Procedure (TCLP), and the Single Pass Flow Through (SPFT) test. The results of the SPFT testing and the activation energies for dissolution are discussed in this study.

  15. Prototype Development of Remote Operated Hot Uniaxial Press (ROHUP) to Fabricate Advanced Tc-99 Bearing Ceramic Waste Forms - 13381

    SciTech Connect (OSTI)

    Alaniz, Ariana J.; Delgado, Luc R.; Werbick, Brett M.; Hartmann, Thomas

    2013-07-01

    The objective of this senior student project is to design and build a prototype construction of a machine that simultaneously provides the proper pressure and temperature parameters to sinter ceramic powders in-situ to create pellets of rather high densities of above 90% (theoretical). This ROHUP (Remote Operated Hot Uniaxial Press) device is designed specifically to fabricate advanced ceramic Tc-99 bearing waste forms and therefore radiological barriers have been included in the system. The HUP features electronic control and feedback systems to set and monitor pressure, load, and temperature parameters. This device operates wirelessly via portable computer using Bluetooth{sup R} technology. The HUP device is designed to fit in a standard atmosphere controlled glove box to further allow sintering under inert conditions (e.g. under Ar, He, N{sub 2}). This will further allow utilizing this HUP for other potential applications, including radioactive samples, novel ceramic waste forms, advanced oxide fuels, air-sensitive samples, metallic systems, advanced powder metallurgy, diffusion experiments and more. (authors)

  16. Out-Of-Drum Grout Mixer Testing With Simulated Liquid Effluents Originating From Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    B. A. Scholes; A. K. Herbst; S. V. Raman; S. H. Hinckley

    2003-09-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) is considering several optional processes for disposal of liquid sodium-bearing waste. During fiscal year 2003, alternatives were evaluated for grout formulation development and associated mixing for the Sodium-Bearing Waste cesium ion exchange process. The neutralization agents calcium or sodium hydroxide and the solidification agents Portland cement, with or without blast furnace slag were evaluated. A desired uniform formulation was pursued to develop a grout waste form without any bleed liquid and solidify within a reasonable period of about twenty-eight days. This testing evaluates the out-of-drum alternative of mixing the effluent with solidification agents prior to being poured into drums versus the in-drum alternative of mixing them all together after being poured into the drums. Experimental results indicate that sodium-bearing waste can be immobilized in grout using the Autocon continuous mixer within the range of 66 to 72 weight percent. Furthermore, a loading of 30 weight percent NWCF scrubber simulant also produced an acceptable grout waste form.

  17. Experimental determination of the speciation, partitioning, and release of perrhenate as a chemical surrogate for pertechnetate from a sodalite-bearing multiphase ceramic waste form

    SciTech Connect (OSTI)

    Pierce, Eric M.; Lukens, Wayne W.; Fitts, Jeff. P.; Jantzen, Carol. M.; Tang, G.

    2013-12-01

    A key component to closing the nuclear fuel cycle is the storage and disposition of nuclear waste in geologic systems. Multiphase ceramic waste forms have been studied extensively as a potential host matrix for nuclear waste. Understanding the speciation, partitioning, and release behavior of radionuclides immobilized in multiphase ceramic waste forms is a critical aspect of developing the scientific and technical basis for nuclear waste management. In this study, we evaluated a sodalite-bearing multiphase ceramic waste form (i.e., fluidized-bed steam reform sodium aluminosilicate [FBSR NAS] product) as a potential host matrix for long-lived radionuclides, such as technetium (99Tc). The FBSR NAS material consists primarily of nepheline (ideally NaAlSiO4), anion-bearing sodalites (ideally M8[Al6Si6O24]X2, where M refers to alkali and alkaline earth cations and X refers to monovalent anions), and nosean (ideally Na8[AlSiO4]6SO4). Bulk X-ray absorption fine structure analysis of the multiphase ceramic waste form, suggest rhenium (Re) is in the Re(VII) oxidation state and has partitioned to a Re-bearing sodalite phase (most likely a perrhenate sodalite Na8[Al6Si6O24](ReO4)2). Rhenium was added as a chemical surrogate for 99Tc during the FBSR NAS synthesis process. The weathering behavior of the FBSR NAS material was evaluated under hydraulically unsaturated conditions with deionized water at 90 ?C. The steady-state Al, Na, and Si concentrations suggests the weathering mechanisms are consistent with what has been observed for other aluminosilicate minerals and include a combination of ion exchange, network hydrolysis, and the formation of an enriched-silica surface layer or phase. The steady-state S and Re concentrations are within an order of magnitude of the nosean and perrhenate sodalite solubility, respectively. The order of magnitude difference between the observed and predicted concentration for Re and S may be associated with the fact that the anion-bearing

  18. Integrated Waste Treatment Unit (IWTU) Input Coal Analyses and Off-Gass Filter (OGF) Content Analyses

    SciTech Connect (OSTI)

    Jantzen, Carol M.; Missimer, David M.; Guenther, Chris P.; Shekhawat, Dushyant; VanEssendelft, Dirk T.; Means, Nicholas C.

    2015-04-23

    A full engineering scale Fluidized Bed Steam Reformer (FBSR) system is being used at the Idaho Nuclear Technology and Engineering Center (INTEC) to stabilize acidic Low Activity Waste (LAW) known as Sodium Bearing Waste (SBW). The INTEC facility, known as the Integrated Waste Treatment Unit (IWTU), underwent an Operational Readiness Review (ORR) and a Technology Readiness Assessment (TRA) in March 2014. The IWTU began non-radioactive simulant processing in late 2014 and by January, 2015 ; the IWTU had processed 62,000 gallons of simulant. The facility is currently in a planned outage for inspection of the equipment and will resume processing simulated waste feed before commencing to process 900,000 gallons of radioactive SBW. The SBW acidic waste will be made into a granular FBSR product (carbonate based) for disposal in the Waste Isolation Pilot Plant (WIPP). In the FBSR process calcined coal is used to create a CO2 fugacity to force the waste species to convert to carbonate species. The quality of the coal, which is a feed input, is important because the reactivity, moisture, and volatiles (C,H,N,O, and S) in the coal impact the reactions and control of the mineralizing process in the primary steam reforming vessel, the Denitration and Mineralizing Reformer (DMR). Too much moisture in the coal can require that additional coal be used. However since moisture in the coal is only a small fraction of the moisture from the fluidizing steam this can be self-correcting. If the coal reactivity or heating value is too low then the coal feedrate needs to be adjusted to achieve the desired heat generation. Too little coal and autothermal heat generation in the DMR cannot be sustained and/or the carbon dioxide fugacity will be too low to create the desired carbonate mineral species. Too much coal and excess S and hydroxide species can form. Excess sulfur from coal that (1) is too rich in sulfur or (2) from overfeeding coal can promote wall scale and contribute to corrosion

  19. Microsoft Word - EMAB Minutes _control version_ 081413

    Office of Environmental Management (EM)

    ... - Pulse-jet mixers SBW - Sodium-bearing waste SRS - (DOE) ... mission and that is on the fast track and given the budget ... the nine nuclear reactors located along the Columbia River. ...

  20. THRUST BEARING

    DOE Patents [OSTI]

    Heller, P.R.

    1958-09-16

    A thrust bearing suitable for use with a rotor or blower that is to rotate about a vertical axis is descrihed. A centrifagal jack is provided so thnt the device may opernte on one hearing at starting and lower speeds, and transfer the load to another bearing at higher speeds. A low viscosity fluid is used to lubricate the higher speed operation bearing, in connection with broad hearing -surfaces, the ability to withstand great loads, and a relatively high friction loss, as contraated to the lower speed operatio;n bearing which will withstand only light thrust loads but is sufficiently frictionfree to avoid bearing seizure during slow speed or startup operation. An axially aligned shaft pin provides the bearing surface for low rotational speeds, but at higher speed, weights operating against spring tension withdraw nthe shaft pin into the bearing proper and the rotor shaft comes in contact with the large bearing surfaces.

  1. Bearing Analytics

    Broader source: Energy.gov [DOE]

    Bearing Analytics is a leading-edge equipment monitoring company aimed at pioneering a new era in industrial bearing condition monitoring. Our objective is to consolidate the needs of customers, environment, and manufacturers to improve asset management and energy efficiency capabilities one bearing at a time.

  2. Journal bearing

    DOE Patents [OSTI]

    Menke, John R.; Boeker, Gilbert F.

    1976-05-11

    1. An improved journal bearing comprising in combination a non-rotatable cylindrical bearing member having a first bearing surface, a rotatable cylindrical bearing member having a confronting second bearing surface having a plurality of bearing elements, a source of lubricant adjacent said bearing elements for supplying lubricant thereto, each bearing element consisting of a pair of elongated relatively shallowly depressed surfaces lying in a cylindrical surface co-axial with the non-depressed surface and diverging from one another in the direction of rotation and obliquely arranged with respect to the axis of rotation of said rotatable member to cause a flow of lubricant longitudinally along said depressed surfaces from their distal ends toward their proximal ends as said bearing members are rotated relative to one another, each depressed surface subtending a radial angle of less than 360.degree., and means for rotating said rotatable bearing member to cause the lubricant to flow across and along said depressed surfaces, the flow of lubricant being impeded by the non-depressed portions of said second bearing surface to cause an increase in the lubricant pressure.

  3. Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 2: Appendix A -- Waste sites, source terms, and waste inventory report; Appendix B -- Description of the field activities and report database; Appendix C -- Characterization of hydrogeologic setting report

    SciTech Connect (OSTI)

    1996-09-01

    This Remedial Investigation (RI) Report characterizes the nature and extent of contamination, evaluates the fate and transport of contaminants, and assesses risk to human health and the environment resulting from waste disposal and other US Department of Energy (DOE) operations in Bear Creek Valley (BCV). BCV, which is located within the DOE Oak Ridge Reservation (ORR) encompasses multiple waste units containing hazardous and radioactive wastes arising from operations at the adjacent Oak Ridge Y-12 Plant. The primary waste units discussed in this RI Report are the S-3 Site, Oil Landfarm (OLF), Boneyard/Burnyard (BYBY), Sanitary Landfill 1 (SL 1), and Bear Creek Burial Grounds (BCBG). These waste units, plus the contaminated media resulting from environmental transport of the wastes from these units, are the subject of this RI. This BCV RI Report represents the first major step in the decision-making process for the BCV watershed. The RI results, in concert with the follow-on FS will form the basis for the Proposed Plan and Record of Decision for all BCV sites. This comprehensive decision document process will meet the objectives of the watershed approach for BCV. Appendix A includes descriptions of waste areas and estimates of the current compositions of the wastes. Appendix B contains an extensive database of environmental data for the Bear Creek Valley Characterization Area. Information is also presented about the number and location of samples collected, the analytes examined, and the extent of data validation. Appendix C describes the hydrogeologic conceptual model for Bear Creek Valley. This model is one of the principal components of the conceptual site models for contaminant transport in BCV.

  4. Physical, Chemical and Structural Evolution of Zeolite-Containing Waste Forms Produced from Metakaolinite and Calcined Sodium Bearing Waste (HLW and/or LLW)

    SciTech Connect (OSTI)

    Grutzeck, Michael W.

    2005-06-27

    Zeolites are extremely versatile. They can adsorb liquids and gases and serve as cation exchange media. They occur in nature as well cemented deposits. The ancient Romans used blocks of zeolitized tuff as a building material. Using zeolites for the management of radioactive waste is not a new idea, but a process by which the zeolites can be made to act as a cementing agent is. Zeolitic materials are relatively easy to synthesize from a wide range of both natural and man-made substances. The process under study is derived from a well known method in which metakaolin (an impure thermally dehydroxylated kaolinite heated to {approx}700 C containing traces of quartz and mica) is mixed with sodium hydroxide (NaOH) and reacted in slurry form (for a day or two) at mildly elevated temperatures. The zeolites form as finely divided powders containing micrometer ({micro}m) sized crystals. However, if the process is changed slightly and only just enough concentrated sodium hydroxide solution is added to the metakaolinite to make a thick crumbly paste and then the paste is compacted and cured under mild hydrothermal conditions (60-200 C), the mixture will form a hard ceramic-like material containing distinct crystalline tectosilicate minerals (zeolites and feldspathoids) imbedded in an X-ray amorphous hydrated sodium aluminosilicate matrix. Due to its lack of porosity and vitreous appearance we have chosen to call this composite a ''hydroceramic''.

  5. Characterisation of Ba(OH){sub 2}–Na{sub 2}SO{sub 4}–blast furnace slag cement-like composites for the immobilisation of sulfate bearing nuclear wastes

    SciTech Connect (OSTI)

    Mobasher, Neda; Bernal, Susan A.; Hussain, Oday H.; Apperley, David C.; Kinoshita, Hajime; Provis, John L.

    2014-12-15

    Soluble sulfate ions in nuclear waste can have detrimental effects on cementitious wasteforms and disposal facilities based on Portland cement. As an alternative, Ba(OH){sub 2}–Na{sub 2}SO{sub 4}–blast furnace slag composites are studied for immobilisation of sulfate-bearing nuclear wastes. Calcium aluminosilicate hydrate (C–A–S–H) with some barium substitution is the main binder phase, with barium also present in the low solubility salts BaSO{sub 4} and BaCO{sub 3}, along with Ba-substituted calcium sulfoaluminate hydrates, and a hydrotalcite-type layered double hydroxide. This reaction product assemblage indicates that Ba(OH){sub 2} and Na{sub 2}SO{sub 4} act as alkaline activators and control the reaction of the slag in addition to forming insoluble BaSO{sub 4}, and this restricts sulfate availability for further reaction as long as sufficient Ba(OH){sub 2} is added. An increased content of Ba(OH){sub 2} promotes a higher degree of reaction, and the formation of a highly cross-linked C–A–S–H gel. These Ba(OH){sub 2}–Na{sub 2}SO{sub 4}–blast furnace slag composite binders could be effective in the immobilisation of sulfate-bearing nuclear wastes.

  6. Immobilization of sodium-bearing high-level radioactive waste in synroc containing (Na{sub 0.5}Nd{sub 0.5})TiO{sub 3}-type perovskite

    SciTech Connect (OSTI)

    Li, L.; Luo, S.; Tang, B.; Wang, D.

    1997-01-01

    This study on the immobilization of high-sodium-bearing HLW in synroc indicates that (Na{sub 0.5}Nd{sub 0.5})TiO{sub 3}-type perovskite can be used to incorporate a high content of sodium in synroc. Synroc samples containing 13.0 wt% waste oxide and 5.7 wt% Na{sub 2}O show very well chemical durability and physical properties. The standard Synroc-C formulation can incorporate only 2 wt% Na{sub 2}O, so this study greatly improved the immobilization ability of sodium in Synroc-related material.

  7. Operating Experience Level 2, Evaluation of Nitrate Bearing Transurani...

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

    015 OE-2 2015-01: Evaluation of Nitrate Bearing Transuranic Waste Streams This Operating Experience Level 2 (OE-2) document provides actions to perform an evaluation of...

  8. Fluid lubricated bearing construction

    DOE Patents [OSTI]

    Dunning, John R.; Boorse, Henry A.; Boeker, Gilbert F.

    1976-01-01

    1. A fluid lubricated thrust bearing assembly comprising, in combination, a first bearing member having a plain bearing surface, a second bearing member having a bearing surface confronting the bearing surface of said first bearing member and provided with at least one spiral groove extending inwardly from the periphery of said second bearing member, one of said bearing members having an axial fluid-tight well, a source of fluid lubricant adjacent to the periphery of said second bearing member, and means for relatively rotating said bearing members to cause said lubricant to be drawn through said groove and to flow between said bearing surfaces, whereby a sufficient pressure is built up between said bearing surfaces and in said well to tend to separate said bearing surfaces.

  9. DRAFT Bear Safety Plan

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

    Bear Safety Plan June 2010 NSAbspRev9.doc 1 Atmospheric Radiation Measurement Climate Research Facility North Slope of AlaskaAdjacent Arctic Ocean (ACRFNSAAAO) Bear Safety ...

  10. Method for recovery of actinides from actinide-bearing scrap and waste nuclear material using O/sub 2/F/sub 2/

    DOE Patents [OSTI]

    Asprey, L.B.; Eller, P.G.

    1984-09-12

    Method for recovery of actinides from nuclear waste material containing sintered and other oxides thereof and from scrap materials containing the metal actinides using O/sub 2/F/sub 2/ to generate the hexafluorides of the actinides present therein. The fluorinating agent, O/sub 2/F/sub 2/, has been observed to perform the above-described tasks at sufficiently low temperatures that there is virtually no damage to the containment vessels. Moreover, the resulting actinide hexafluorides are not detroyed by high temperature reactions with the walls of the reaction vessel. Dioxygen difluoride is readily prepared, stored and transferred to the place of reaction.

  11. Passive magnetic bearing configurations

    DOE Patents [OSTI]

    Post, Richard F.

    2011-01-25

    A journal bearing provides vertical and radial stability to a rotor of a passive magnetic bearing system when the rotor is not rotating and when it is rotating. In the passive magnetic bearing system, the rotor has a vertical axis of rotation. Without the journal bearing, the rotor is vertically and radially unstable when stationary, and is vertically stable and radially unstable when rotating.

  12. Idaho High-Level Waste & Facilities Disposition, Final Environmental...

    Office of Environmental Management (EM)

    Abstract: This EIS analyzes the potential environmental consequences of alternatives for managing high- level waste (HLW) calcine, mixed transuranic wastesodium bearing waste ...

  13. Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 2. Revision 1

    SciTech Connect (OSTI)

    1995-02-01

    This document is the Baseline Inventory Report for the transuranic (alpha-bearing) wastes stored at the Waste Isolation Pilot Plant (WIPP) in New Mexico. Waste stream profiles including origin, applicable EPA codes, typical isotopic composition, typical waste densities, and typical rates of waste generation for each facility are presented for wastes stored at the WIPP.

  14. Bear Creek Valley Watershed

    Broader source: Energy.gov [DOE]

    This document explains the cleanup activities and any use limitations for the land surrounding the Bear Creek Valley Watershed.

  15. Nitrate Salt Bearing Transuranic Waste Container Monitoring

    Broader source: Energy.gov [DOE]

    Supporting Technical Document for the Radiological Release Accident Investigation Report (Phase II Report)

  16. Carbon Bearing Trace Gases

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

    carbon bearing trace gases Carbon Bearing Trace Gases A critical scientific and policy oriented question is what are the present day sources and sinks of carbon dioxide (CO2) in the natural environment and how will these sinks evolve under rising CO2 concentrations and expected climate change and ecosystem response. Sources and sinks of carbon dioxide impart their signature on the distribution, concentration, and isotopic composition of CO2. Spatial and temporal trends (variability) provide

  17. Load responsive hydrodynamic bearing

    DOE Patents [OSTI]

    Kalsi, Manmohan S.; Somogyi, Dezso; Dietle, Lannie L.

    2002-01-01

    A load responsive hydrodynamic bearing is provided in the form of a thrust bearing or journal bearing for supporting, guiding and lubricating a relatively rotatable member to minimize wear thereof responsive to relative rotation under severe load. In the space between spaced relatively rotatable members and in the presence of a liquid or grease lubricant, one or more continuous ring shaped integral generally circular bearing bodies each define at least one dynamic surface and a plurality of support regions. Each of the support regions defines a static surface which is oriented in generally opposed relation with the dynamic surface for contact with one of the relatively rotatable members. A plurality of flexing regions are defined by the generally circular body of the bearing and are integral with and located between adjacent support regions. Each of the flexing regions has a first beam-like element being connected by an integral flexible hinge with one of the support regions and a second beam-like element having an integral flexible hinge connection with an adjacent support region. A least one local weakening geometry of the flexing region is located intermediate the first and second beam-like elements. In response to application of load from one of the relatively rotatable elements to the bearing, the beam-like elements and the local weakening geometry become flexed, causing the dynamic surface to deform and establish a hydrodynamic geometry for wedging lubricant into the dynamic interface.

  18. Mr. John E. Kieling, Bureau Chief Hazardous Waste Bureau

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

    SEP 3 0 2014 New Mexico Environment Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, NM 87508-6303 Subject: Information Regarding the Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container Isolation Plan Dear Mr. Kieling: The purpose of this letter is to provide the information requested in your August 5, 2014 letter regarding the Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container Isolation Plan. The following are enclosed with the letter: * Waste Isolation

  19. Fluid lubricated bearing assembly

    DOE Patents [OSTI]

    Boorse, Henry A.; Boeker, Gilbert F.; Menke, John R.

    1976-01-01

    1. A support for a loaded rotatable shaft comprising in combination on a housing having a fluid-tight cavity encasing an end portion of said shaft, a thrust bearing near the open end of said cavity for supporting the axial thrust of said shaft, said thrust bearing comprising a thrust plate mounted in said housing and a thrust collar mounted on said shaft, said thrust plate having a central opening the peripheral portion of which is hermetically sealed to said housing at the open end of said cavity, and means for supplying a fluid lubricant to said thrust bearing, said thrust bearing having a lubricant-conducting path connecting said lubricant supplying means with the space between said thrust plate and collar intermediate the peripheries thereof, the surfaces of said plate and collar being constructed and arranged to inhibit radial flow of lubricant and, on rotation of said thrust collar, to draw lubricant through said path between the bearing surfaces and to increase the pressure therebetween and in said cavity and thereby exert a supporting force on said end portion of said shaft.

  20. Magnetically leviated superconducting bearing

    DOE Patents [OSTI]

    Weinberger, Bernard R.; Lynds, Jr., Lahmer

    1993-01-01

    A magnetically levitated superconducting bearing includes a magnet (2) mounted on a shaft (12) that is rotatable around an axis of rotation and a Type II superconductor (6) supported on a stator (14) in proximity to the magnet (2). The superconductor (6) is positioned so that when it is cooled to its superconducting state in the presence of a magnetic field, it interacts with the magnet (2) to produce an attractive force that levitates the magnet (2) and supports a load on the shaft (12). The interaction between the superconductor (6) and magnet(2) also produces surface screening currents (8) that generate a repulsive force perpendicular to the load. The bearing also has means for maintaining the superconductor at a temperature below its critical temperature (16, 18). The bearing could also be constructed so the magnet (2) is supported on the stator (14) and the superconductor (6) is mounted on the shaft (12). The bearing can be operated by cooling the superconductor (6) to its superconducting state in the presence of a magnetic field.

  1. Centrifugally decoupling touchdown bearings

    DOE Patents [OSTI]

    Post, Richard F

    2014-06-24

    Centrifugally decoupling mechanical bearing systems provide thin tensioned metallic ribbons contained in a support structure. This assembly rotates around a stationary shaft being centered at low speeds by the action of the metal ribbons. Tension springs are connected on one end to the ribbons and on the other end to the support structure. The ribbons pass through slots in the inner ring of the support structure. The spring preloading thus insures contact (or near-contact) between the ribbons and the shaft at rotation speeds below the transition speed. Above this speed, however, the centrifugal force on the ribbons produces a tensile force on them that exceeds the spring tensile force so that the ribbons curve outward, effectively decoupling them from mechanical contact with the shaft. They still remain, however, in position to act as a touchdown bearing in case of abnormally high transverse accelerations.

  2. Passive magnetic bearing system

    DOE Patents [OSTI]

    Post, Richard F.

    2014-09-02

    An axial stabilizer for the rotor of a magnetic bearing provides external control of stiffness through switching in external inductances. External control also allows the stabilizer to become a part of a passive/active magnetic bearing system that requires no external source of power and no position sensor. Stabilizers for displacements transverse to the axis of rotation are provided that require only a single cylindrical Halbach array in its operation, and thus are especially suited for use in high rotation speed applications, such as flywheel energy storage systems. The elimination of the need of an inner cylindrical array solves the difficult mechanical problem of supplying support against centrifugal forces for the magnets of that array. Compensation is provided for the temperature variation of the strength of the magnetic fields of the permanent magnets in the levitating magnet arrays.

  3. Rotating plug bearing and seal

    DOE Patents [OSTI]

    Wade, Elman E.

    1977-01-01

    A bearing and seal structure for nuclear reactors utilizing rotating plugs above the nuclear reactor vessel. The structure permits lubrication of bearings and seals of the rotating plugs without risk of the lubricant draining into the reactor vessel below. The structure permits lubrication by utilizing a rotating outer race bearing.

  4. Bearing for liquid metal pump

    DOE Patents [OSTI]

    Dickinson, Robert J.; Wasko, John; Pennell, William E.

    1984-01-01

    A liquid metal pump bearing support comprises a series of tangentially oriented spokes that connect the bearing cylinder to the pump internals structure. The spokes may be arranged in a plurality of planes extending from the bearing cylinder to the pump internals with the spokes in one plane being arranged alternately with those in the next plane. The bearing support structure provides the pump with sufficient lateral support for the bearing structure together with the capability of accommodating differential thermal expansion without adversely affecting pump performance.

  5. Bearing construction for refrigeration compresssor

    DOE Patents [OSTI]

    Middleton, Marc G.; Nelson, Richard T.

    1988-01-01

    A hermetic refrigeration compressor has a cylinder block and a crankshaft rotatable about a vertical axis to reciprocate a piston in a cylinder on the cylinder block. A separate bearing housing is secured to the central portion of the cylinder block and extends vertically along the crankshaft, where it carries a pair of roller bearings to journal the crankshaft. The crankshaft has a radially extending flange which is journaled by a thrust-type roller bearing above the bearing housing to absorb the vertical forces on the crankshaft so that all three of the roller bearings are between the crankshaft and the bearing housing to maintain and control the close tolerances required by such bearings.

  6. Interim storage study report

    SciTech Connect (OSTI)

    Rawlins, J.K.

    1998-02-01

    High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration.

  7. ARM - Who's Professor Polar Bear?

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

    Professor Polar Bear? Outreach Home Room News Publications Traditional Knowledge Kiosks Barrow, Alaska Tropical Western Pacific Site Tours Contacts Students Study Hall About ARM Global Warming FAQ Just for Fun Meet our Friends Cool Sites Teachers Teachers' Toolbox Lesson Plans Who's Professor Polar Bear? Professor Polar Bear's home is located at "the top of the world" just north of Barrow, Alaska. Barrow is located at the northernmost point on the continent, 330 miles north of the

  8. Robust and intelligent bearing estimation

    DOE Patents [OSTI]

    Claassen, John P.

    2000-01-01

    A method of bearing estimation comprising quadrature digital filtering of event observations, constructing a plurality of observation matrices each centered on a time-frequency interval, determining for each observation matrix a parameter such as degree of polarization, linearity of particle motion, degree of dyadicy, or signal-to-noise ratio, choosing observation matrices most likely to produce a set of best available bearing estimates, and estimating a bearing for each observation matrix of the chosen set.

  9. Report on the biological monitoring program for Bear Creek at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, 1989-1994

    SciTech Connect (OSTI)

    Hinzman, R.L.; Beauchamp, J.J.; Cada, G.F.; Peterson, M.J.

    1996-04-01

    The Bear Creek Valley watershed drains the area surrounding several closed Oak Ridge Y-12 Plant waste disposal facilities. Past waste disposal practices in the Bear Creek Valley resulted in the contamination of Bear Creek and consequent ecological damage. Ecological monitoring by the Biological Monitoring and Abatement Program (BMAP) was initiated in the Bear Creek watershed in May 1984 and continues at present. Studies conducted during the first year provided a detailed characterization of the benthic invertebrate and fish communities in Bear Creek. The initial characterization was followed by a biological monitoring phase in which studies were conducted at reduced intensities.

  10. EXCITATION OF STRUCTURAL RESONANCE DUE TO A BEARING FAILURE

    SciTech Connect (OSTI)

    Leishear, R; David Stefanko, D

    2007-04-30

    Vibration due to a bearing failure in a pump created significant vibrations in a fifteen foot by fifteen foot by eight feet tall mounting platform due to excitation of resonant frequencies. In this particular application, an 18,000 pound pump was mounted to a structural steel platform. When bearing damage commenced, the platform vibrated with sufficient magnitude that conversations could not be heard within forty feet of the pump. Vibration analysis determined that the frequency of the bearing was coincident to one of the natural frequencies of the pump, which was, in turn, coincident to one of the natural frequencies of the mounting platform. This coincidence of frequencies defines resonance. Resonance creates excessive vibrations when the natural frequency of a structure is coincident to an excitation frequency. In this well documented case, the excitation frequency was related to ball bearing failures. The pump is a forty foot long vertical pump used to mix nuclear waste in 1,300,000 gallon tanks. A 300 horsepower drive motor is mounted to a structural steel platform on top of the tank. The pump hangs down into the tank from above to mix the waste and is inaccessible after installation. Initial awareness of the problem was due to increased noise from the pump. Initial vibration analysis indicated that the vibration levels of the bearing were within the expected range for this type of bearing, and the resonant condition was not obvious. Further analysis consisted of disassembly of the motor to inspect the bearings and extensive vibration monitoring. Vibration data for the bearings was obtained from the manufacturer and compared to measured vibration plots for the pump and mounting platform. Vibration data measured along the length of the pump was available from full scale testing, and vibrations were also measured at the installed pump. One of the axial frequencies of the pump, the platform frequency in the vertical direction, and the ball spin frequency for the

  11. Mixed-mu superconducting bearings

    DOE Patents [OSTI]

    Hull, J.R.; Mulcahy, T.M.

    1998-03-03

    A mixed-mu superconducting bearing is disclosed including a ferrite structure disposed for rotation adjacent a stationary superconductor material structure and a stationary permanent magnet structure. The ferrite structure is levitated by said stationary permanent magnet structure. 9 figs.

  12. Mixed-mu superconducting bearings

    DOE Patents [OSTI]

    Hull, John R. (Hinsdale, IL); Mulcahy, Thomas M. (Western Springs, IL)

    1998-01-01

    A mixed-mu superconducting bearing including a ferrite structure disposed for rotation adjacent a stationary superconductor material structure and a stationary permanent magnet structure. The ferrite structure is levitated by said stationary permanent magnet structure.

  13. TWR Bench-Scale Steam Reforming Demonstration

    SciTech Connect (OSTI)

    D. W. Marshall; N. R. Soelberg

    2003-05-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) was home to nuclear fuel reprocessing activities for decades at the Idaho National Engineering and Environmental Laboratory. As a result of the reprocessing activities, INTEC has accumulated approximately one million gallons of acidic, radioactive, sodium-bearing waste (SBW). The purpose of this demonstration was to investigate a reforming technology, offered by ThermoChem Waste Remediation, LLC, (TWR) for treatment of SBW into a "road ready" waste form that would meet the waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP). TWR is the licensee of Manufacturing Technology Conservation International (MTCI) steam-reforming technology in the field of radioactive waste treatment. A non-radioactive simulated SBW was used based on the known composition of waste tank WM-180 at INTEC. Rhenium was included as a non-radioactive surrogate for technetium. Data was collected to determine the nature and characteristics of the product, the operability of the technology, the composition of the off-gases, and the fate of key radionuclides (cesium and technetium) and volatile mercury compounds. The product contained a low fraction of elemental carbon residues in the cyclone and filter vessel catches. Mercury was quantitatively stripped from the product but cesium, rhenium (Tc surrogate), and the heavy metals were retained. Nitrate residues were about 400 ppm in the product and NOx destruction exceeded 86%. The demonstration was successful.

  14. TWR Bench-Scale Steam Reforming Demonstration

    SciTech Connect (OSTI)

    Marshall, D.W.; Soelberg, N.R.

    2003-05-21

    The Idaho Nuclear Technology and Engineering Center (INTEC) was home to nuclear fuel reprocessing activities for decades at the Idaho National Engineering and Environmental Laboratory. As a result of the reprocessing activities, INTEC has accumulated approximately one million gallons of acidic, radioactive, sodium-bearing waste (SBW). The purpose of this demonstration was to investigate a reforming technology, offered by ThermoChem Waste Remediation, LLC, (TWR) for treatment of SBW into a ''road ready'' waste form that would meet the waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP). TWR is the licensee of Manufacturing Technology Conservation International (MTCI) steam-reforming technology in the field of radioactive waste treatment. A non-radioactive simulated SBW was used based on the known composition of waste tank WM-180 at INTEC. Rhenium was included as a non-radioactive surrogate for technetium. Data was collected to determine the nature and characteristics of the product, the operability of the technology, the composition of the off-gases, and the fate of key radionuclides (cesium and technetium) and volatile mercury compounds. The product contained a low fraction of elemental carbon residues in the cyclone and filter vessel catches. Mercury was quantitatively stripped from the product but cesium, rhenium (Tc surrogate), and the heavy metals were retained. Nitrate residues were about 400 ppm in the product and NOx destruction exceeded 86%. The demonstration was successful.

  15. Hydrostatic bearings for a turbine fluid flow metering device

    DOE Patents [OSTI]

    Fincke, J.R.

    1982-05-04

    A rotor assembly fluid metering device has been improved by development of a hydrostatic bearing fluid system which provides bearing fluid at a common pressure to rotor assembly bearing surfaces. The bearing fluid distribution system produces a uniform film of fluid between bearing surfaces and allows rapid replacement of bearing fluid between bearing surfaces, thereby minimizing bearing wear and corrosion. 3 figs.

  16. Hydrostatic bearings for a turbine fluid flow metering device

    DOE Patents [OSTI]

    Fincke, James R.

    1982-01-01

    A rotor assembly fluid metering device has been improved by development of a hydrostatic bearing fluid system which provides bearing fluid at a common pressure to rotor assembly bearing surfaces. The bearing fluid distribution system produces a uniform film of fluid between bearing surfaces and allows rapid replacement of bearing fluid between bearing surfaces, thereby minimizing bearing wear and corrosion.

  17. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report

    SciTech Connect (OSTI)

    Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Argyle, Mark Don; Lauerhass, Lance; Bendixsen, Carl Lee; Hinckley, Steve Harold

    2000-11-01

    The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

  18. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report

    SciTech Connect (OSTI)

    Herbst, A.K.; McCray, J.A.; Kirkham, R.J.; Pao, J.; Argyle, M.D.; Lauerhass, L.; Bendixsen, C.L.; Hinckley, S.H.

    2000-10-31

    The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

  19. Air bearing vacuum seal assembly

    DOE Patents [OSTI]

    Booth, Rex

    1978-01-01

    An air bearing vacuum seal assembly capable of rotating at the speed of several thousand revolutions per minute using an air cushion to prevent the rotating and stationary parts from touching, and a two stage differential pumping arrangement to maintain the pressure gradient between the air cushion and the vacuum so that the leak rate into the vacuum is, for example, less than 1 .times. 10.sup.-4 Pa m.sup.3 /s. The air bearing vacuum seal has particular application for mounting rotating targets to an evacuated accelerator beam tube for bombardment of the targets with high-power charged particle beams in vacuum.

  20. SEMI-ANNUAL REPORTS FOR - BEAR HEAD LNG CORPORATION AND BEAR...

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

    More Documents & Publications CX-200005: Categorical Exclusion Determination ORDER 3770: BEAR HEAD LNG CORPORATION and BEAR HEAD LNG (USA), LLC Listing of DOEFE Authorizations...

  1. THOR Bench-Scale Steam Reforming Demonstration

    SciTech Connect (OSTI)

    D. W. Marshall; N. R. Soelberg; K. M. Shaber

    2003-05-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) was home to nuclear fuel reprocessing activities for decades at the Idaho National Engineering and Environmental Laboratory. As a result of the reprocessing activities, INTEC has accumulated approximately one million gallons of acidic, radioactive, sodium-bearing waste (SBW). The purpose of this demonstration was to investigate a reforming technology, offered by THORsm Treatment Technologies, LLC, for treatment of SBW into a "road ready" waste form that would meet the waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP). A non-radioactive simulated SBW was used based on the known composition of waste tank WM-180 at INTEC. Rhenium was included as a non-radioactive surrogate for technetium. Data was collected to determine the nature and characteristics of the product, the operability of the technology, the composition of the off-gases, and the fate of key radionuclides (cesium and technetium) and volatile mercury compounds. The product contained a low fraction of elemental carbon residues in the cyclone and filter vessel catches. Mercury was quantitatively stripped from the product but cesium, rhenium (Tc surrogate), and the heavy metals were retained. Nitrates were not detected in the product and NOx destruction exceeded 98%. The demonstration was successful.

  2. THOR Bench-Scale Steam Reforming Demonstration

    SciTech Connect (OSTI)

    Marshall, D.W.; Soelberg, N.R.; Shaber, K.M.

    2003-05-21

    The Idaho Nuclear Technology and Engineering Center (INTEC) was home to nuclear fuel reprocessing activities for decades at the Idaho National Engineering and Environmental Laboratory. As a result of the reprocessing activities, INTEC has accumulated approximately one million gallons of acidic, radioactive, sodium-bearing waste (SBW). The purpose of this demonstration was to investigate a reforming technology, offered by THORsm Treatment Technologies, LLC, for treatment of SBW into a ''road ready'' waste form that would meet the waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP). A non-radioactive simulated SBW was used based on the known composition of waste tank WM-180 at INTEC. Rhenium was included as a non-radioactive surrogate for technetium. Data was collected to determine the nature and characteristics of the product, the operability of the technology, the composition of the off-gases, and the fate of key radionuclides (cesium and technetium) and volatile mercury compounds. The product contained a low fraction of elemental carbon residues in the cyclone and filter vessel catches. Mercury was quantitatively stripped from the product but cesium, rhenium (Tc surrogate), and the heavy metals were retained. Nitrates were not detected in the product and NOx destruction exceeded 98%. The demonstration was successful.

  3. Sodium Bearing Waste Treatment Project ? Countdown to Startup

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

    any readiness review, DOE Federal Project Director Ric Craun said. It is also a testament to the state of readiness that these nine findings will be resolved in time to...

  4. WIPP Nitrate Salt Bearing Waste Container Isolation Plan Implementatio...

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

    Electrical * Restoration of electrical switch stations in the underground, north of S-1950 drift, is complete. b. Ventilation * Air Flow-The underground ventilation system is ...

  5. Review of the Sodium Bearing Waste Treatment Project - Integrated...

    Office of Environmental Management (EM)

    ... The crane operator and the outside support operator (OSO) demonstrated good communication, and the crane operator executed the crane movement activities in a careful and controlled ...

  6. INEEL Summary on Calcination

    SciTech Connect (OSTI)

    Gombert, Dirk

    2003-12-01

    Irradiated nuclear fuel reprocessing to recover 235U and 80Kr began at the INEEL in 1953. The resulting acidic high-level liquid radioactive waste (HLW) was stored in stainless steel tanks in underground concrete vaults. A fluidized-bed calcination process was developed during the 1950s to form a granular calcine solid from the acidic HLW with a seven-fold volume reduction. An engineering-scale demonstration, the Waste Calcining Facility (WCF) was constructed and operated in 1963. After the successful demonstration of the process, the WCF was continued as a production facility through 1981, Calcining 15,000 m3 of HLW to 2,160 m3 of calcine.1 The New Waste Calcining Facility (NWCF) was designed and constructed based on the operating experience of the WCF, and began operation in 1982. With a rated capacity of 3,000 gallons/day, the NWCF continued waste processing operations through May of 2000, resulting in an additional 2,226 m3 of calcine (total current inventory of 4,386 m3).2 During waste processing at the NWCF, sodium-bearing waste (SBW) from decontamination activities was blended with HLW to minimize alkali (sodium and potassium) concentrations in the calciner feed solution. This was necessary due to the propensity of sodium and potassium nitrates to melt in the calciner, causing the bed to agglomerate and interfere with fluidization. However, near the end of HLW processing, work was initiated to modify the calcination process to treat SBW directly, blending it with chemical additives such as aluminum nitrate rather than lower alkali content HLW liquids. The result of this development effort was to increase the operating temperature of the calciner from 500°C to 600°C. The 600°C SBW flowsheet was successfully demonstrated at the NWCF during two separate trials during 1999 and 2000.3, 4 The conclusion from these demonstrations was that operating the existing NWCF at 600°C is a viable method for solidifying SBW, and this concept is currently being evaluated

  7. Bearing system employing a superconductor element

    SciTech Connect (OSTI)

    Agarwala, A.K.

    1992-06-30

    This patent describes a bearing system. It comprises a bearing having a generally planar surface; means maintaining the material at a temperature less than T{sub c}; a magnetic rotor.

  8. Magnetic bearing element with adjustable stiffness

    DOE Patents [OSTI]

    Post, Richard F

    2013-11-12

    A compact magnetic bearing element is provided which is made of permanent magnet discs configured to be capable of the adjustment of the bearing stiffness and levitation force over a wide range.

  9. Argonne National Laboratory Investigates Premature Bearing Failures |

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

    Department of Energy Investigates Premature Bearing Failures Argonne National Laboratory Investigates Premature Bearing Failures August 1, 2013 - 4:13pm Addthis This is an excerpt from the Second Quarter 2013 edition of the Wind Program R&D Newsletter. Researchers at Argonne National Laboratory (ANL) are investigating a leading cause of premature bearing failures in wind turbine gearboxes that can occur within the first 2 years of a gearbox's intended design life (20 years). The bearing

  10. Thin film superconductor magnetic bearings

    DOE Patents [OSTI]

    Weinberger, Bernard R.

    1995-12-26

    A superconductor magnetic bearing includes a shaft (10) that is subject to a load (L) and rotatable around an axis of rotation, a magnet (12) mounted to the shaft, and a stator (14) in proximity to the shaft. The stator (14) has a superconductor thin film assembly (16) positioned to interact with the magnet (12) to produce a levitation force on the shaft (10) that supports the load (L). The thin film assembly (16) includes at least two superconductor thin films (18) and at least one substrate (20). Each thin film (18) is positioned on a substrate (20) and all the thin films are positioned such that an applied magnetic field from the magnet (12) passes through all the thin films. A similar bearing in which the thin film assembly (16) is mounted on the shaft (10) and the magnet (12) is part of the stator (14) also can be constructed.

  11. Low Temperature Waste Immobilization Testing Vol. I

    SciTech Connect (OSTI)

    Russell, Renee L.; Schweiger, Michael J.; Westsik, Joseph H.; Hrma, Pavel R.; Smith, D. E.; Gallegos, Autumn B.; Telander, Monty R.; Pitman, Stan G.

    2006-09-14

    The Pacific Northwest National Laboratory (PNNL) is evaluating low-temperature technologies to immobilize mixed radioactive and hazardous waste. Three waste formsalkali-aluminosilicate hydroceramic cement, Ceramicrete phosphate-bonded ceramic, and DuraLith alkali-aluminosilicate geopolymerwere selected through a competitive solicitation for fabrication and characterization of waste-form properties. The three contractors prepared their respective waste forms using simulants of a Hanford secondary waste and Idaho sodium bearing waste provided by PNNL and characterized their waste forms with respect to the Toxicity Characteristic Leaching Procedure (TCLP) and compressive strength. The contractors sent specimens to PNNL, and PNNL then conducted durability (American National Standards Institute/American Nuclear Society [ANSI/ANS] 16.1 Leachability Index [LI] and modified Product Consistency Test [PCT]) and compressive strength testing (both irradiated and as-received samples). This report presents the results of these characterization tests.

  12. ICPP tank farm closure study. Volume 1

    SciTech Connect (OSTI)

    Spaulding, B.C.; Gavalya, R.A.; Dahlmeir, M.M.

    1998-02-01

    The disposition of INEEL radioactive wastes is now under a Settlement Agreement between the DOE and the State of Idaho. The Settlement Agreement requires that existing liquid sodium bearing waste (SBW), and other liquid waste inventories be treated by December 31, 2012. This agreement also requires that all HLW, including calcined waste, be disposed or made road ready to ship from the INEEL by 2035. Sodium bearing waste (SBW) is produced from decontamination operations and HLW from reprocessing of SNF. SBW and HLW are radioactive and hazardous mixed waste; the radioactive constituents are regulated by DOE and the hazardous constituents are regulated by the Resource Conservation and Recovery Act (RCRA). Calcined waste, a dry granular material, is produced in the New Waste Calcining Facility (NWCF). Two primary waste tank storage locations exist at the ICPP: Tank Farm Facility (TFF) and the Calcined Solids Storage Facility (CSSF). The TFF has the following underground storage tanks: four 18,400-gallon tanks (WM 100-102, WL 101); four 30,000-gallon tanks (WM 103-106); and eleven 300,000+ gallon tanks. This includes nine 300,000-gallon tanks (WM 182-190) and two 318,000 gallon tanks (WM 180-181). This study analyzes the closure and subsequent use of the eleven 300,000+ gallon tanks. The 18,400 and 30,000-gallon tanks were not included in the work scope and will be closed as a separate activity. This study was conducted to support the HLW Environmental Impact Statement (EIS) waste separations options and addresses closure of the 300,000-gallon liquid waste storage tanks and subsequent tank void uses. A figure provides a diagram estimating how the TFF could be used as part of the separations options. Other possible TFF uses are also discussed in this study.

  13. Waste form product characteristics

    SciTech Connect (OSTI)

    Taylor, L.L.; Shikashio, R.

    1995-01-01

    The Department of Energy has operated nuclear facilities at the Idaho National Engineering Laboratory (INEL) to support national interests for several decades. Since 1953, it has supported the development of technologies for the storage and reprocessing of spent nuclear fuels (SNF) and the resultant wastes. However, the 1992 decision to discontinue reprocessing of SNF has left nearly 768 MT of SNF in storage at the INEL with unspecified plans for future dispositioning. Past reprocessing of these fuels for uranium and other resource recovery has resulted in the production of 3800 M{sup 3} calcine and a total inventory of 7600 M{sup 3} of radioactive liquids (1900 M{sup 3} destined for immediate calcination and the remaining sodium-bearing waste requiring further treatment before calcination). These issues, along with increased environmental compliance within DOE and its contractors, mandate operation of current and future facilities in an environmentally responsible manner. This will require satisfactory resolution of spent fuel and waste disposal issues resulting from the past activities. A national policy which identifies requirements for the disposal of SNF and high level wastes (HLW) has been established by the Nuclear Waste Policy Act (NWPA) Sec.8,(b) para(3)) [1982]. The materials have to be conditioned or treated, then packaged for disposal while meeting US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) regulations. The spent fuel and HLW located at the INEL will have to be put into a form and package that meets these regulatory criteria. The emphasis of Idaho Chemical Processing Plant (ICPP) future operations has shifted toward investigating, testing, and selecting technologies to prepare current and future spent fuels and waste for final disposal. This preparation for disposal may include mechanical, physical and/or chemical processes, and may differ for each of the various fuels and wastes.

  14. Valve assembly having remotely replaceable bearings

    DOE Patents [OSTI]

    Johnson, Evan R.; Tanner, David E.

    1980-01-01

    A valve assembly having remotely replaceable bearings is disclosed wherein a valve disc is supported within a flow duct for rotation about a pair of axially aligned bearings, one of which is carried by a spindle received within a diametral bore in the valve disc, and the other of which is carried by a bearing support block releasably mounted on the duct circumferentially of an annular collar on the valve disc coaxial with its diametrical bore. The spindle and bearing support block are adapted for remote removal to facilitate servicing or replacement of the valve disc support bearings.

  15. Hydrostatic bearings for a turbine fluid flow metering device

    DOE Patents [OSTI]

    Fincke, J.R.

    1980-05-02

    A rotor assembly fluid metering device has been improved by development of a hydrostatic bearing fluid system which provides bearing fluid at a common pressure to rotor assembly bearing surfaces. The bearing fluid distribution system produces a uniform film of fluid distribution system produces a uniform film of fluid between bearing surfaces and allows rapid replacement of bearing fluid between bearing surfaces, thereby minimizing bearing wear and corrosion.

  16. Waste Guide

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

    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. Estimating Waste Inventory and Waste Tank Characterization |...

    Office of Environmental Management (EM)

    Estimating Waste Inventory and Waste Tank Characterization Estimating Waste Inventory and Waste Tank Characterization Summary Notes from 28 May 2008 Generic Technical Issue ...

  18. Negotiating equity for management of DOE wastes

    SciTech Connect (OSTI)

    Carnes, S.A.

    1994-09-01

    One important factor frustrating optimal management of Department of Energy (DOE)-complex wastes is the inability to use licensed and permitted facilities systematically. Achieving the goal of optimal use of DOE`s waste management facilities is politically problematic for two reasons. First, no locale wants to bear a disproportionate burden from DOE wastes. Second, the burden imposed by additional wastes transported from one site to another is difficult to characterize. To develop a viable framework for equitably distributing these burdens while achieving efficient use of all DOE waste management facilities, several implementation and equity issues must be addressed and resolved. This paper discusses stakeholder and equity issues and proposes a framework for joint research and action that could facilitate equity negotiations among stakeholder and move toward a more optimal use of DOE`s waste management capabilities.

  19. ORDER 3770: BEAR HEAD LNG CORPORATION and BEAR HEAD LNG (USA), LLC |

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

    Department of Energy 3770: BEAR HEAD LNG CORPORATION and BEAR HEAD LNG (USA), LLC ORDER 3770: BEAR HEAD LNG CORPORATION and BEAR HEAD LNG (USA), LLC OPINION AND ORDER GRANTING LONG-TERM, MULTI-CONTRACT AUTHORIZATION TO EXPORT U.S.-SOURCED NATURAL GAS BY PIPELINE TO CANADA FOR LIQUEFACTION AND RE-EXPORT IN THE FORM OF LIQUEFIED NATURAL GAS TO NON-FREE TRADE AGREEMENT COUNTRIES On February 5, 2016, the Energy Department issued an authorization to Bear Head LNG Corporation and Bear Head LNG

  20. Tank Waste and Waste Processing | Department of Energy

    Office of Environmental Management (EM)

    Tank Waste and Waste Processing Tank Waste and Waste Processing Tank Waste and Waste Processing The Defense Waste Processing Facility set a record by producing 267 canisters filled ...

  1. Production of iron from metallurgical waste

    SciTech Connect (OSTI)

    Hendrickson, David W; Iwasaki, Iwao

    2013-09-17

    A method of recovering metallic iron from iron-bearing metallurgical waste in steelmaking comprising steps of providing an iron-bearing metallurgical waste containing more than 55% by weight FeO and FeO equivalent and a particle size of at least 80% less than 10 mesh, mixing the iron-bearing metallurgical waste with a carbonaceous material to form a reducible mixture where the carbonaceous material is between 80 and 110% of the stoichiometric amount needed to reduce the iron-bearing waste to metallic iron, and as needed additions to provide a silica content between 0.8 and 8% by weight and a ratio of CaO/SiO.sub.2 between 1.4 and 1.8, forming agglomerates of the reducible mixture over a hearth material layer to protect the hearth, heating the agglomerates to a higher temperature above the melting point of iron to form nodules of metallic iron and slag material from the agglomerates by melting.

  2. In-plant recycling of ironmaking waste materials at Pohang Works

    SciTech Connect (OSTI)

    Kim, C.H.; Jung, S.

    1997-12-31

    The regulations for pollution control are being strengthened more year by year. Therefore, waste materials containing iron oxides are being increasingly used in the sinter plant. As a result, waste materials recycling in the sintering process not only reduces costs by eliminating waste disposal costs and utilizing Fe bearing by-products to replace iron ores and flux materials, but gives fuel rate benefits to the sintering process through heat of oxidizing of Fe bearing materials and combustion of coke fines carried with Fe Bearing by-products.

  3. Bear Creek Wind Farm | Open Energy Information

    Open Energy Info (EERE)

    energy Facility Type Commercial Scale Wind Facility Status In Service Owner Babcock & Brown owns majority Developer CEI Iberdrola Energy Purchaser PPL Corp. Location Near Bear...

  4. Sabdia's Radial Flow Air Bearing Heat Exchanger

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

    The Sandia Cooler) vapor chamber hydrodynamic air bearing heat-sink-impeller Dr. Jeff Koplow, jkoplow@sandia.gov Sandia National Laboratories Project Summary Timeline: Start date: ...

  5. SEMI-ANNUAL REPORTS FOR - BEAR HEAD LNG CORPORATION AND BEAR...

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

    SEMI-ANNUAL REPORTS FOR - BEAR HEAD LNG CORPORATION AND BEAR HEAD (USA) LLC - FE DKT. NO. ... REPORTS FOR LNG DEVELOPMENT COMPANY, LLC (DBA Oregon LNG) - FE DKT. NO. 12-48-LNG - ...

  6. Gearbox Reliability Collaborative Bearing Calibration

    SciTech Connect (OSTI)

    van Dam, J.

    2011-10-01

    NREL has initiated the Gearbox Reliability Collaborative (GRC) to investigate the root cause of the low wind turbine gearbox reliability. The GRC follows a multi-pronged approach based on a collaborative of manufacturers, owners, researchers and consultants. The project combines analysis, field testing, dynamometer testing, condition monitoring, and the development and population of a gearbox failure database. At the core of the project are two 750kW gearboxes that have been redesigned and rebuilt so that they are representative of the multi-megawatt gearbox topology currently used in the industry. These gearboxes are heavily instrumented and are tested in the field and on the dynamometer. This report discusses the bearing calibrations of the gearboxes.

  7. Methods and systems for micro bearings

    DOE Patents [OSTI]

    Stalford, Harold L

    2015-01-27

    A micro drive assembly may comprise a substrate, a micro shaft oriented in-plane with the substrate and at least one micro bearing to support rotation of the micro shaft. The micro shaft and micro bearing may be in or less than the micrometer domain.

  8. Methods and systems for micro bearings

    DOE Patents [OSTI]

    Stalford, Harold L.

    2012-10-09

    A micro drive assembly may comprise a substrate, a micro shall oriented in-plane with the substrate and at least one micro bearing to support rotation of the micro shaft. The micro shaft and micro bearing may be in or less than the micrometer domain.

  9. Self-adjusting magnetic bearing systems

    DOE Patents [OSTI]

    Post, R.F.

    1998-07-21

    A self-adjusting magnetic bearing automatically adjusts the parameters of an axially unstable magnetic bearing such that its force balance is maintained near the point of metastable equilibrium. Complete stabilization can be obtained with the application of weak restoring forces either from a mechanical bearing (running at near-zero load, thus with reduced wear) or from the action of residual eddy currents in a snubber bearing. In one embodiment, a torque is generated by the approach of a slotted pole to a conducting plate. The torque actuates an assembly which varies the position of a magnetic shunt to change the force exerted by the bearing. Another embodiment achieves axial stabilization by sensing vertical displacements in a suspended bearing element, and using this information in an electrical servo system. In a third embodiment, as a rotating eddy current exciter approaches a stationary bearing, it heats a thermostat which actuates an assembly to weaken the attractive force between the two bearing elements. An improved version of an electromechanical battery utilizing the designs of the various embodiments is described. 7 figs.

  10. Self-adjusting magnetic bearing systems

    DOE Patents [OSTI]

    Post, Richard F.

    1998-01-01

    A self-adjusting magnetic bearing automatically adjusts the parameters of an axially unstable magnetic bearing such that its force balance is maintained near the point of metastable equilibrium. Complete stabilization can be obtained with the application of weak restoring forces either from a mechanical bearing (running at near-zero load, thus with reduced wear) or from the action of residual eddy currents in a snubber bearing. In one embodiment, a torque is generated by the approach of a slotted pole to a conducting plate. The torque actuates an assembly which varies the position of a magnetic shunt to change the force exerted by the bearing. Another embodiment achieves axial stabilization by sensing vertical displacements in a suspended bearing element, and using this information in an electrical servo system. In a third embodiment, as a rotating eddy current exciter approaches a stationary bearing, it heats a thermostat which actuates an assembly to weaken the attractive force between the two bearing elements. An improved version of an electromechanical battery utilizing the designs of the various embodiments is described.

  11. Attenuation of heavy metal leaching from hazardous wastes by co-disposal of wastes

    SciTech Connect (OSTI)

    Bae, Wookeun; Shin, Eung Bai; Lee, Kil Chul; Kim, Jae Hyung

    1996-12-31

    The potential hazard of landfill wastes was previously evaluated by examining the extraction procedures for individual waste, although various wastes were co-disposed of in actual landfills. This paper investigates the reduction of extraction-procedure toxicity by co-disposing various combinations of two wastes. When two wastes are mixed homogeneously, the extraction of heavy metals from the waste mixture is critically affected by the extract pH. Thus, co-disposal wastes will have a resultant pH between the pH values of its constituent. The lower the resultant pH, the lower the concentrations of heavy metals in the extract. When these wastes are extracted sequentially, the latter extracted waste has a stronger influence on the final concentration of heavy metals in the extract. Small-scale lysimeter experiments confirm that when heavy-metal-bearing leachates Generated from hazardous-waste lysimeters are passed through a nonhazardous-waste lysimeter filled with compost, briquette ash, or refuse-incineration ashes, the heavy-metal concentration in the final leachates decreases significantly. Thus, the heavy-metal leaching could be attenuated if a less extraction-procedure-toxic waste were placed at the bottom of a landfill. 3 refs., 4 figs., 5 tabs.

  12. Rotor and bearing system for a turbomachine

    DOE Patents [OSTI]

    Lubell, Daniel; Weissert, Dennis

    2006-09-26

    A rotor and bearing system for a turbomachine. The turbomachine includes a drive shaft, an impeller positioned on the drive shaft, and a turbine positioned on the drive shaft proximate to the impeller. The bearing system comprises one gas journal bearing supporting the drive shaft between the impeller and the turbine. The area between the impeller and the turbine is an area of increased heat along the drive shaft in comparison to other locations along the drive shaft. The section of the drive shaft positioned between impeller and the turbine is also a section of the drive shaft that experiences increased stressed and load in the turbomachine. The inventive bearing machine system positions only one radial bearing in this area of increased stress and load.

  13. Glass Development for Treatment of LANL Evaporator Bottoms Waste

    SciTech Connect (OSTI)

    DE Smith; GF Piepel; GW Veazey; JD Vienna; ML Elliott; RK Nakaoka; RP Thimpke

    1998-11-20

    Vitrification is an attractive treatment option for meeting the stabilization and final disposal requirements of many plutonium (Pu) bearing materials and wastes at the Los Alamos National Laboratory (LANL) TA-55 facility, Rocky Flats Environmental Technology Site (RFETS), Hanford, and other Department of Energy (DOE) sites. The Environmental Protection Agency (EPA) has declared that vitrification is the "best demonstrated available technology" for high- level radioactive wastes (HLW) (Federal Register 1990) and has produced a handbook of vitriilcation technologies for treatment of hazardous and radioactive waste (US EPA, 1992). This technology has been demonstrated to convert Pu-containing materials (Kormanos, 1997) into durable (Lutze, 1988) and accountable (Forsberg, 1995) waste. forms with reduced need for safeguarding (McCulhun, 1996). The composition of the Evaporator Bottoms Waste (EVB) at LANL, like that of many other I%-bearing materials, varies widely and is generally unpredictable. The goal of this study is to optimize the composition of glass for EVB waste at LANL, and present the basic techniques and tools for developing optimized glass compositions for other Pu-bearing materials in the complex. This report outlines an approach for glass formulation with fixed property restrictions, using glass property-composition databases. This approach is applicable to waste glass formulation for many variable waste streams and vitrification technologies.. Also reported are the preliminary property data for simulated evaporator bottom glasses, including glass viscosity and glass leach resistance using the Toxicity Characteristic Leaching Procedure (TCLP).

  14. Thrust bearing assembly for a downhole drill motor

    SciTech Connect (OSTI)

    Geczy, B. A.

    1985-12-24

    A bidirectional thrust bearing assembly is used between a downhole fluid motor and a rock bit for drilling oil wells. The bearing assembly has a stationary housing with radial journal bearing sleeves and a rotatable drive shaft also having radial bearing sleeves. A pair of oppositely facing thrust bearing rings are mounted in the housing. A second pair of thrust bearing rings are mounted on the shaft so as to have faces opposing the bearing faces on the first pair of rings. Belleville springs resiliently bias a pair of the thrust bearing rings apart and carry the thrust load between such rings. Each ring has a plurality of inserts of hard material, preferably polycrystalline diamond, at the bearing surface. Means are provided for circulating drilling fluid from the motor through the thrust bearing faces for forming hydrodynamic fluid bearing films in the bearing interfaces.

  15. The Waste Isolation Pilot Plant Hazardous Waste Facility Permit...

    Office of Environmental Management (EM)

    The Waste Isolation Pilot Plant Hazardous Waste Facility Permit, Waste Analysis Plan The Waste Isolation Pilot Plant Hazardous Waste Facility Permit, Waste Analysis Plan This ...

  16. Compressor ported shroud for foil bearing cooling

    DOE Patents [OSTI]

    Elpern, David G.; McCabe, Niall; Gee, Mark

    2011-08-02

    A compressor ported shroud takes compressed air from the shroud of the compressor before it is completely compressed and delivers it to foil bearings. The compressed air has a lower pressure and temperature than compressed outlet air. The lower temperature of the air means that less air needs to be bled off from the compressor to cool the foil bearings. This increases the overall system efficiency due to the reduced mass flow requirements of the lower temperature air. By taking the air at a lower pressure, less work is lost compressing the bearing cooling air.

  17. Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Federal Operational Readiness Review

    Office of Environmental Management (EM)

    Federal Operational Readiness Review June 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background

  18. Bear Head LNG Corporation and Bear Head LNG (USA), LLC- FE Dkt No. 15-14-NG

    Broader source: Energy.gov [DOE]

    On January 23, 2015, Bear Head LNG Corporation and Bear Head LNG (USA), LLC (together, “Bear Head LNG”), filed an application for long-term, multi-contract authorization to engage in imports from,...

  19. Beijing Jingye Bearing Manufacture for Rolling Mills Co Ltd ...

    Open Energy Info (EERE)

    Beijing Jingye Bearing Manufacture for Rolling Mills Co Ltd Jump to: navigation, search Name: Beijing Jingye Bearing Manufacture for Rolling Mills Co Ltd Place: Beijing...

  20. Statistics Show Bearing Problems Cause the Majority of Wind Turbine...

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

    Statistics Show Bearing Problems Cause the Majority of Wind Turbine Gearbox Failures Statistics Show Bearing Problems Cause the Majority of Wind Turbine Gearbox Failures September ...

  1. Bear Trap Hot Spring Pool & Spa Low Temperature Geothermal Facility...

    Open Energy Info (EERE)

    Trap Hot Spring Pool & Spa Low Temperature Geothermal Facility Jump to: navigation, search Name Bear Trap Hot Spring Pool & Spa Low Temperature Geothermal Facility Facility Bear...

  2. Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence...

    Energy Savers [EERE]

    Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence: Literature Review and DOE-LM Site Surveys Uranium-Bearing Evaporite Mineralization Influencing Plume ...

  3. Potential dispositioning flowsheets for ICPP SNF and wastes

    SciTech Connect (OSTI)

    Olson, A.L.; Anderson, P.A.; Bendixsen, C.L.

    1995-11-01

    The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Laboratory (INEL), has reprocessed irradiated nuclear fuels for the US Department of Energy (DOE) since 1953. This activity resulted mainly in the recovery of uranium and the management of the resulting wastes. The acidic radioactive high-level liquid waste was routinely stored in stainless steel tanks and then calcined to form a dry granular solid. The calcine is stored in stainless steel bins that are housed in underground concrete vaults. In April 1992, the DOE discontinued the practice of reprocessing irradiated nuclear fuels. This decision has left a legacy of 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste), 3800 cubic meters of calcine waste, and 289 metric tons of heavy metal within unprocessed spent nuclear fuel (SNF) left in inventory at the ICPP. The nation`s radioactive waste policy has been established by the Nuclear Waste Policy Act (NWPA), which requires the final disposal of SNF and radioactive waste in accordance with US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) standards. In accordance with these regulations and other legal agreements between the State of Idaho and the DOE, the DOE must, among other requirements, (1) complete a final Environmental Impact Statement by April 30, 1995, (2) evaluate and test sodium-bearing waste pre-treatment technologies, (3) select the sodium-bearing and calcine waste pre-treatment technology, if necessary, by June 1, 1995, and (4) select a technology for converting calcined waste into an appropriate disposal form by June 1, 1995.

  4. Bear Valley Electric Service- Solar Initiative Program

    Broader source: Energy.gov [DOE]

    Bear Valley Electric Service is providing an incentive for their residential customers to install photovoltaic (PV) systems. Systems must be sized to provide no more than 90% of the calculated or...

  5. Sun Bear Solar Ltd | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Name: Sun Bear Solar Ltd Place: Hong Kong Sector: Solar Product: Hong Kong-based firm that manufactures solar product equipment, such as PV glass,...

  6. Chemical Equilibrium of Aluminate in Hanford Tank Waste Originating from Tanks 241-AN-105 and 241-AP-108

    SciTech Connect (OSTI)

    McCoskey, Jacob K.; Cooke, Gary A.; Herting, Daniel L.

    2015-09-23

    The purposes of the study described in this document follow; Determine or estimate the thermodynamic equilibrium of gibbsite in contact with two real tank waste supernatant liquids through both dissolution of gibbsite (bottom-up approach) and precipitation of aluminum-bearing solids (top-down approach); determine or estimate the thermodynamic equilibrium of a mixture of gibbsite and real tank waste saltcake in contact with real tank waste supernatant liquid through both dissolution of gibbsite and precipitation of aluminum-bearing solids; and characterize the solids present after equilibrium and precipitation of aluminum-bearing solids.

  7. Flywheel energy storage with superconductor magnetic bearings

    DOE Patents [OSTI]

    Weinberger, Bernard R.; Lynds, Jr., Lahmer; Hull, John R.

    1993-01-01

    A flywheel having superconductor bearings has a lower drag to lift ratio that translates to an improvement of a factor of ten in the rotational decay rate. The lower drag results from the lower dissipation of melt-processed YBCO, improved uniformity of the permanent magnet portion of the bearings, operation in a different range of vacuum pressure from that taught by the art, and greater separation distance from the rotating members of conductive materials.

  8. CONTENTS Gas Hydrate-Bearing Sand

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

    CONTENTS Gas Hydrate-Bearing Sand Reservoir Systems in the Offshore of India: Results of the India National Gas Hydrate Program Expedition 02 ..............1 The Potential for Abiotic Methane in Arctic Gas Hydrates .................9 Coupled Thermo-Hydro-Chemo- Mechanical (THCM) Models for Hydrate-Bearing Sediments ....13 Emerging Issues in the Development of Geologic Models for Gas Hydrate Numerical Simulation ................19 Announcements ...................... 23 * DOE/NETL FY2016 Methane

  9. The Waste Isolation Pilot Plant Hazardous Waste Facility Permit, Waste

    Office of Environmental Management (EM)

    Analysis Plan | Department of Energy The Waste Isolation Pilot Plant Hazardous Waste Facility Permit, Waste Analysis Plan The Waste Isolation Pilot Plant Hazardous Waste Facility Permit, Waste Analysis Plan This document was used to determine facts and conditions during the Department of Energy Accident Investigation Board's investigation into the radiological release event at the Waste Isolation Pilot Plant. Additional documents referenced and listed in the Phase 2 Radiological Release

  10. Promising Technology: Magnetic Bearing Variable-Speed Centrifugal Chillers

    Broader source: Energy.gov [DOE]

    Magnetic bearing variable speed centrifugal chillers save energy compared to conventional chillers by eliminating friction with the magnetic bearings and by improving efficiency at partial loads with the variable speed drive. In addition to saving energy, the magnetic bearings eliminate the maintenance costs associated with lubricating conventional metal bearings.

  11. Bearing assemblies, apparatuses, and motor assemblies using the same

    DOE Patents [OSTI]

    Sexton, Timothy N.; Cooley, Craig H.; Knuteson, Cody W.

    2015-12-29

    Various embodiments of the invention relate to bearing assemblies, apparatuses and motor assemblies that include geometric features configured to impart a selected amount of heat transfer and/or hydrodynamic film formation. In an embodiment, a bearing assembly may include a plurality of superhard bearing pads distributed circumferentially about an axis. At least some of the plurality of superhard bearing pads may include a plurality of sub-superhard bearing elements defining a bearing surface. At least some of the plurality of sub-superhard bearing elements may be spaced from one another by one or more voids to impart a selected amount of heat transfer and hydrodynamic film formation thereon during operation. The bearing assembly may also include a support ring that carries the plurality of superhard bearing pads. In addition, at least a portion of the sub-superhard bearing elements may extend beyond the support ring.

  12. Method for changing removable bearing for a wind turbine generator

    DOE Patents [OSTI]

    Bagepalli, Bharat Sampathkumaran; Jansen, Patrick Lee; Gadre, Aniruddha Dattatraya

    2008-04-22

    A wind generator having removable change-out bearings includes a rotor and a stator, locking bolts configured to lock the rotor and stator, a removable bearing sub-assembly having at least one shrunk-on bearing installed, and removable mounting bolts configured to engage the bearing sub-assembly and to allow the removable bearing sub-assembly to be removed when the removable mounting bolts are removed.

  13. Removable bearing arrangement for a wind turbine generator

    DOE Patents [OSTI]

    Bagepalli, Bharat Sampathkumaran; Jansen, Patrick Lee; Gadre, Aniruddha Dattatraya

    2010-06-15

    A wind generator having removable change-out bearings includes a rotor and a stator, locking bolts configured to lock the rotor and stator, a removable bearing sub-assembly having at least one shrunk-on bearing installed, and removable mounting bolts configured to engage the bearing sub-assembly and to allow the removable bearing sub-assembly to be removed when the removable mounting bolts are removed.

  14. Mr. John E. Kieling, Bureau Chief Hazardous Waste Bureau

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

    3 0 2014 New Mexico Environment Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, NM 87508-6303 Mr. Tom Blaine, Division Director Environmental Health Division Harold Runnels Building 1190 Saint Francis Drive, Room 4050 Santa Fe, NM 87502-5469 Subject: Written Notice Regarding Application of EPA Hazardous Waste Number D001 to Some Nitrate Salt Bearing Waste Containers Dear Mr. Kieling and Mr. Blaine: The purpose of this letter is to provide you written notice that the Department of

  15. Mr. John E. Kieling, Bureau Chief Hazardous Waste Bureau

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

    SEP 1 7 2014 New Mexico Environment Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, NM 87508-6303 Subject: Update to the Information provided to the New Mexico Environment Department Regarding the WIPP Nitrate Salt Bearing Waste Container Isolation Plan dated September 5, 2014 Reference: New Mexico Environment Department Correspondence from Ryan Flynn, Secretary, to Jose Franco, Carlsbad Field Office and Robert L. McQuinn, Nuclear Waste Partnership LLC, dated August 7, 2014, subject:

  16. Process for depositing Cr-bearing layer

    DOE Patents [OSTI]

    Ellis, Timothy W.; Lograsso, Thomas A.; Eshelman, Mark A.

    1995-05-09

    A method of applying a Cr-bearing layer to a substrate, comprises introducing an organometallic compound, in vapor or solid powder form entrained in a carrier gas to a plasma of an inductively coupled plasma torch or device to thermally decompose the organometallic compound and contacting the plasma and the substrate to be coated so as to deposit the Cr-bearing layer on the substrate. A metallic Cr, Cr alloy or Cr compound such as chromium oxide, nitride and carbide can be provided on the substrate. Typically, the organometallic compound is introduced to an inductively coupled plasma torch that is disposed in ambient air so to thermally decompose the organometallic compound in the plasma. The plasma is directed at the substrate to deposit the Cr-bearing layer or coating on the substrate.

  17. Robust Bearing Estimation for 3-Component Stations

    SciTech Connect (OSTI)

    Claassen, John P.

    1999-06-03

    A robust bearing estimation process for 3-component stations has been developed and explored. The method, called SEEC for Search, Estimate, Evaluate and Correct, intelligently exploits the in- herent information in the arrival at every step of the process to achieve near-optimal results. In particular, the approach uses a consistent framework to define the optimal time-frequency windows on which to make estimates, to make the bearing estimates themselves, to construct metrics helpful in choosing the better estimates or admitting that the bearing is immeasurable, andjinally to apply bias corrections when calibration information is available to yield a single final estimate. The method was applied to a small but challenging set of events in a seismically active region. The method demonstrated remarkable utility by providing better estimates and insights than previously available. Various monitoring implications are noted fiom these findings.

  18. Robust bearing estimation for 3-component stations

    SciTech Connect (OSTI)

    CLAASSEN,JOHN P.

    2000-02-01

    A robust bearing estimation process for 3-component stations has been developed and explored. The method, called SEEC for Search, Estimate, Evaluate and Correct, intelligently exploits the inherent information in the arrival at every step of the process to achieve near-optimal results. In particular the approach uses a consistent framework to define the optimal time-frequency windows on which to make estimates, to make the bearing estimates themselves, to construct metrics helpful in choosing the better estimates or admitting that the bearing is immeasurable, and finally to apply bias corrections when calibration information is available to yield a single final estimate. The algorithm was applied to a small but challenging set of events in a seismically active region. It demonstrated remarkable utility by providing better estimates and insights than previously available. Various monitoring implications are noted from these findings.

  19. Process for depositing Cr-bearing layer

    DOE Patents [OSTI]

    Ellis, T.W.; Lograsso, T.A.; Eshelman, M.A.

    1995-05-09

    A method of applying a Cr-bearing layer to a substrate, comprises introducing an organometallic compound, in vapor or solid powder form entrained in a carrier gas to a plasma of an inductively coupled plasma torch or device to thermally decompose the organometallic compound and contacting the plasma and the substrate to be coated so as to deposit the Cr-bearing layer on the substrate. A metallic Cr, Cr alloy or Cr compound such as chromium oxide, nitride and carbide can be provided on the substrate. Typically, the organometallic compound is introduced to an inductively coupled plasma torch that is disposed in ambient air so to thermally decompose the organometallic compound in the plasma. The plasma is directed at the substrate to deposit the Cr-bearing layer or coating on the substrate. 7 figs.

  20. Wear Analysis of Wind Turbine Gearbox Bearings

    SciTech Connect (OSTI)

    Blau, Peter Julian; Walker, Larry R; Xu, Hanbing; Parten, Randy J; Qu, Jun; Geer, Tom

    2010-04-01

    The objective of this effort was to investigate and characterize the nature of surface damage and wear to wind turbine gearbox bearings returned from service in the field. Bearings were supplied for examination by S. Butterfield and J. Johnson of the National Wind Technology Center (NREL), Boulder, Colorado. Studies consisted of visual examination, optical and electron microscopy, dimensional measurements of wear-induced macro-scale and micro-scale features, measurements of macro- and micro-scale hardness, 3D imaging of surface damage, studies of elemental distributions on fracture surfaces, and examinations of polished cross-sections of surfaces under various etched and non-etched conditions.

  1. Waste Treatment Plant Overview

    Office of Environmental Management (EM)

    Waste Isolation Pilot Plant Waste Isolation Pilot Plant Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations The mission of the Waste Isolation Pilot Plant site is to provide permanent, underground disposal of TRU and TRU-mixed wastes (wastes that also have hazardous chemical components). TRU waste consists of clothing, tools, and debris left from the research and production of nuclear weapons. TRU waste is

  2. HLW Glass Waste Loadings

    Office of Environmental Management (EM)

    HLW Glass Waste Loadings Ian L. Pegg Vitreous State Laboratory The Catholic University of ... (JHCM) technology Factors affecting waste loadings Waste loading requirements ...

  3. Hot isostatic press waste option study report

    SciTech Connect (OSTI)

    Russell, N.E.; Taylor, D.D.

    1998-02-01

    A Settlement Agreement between the Department of Energy and the State of Idaho mandates that all high-level radioactive waste now stored at the Idaho Chemical Processing Plant be treated so that it is ready to move out of Idaho for disposal by the target date of 2035. This study investigates the immobilization of all Idaho Chemical Processing Plant calcine, including calcined sodium bearing waste, via the process known as hot isostatic press, which produces compact solid waste forms by means of high temperature and pressure (1,050 C and 20,000 psi), as the treatment method for complying with the settlement agreement. The final waste product would be contained in stainless-steel canisters, the same type used at the Savannah River Site for vitrified waste, and stored at the Idaho National Engineering and Environmental Laboratory until a national geological repository becomes available for its disposal. The waste processing period is from 2013 through 2032, and disposal at the High Level Waste repository will probably begin sometime after 2065.

  4. Waste Hoist

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

    Primary Hoist: 45-ton Rope-Guide Friction Hoist Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides. With a 45-ton capacity, it was the largest friction hoist in the world when it was built in 1986. Largest friction hoist in the world when it was built in 1985 Hoist deck footprint: approximately 3m wide x 5m long Hoist deck height: approximately 3m wide x 7m high Access height to the waste hoist deck is limited by a 4 m high door

  5. Waste Hoist

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

    Primary Hoist: 45-ton Rope-Guide Friction Hoist Largest friction hoist in the world when it was built in 1985 Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides (uses a balanced counterweight and tail ropes). With a 45-ton capacity, it was the largest friction hoist in the world when it was built in 1986. Hoist deck footprint: 2.87m wide x 4.67m long Hoist deck height: 2.87m wide x 7.46m high Access height to the waste hoist deck

  6. Waste processing air cleaning

    SciTech Connect (OSTI)

    Kriskovich, J.R.

    1998-07-27

    Waste processing and preparing waste to support waste processing relies heavily on ventilation. Ventilation is used at the Hanford Site on the waste storage tanks to provide confinement, cooling, and removal of flammable gases.

  7. Bioelectrochemical Integration of Waste Heat Recovery, Waste...

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

    Waste-to-Energy Conversion, and Waste-to-Chemical Conversion with Industrial Gas and Chemical Manufacturing Processes Advancing a Novel Microbial Reverse Electrodialysis ...

  8. Bioelectrochemical Integration of Waste Heat Recovery, Waste...

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

    Air Products and Chemicals, Inc. - Allentown, PA A microbial reverse electrodialysis technology ... Bio-Electrochemical Integration of Waste Heat Recovery, Waste-To-Energy Conversion, ...

  9. Magnetic-Bearing Chiller Compressors | Department of Energy

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

    Technology Deployment » Magnetic-Bearing Chiller Compressors Magnetic-Bearing Chiller Compressors Centrifugal, two-stage, magnetic-bearing chiller compressors equipped with variable-speed drives are a relatively new technology that operates at a high efficiency. Based on this case study, independent analysis by the U.S. Department of the Navy has verified that magnetic bearing compressors operate more efficiently than reciprocating and screw compressors, especially during partial load

  10. Recommendation 195: Mitigation of Contamination in Bear Creek Burial Grounds

    Broader source: Energy.gov [DOE]

    The ORSSAB requests DOE provide possible remedial actions to mitigate releases of contamination from Bear Creek Burial Grounds.

  11. Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence:

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

    Literature Review and DOE-LM Site Surveys | Department of Energy Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence: Literature Review and DOE-LM Site Surveys Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence: Literature Review and DOE-LM Site Surveys Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence: Literature Review and DOE-LM Site Surveys Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence: Literature Review

  12. Dynamically stable magnetic suspension/bearing system

    DOE Patents [OSTI]

    Post, Richard F.

    1996-01-01

    A magnetic bearing system contains magnetic subsystems which act together to support a rotating element in a state of dynamic equilibrium. However, owing to the limitations imposed by Earnshaw's Theorem, the magnetic bearing systems to be described do not possess a stable equilibrium at zero rotational speed. Therefore, mechanical stabilizers are provided, in each case, to hold the suspended system in equilibrium until its speed has exceeded a low critical speed where dynamic effects take over, permitting the achievement of a stable equilibrium for the rotating object. A state of stable equilibrium is achieved above a critical speed by use of a collection of passive elements using permanent magnets to provide their magnetomotive excitation. The magnetic forces exerted by these elements, when taken together, levitate the rotating object in equilibrium against external forces, such as the force of gravity or forces arising from accelerations. At the same time, this equilibrium is made stable against displacements of the rotating object from its equilibrium position by using combinations of elements that possess force derivatives of such magnitudes and signs that they can satisfy the conditions required for a rotating body to be stably supported by a magnetic bearing system over a finite range of those displacements.

  13. Dynamically stable magnetic suspension/bearing system

    DOE Patents [OSTI]

    Post, R.F.

    1996-02-27

    A magnetic bearing system contains magnetic subsystems which act together to support a rotating element in a state of dynamic equilibrium. However, owing to the limitations imposed by Earnshaw`s Theorem, the magnetic bearing systems to be described do not possess a stable equilibrium at zero rotational speed. Therefore, mechanical stabilizers are provided, in each case, to hold the suspended system in equilibrium until its speed has exceeded a low critical speed where dynamic effects take over, permitting the achievement of a stable equilibrium for the rotating object. A state of stable equilibrium is achieved above a critical speed by use of a collection of passive elements using permanent magnets to provide their magnetomotive excitation. The magnetic forces exerted by these elements, when taken together, levitate the rotating object in equilibrium against external forces, such as the force of gravity or forces arising from accelerations. At the same time, this equilibrium is made stable against displacements of the rotating object from its equilibrium position by using combinations of elements that possess force derivatives of such magnitudes and signs that they can satisfy the conditions required for a rotating body to be stably supported by a magnetic bearing system over a finite range of those displacements. 32 figs.

  14. Gerotor and bearing system for whirling mass orbital vibrator

    DOE Patents [OSTI]

    Brett, James Ford; Westermark, Robert Victor; Turner, Jr., Joey Earl; Lovin, Samuel Scott; Cole, Jack Howard; Myers, Will

    2007-02-27

    A gerotor and bearing apparatus for a whirling mass orbital vibrator which generates vibration in a borehole. The apparatus includes a gerotor with an inner gear rotated by a shaft having one less lobe than an outer gear. A whirling mass is attached to the shaft. At least one bearing is attached to the shaft so that the bearing engages at least one sleeve. A mechanism is provided to rotate the inner gear, the mass and the bearing in a selected rotational direction in order to cause the mass, the inner gear, and the bearing to backwards whirl in an opposite rotational direction. The backwards whirling mass creates seismic vibrations.

  15. EM's Defense Waste Processing Facility Achieves Waste Cleanup...

    Office of Environmental Management (EM)

    Defense Waste Processing Facility Achieves Waste Cleanup Milestone EM's Defense Waste Processing Facility Achieves Waste Cleanup Milestone January 14, 2016 - 12:10pm Addthis The ...

  16. EM Tank Waste Subcommittee Report for SRS / Hanford Tank Waste...

    Office of Environmental Management (EM)

    Tank Waste Subcommittee Report for SRS Hanford Tank Waste Review EM Tank Waste Subcommittee Report for SRS Hanford Tank Waste Review Environmental Management Advisory Board EM ...

  17. Hanford Dangerous Waste Permit

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

    Integrated Disposal Facility Operating Unit #11 Aerial view of IDF looking south. Note semi-truck trailer for scale. There are risks to groundwater in the future from secondary waste, according to modeling. Secondary waste would have to be significantly mitigated before it could be disposed at IDF. Where did the waste come from? No waste is stored here yet. IDF will receive vitrified waste when the Waste Treatment Plant starts operating. It may also receive secondary waste resulting from

  18. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

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

    ... NMSW - New Mexico Special Waste MSW - Municipal Solid Waste C&D - Construction and ... Proposed waste streams that could generate hazardous wastes are reviewed regularly to ...

  19. Legacy Waste | Department of Energy

    Office of Environmental Management (EM)

    Services Legacy Waste Legacy Waste Legacy Waste The Environmental Management Los Alamos Field Office's (EM-LA) Solid Waste Stabilization and Disposition Project Team is ...

  20. Flywheel energy storage advances using HTS bearings.

    SciTech Connect (OSTI)

    Mulcahy, T. M.

    1998-09-11

    High-Temperature-Superconducting (HT) bearings have the potential to reduce idling losses and make flywheel energy storage economical. Demonstration of large, high-speed flywheels is key to market penetration. Toward this goal, a flywheel system has been developed and tested with 5-kg to 15-kg disk-shaped rotors. Rlm speeds exceeded 400 mls and stored energies were >80 W-hr. Test implementation required technological advances in nearly all aspects of the flywheel system. Features and limitations of the design and tests are discussed, especially those related to achieving additional energy storage.

  1. Thermal Treatment of Solid Wastes Using the Electric Arc Furnace

    SciTech Connect (OSTI)

    O'Connor, W.K.; Turner, P.C.

    1999-09-01

    A thermal waste treatment facility has been developed at the Albany Research Center (ARC) over the past seven years to process a wide range of heterogeneous mixed wastes, on a scale of 227 to 907 kg/h (500 to 2,000 lb/h). The current system includes a continuous feed system, a 3-phase AC, 0.8 MW graphite electrode arc furnace, and a dedicated air pollution control system (APCS) which includes a close-coupled thermal oxidizer, spray cooler, baghouse, and wet scrubber. The versatility of the complete system has been demonstrated during 5 continuous melting campaigns, ranging from 11 to 25 mt (12 to 28 st) of treated wastes per campaign, which were conducted on waste materials such as (a) municipal incinerator ash, (b) simulated low-level radioactive, high combustible-bearing mixed wastes, (c) simulated low-level radioactive liquid tank wastes, (d) heavy metal contaminated soils, and (e) organic-contaminated dredging spoils. In all cases, the glass or slag products readily passed the U.S. Environmental Protection Agency (EPA) Toxicity Characteristic Leachability Program (TCLP) test. Additional studies are currently under way on electric utility wastes, steel and aluminum industry wastes, as well as zinc smelter residues. Thermal treatment of these solid waste streams is intended to produce a metallic product along with nonhazardous glass or slag products.

  2. Waste remediation

    SciTech Connect (OSTI)

    Halas, Nancy J.; Nordlander, Peter; Neumann, Oara

    2015-12-29

    A system including a steam generation system and a chamber. The steam generation system includes a complex and the steam generation system is configured to receive water, concentrate electromagnetic (EM) radiation received from an EM radiation source, apply the EM radiation to the complex, where the complex absorbs the EM radiation to generate heat, and transform, using the heat generated by the complex, the water to steam. The chamber is configured to receive the steam and an object, wherein the object is of medical waste, medical equipment, fabric, and fecal matter.

  3. Positive contact, self retaining bearing seals

    DOE Patents [OSTI]

    Johnson, Bruce H.; Larsen, Lawrence E.; Welch, Edmund F.

    1992-05-05

    An ultra-low friction bearing including an inner race, an outer race, bearing elements engaged between the inner and outer races and a seal between the inner and outer races is disclosed. The seal includes first and second sealing washers. The first washer has an outer diameter greater than an inner diameter of the outer race and an inner diameter greater than the outer diameter of the inner race. The second washer has an inner diameter less than the outer diameter of the inner race and an outer diameter less than the inner diameter of the outer race. The first washer slidably engages the outer race, the second washer slidably engages the inner race and the washers overlap and slidably engage one another. One of the washers snap fits into its respective inner or outer race while the other washer engages a stepped surface of the other of the inner and outer races. The grooved and stepped surface are offset from one another in a longitudinal direction of the races such that the washers are conically loaded thus providing a seal between the inner and outer races sufficient to prevent lubricant and contaminating particles from passing therethrough. The washers are made from a non-metallic semi-flexible low-modulus material.

  4. Transuranic Waste Requirements

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

    1999-07-09

    The guide provides criteria for determining if a waste is to be managed in accordance with DOE M 435.1-1, Chapter III, Transuranic Waste Requirements.

  5. Radioactive Waste Management

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

    1984-02-06

    To establish policies and guidelines by which the Department of Energy (DOE) manages tis radioactive waste, waste byproducts, and radioactively contaminated surplus facilities.

  6. Salt Waste Processing Initiatives

    Office of Environmental Management (EM)

    Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives 2 ...

  7. Hanford Tank Waste Retrieval,

    Office of Environmental Management (EM)

    Tank Waste Retrieval, Treatment, and Disposition Framework September 24, 2013 U.S. Department of Energy Washington, D.C. 20585 Hanford Tank Waste Retrieval, Treatment, and ...

  8. Tank Waste Strategy Update

    Office of Environmental Management (EM)

    Tank Waste Subcommittee www.em.doe.gov safety performance cleanup closure E M Environmental Management 1 Tank Waste Subcommittee Ken Picha Office of Environmental Management ...

  9. Waste Heat Recovery

    Office of Environmental Management (EM)

    - PRE-DECISIONAL - DRAFT 1 Waste Heat Recovery 1 Technology Assessment 2 Contents 3 1. ... 2 4 1.1. Introduction to Waste Heat Recovery ......

  10. Rolling bearing life models and steel internal cleanliness

    SciTech Connect (OSTI)

    Beswick, J.; Gabelli, A.; Ioannides, S.; Tripp, J.H.; Voskamp, A.P.

    1999-07-01

    The most widely used steel grade for rolling bearings is based on a steel composition first used almost a hundred years ago, the so-called 1C-1.5Cr steel. This steel is used either in a selective surface induction hardened conditions or in a through hardened heat treated condition, both yielding exceptional structural and contact fatigue properties. The Lundberg and Palmgren rolling bearing life prediction model, published in 1947, was the first analytical approach to bearing performance prediction, subsequently becoming a widely accepted basis for rolling bearing life calculations. At that time the fatigue life of rolling bearings was dominated by the classical sub-surface initiated failure mode. This mode results from the accumulation of micro-plastic strain at the depth of maximum Hertzian stress and is accelerated by the stress concentrations occurring at the micro internal defects. In common with all fatigue processes, rolling bearing failure is a statistical process: the failures of bearings with high inclusion content tested at high stress levels belong to the well-known family of Weibull distributions. Steady improvements in bearing steel cleanliness due, amongst other things, to the introduction of secondary metallurgy steel making techniques, have resulted in a significantly increased rolling bearing life and load carrying capacity. In recognition of this, in 1985 Ioannides and Harris introduced a new fatigue life model for rolling bearings, comprising a more widely applicable approach to the modeling of bearing life based on the relevant failure mode. Subsequently this has been extended to include effects of hardness and of micro-inclusion distributions in state-of-the-art clean bearing steel.

  11. Interagency cooperation in the development of a cost-effective transportation and disposal solution for vitrified radium bearing material

    SciTech Connect (OSTI)

    Smith, M.L.; Nixon, D.A.; Stone, T.J.; Tope, W.G.; Vogel, R.A.; Allen, R.B.; Schofield, W.D.

    1996-02-01

    Fernald radium bearing ore residue waste, stored within Silos 1 and 2 (K-65) and Silo 3 waste, will be vitrified for disposal at the Nevada Test Site (NTS). A comprehensive, parametric evaluation of waste form, shielding requirements, packaging, and transportation alternatives was completed to identify the safest, most cost-effective approach. The impacts of waste loading, waste form, regulatory requirements, NTS waste acceptance criteria, as-low-as-resonably-achievable principles, and material handling costs were factored into the recommended approach. Through cooperative work between the U.S. Department of Energy (DOE) and the U.S. Department of Transportation (DOT), the vitrified K-65 and Silo 3 radioactive material will be classified consistent with the regulations promulgated by DOT in the September 28, 1995 Federal Register. These new regulations adopt International Atomic Energy Agency language to promote a consistent approach for the transportation and management of radioactive material between the international community and the DOT. Use of the new regulations allows classification of the vitrified radioactive material from the Fernald silos under the designation of low specific activity-II and allows the development of a container that is optimized to maximize payload while minimizing internal void space, external surface radiation levels, and external volume. This approach minimizes the required number of containers and shipments, and the related transportation and disposal costs.

  12. Optimization and testing results of Zr-bearing ferritic steels

    SciTech Connect (OSTI)

    Tan, Lizhen; Yang, Ying; Tyburska-Puschel, Beata; Sridharan, K.

    2014-09-01

    The mission of the Nuclear Energy Enabling Technologies (NEET) program is to develop crosscutting technologies for nuclear energy applications. Advanced structural materials with superior performance at elevated temperatures are always desired for nuclear reactors, which can improve reactor economics, safety margins, and design flexibility. They benefit not only new reactors, including advanced light water reactors (LWRs) and fast reactors such as sodium-cooled fast reactor (SFR) that is primarily designed for management of high-level wastes, but also life extension of the existing fleet when component exchange is needed. Developing and utilizing the modern materials science tools (experimental, theoretical, and computational tools) is an important path to more efficient alloy development and process optimization. Ferritic-martensitic (FM) steels are important structural materials for nuclear reactors due to their advantages over other applicable materials like austenitic stainless steels, notably their resistance to void swelling, low thermal expansion coefficients, and higher thermal conductivity. However, traditional FM steels exhibit a noticeable yield strength reduction at elevated temperatures above ~500°C, which limits their applications in advanced nuclear reactors which target operating temperatures at 650°C or higher. Although oxide-dispersion-strengthened (ODS) ferritic steels have shown excellent high-temperature performance, their extremely high cost, limited size and fabricability of products, as well as the great difficulty with welding and joining, have limited or precluded their commercial applications. Zirconium has shown many benefits to Fe-base alloys such as grain refinement, improved phase stability, and reduced radiation-induced segregation. The ultimate goal of this project is, with the aid of computational modeling tools, to accelerate the development of a new generation of Zr-bearing ferritic alloys to be fabricated using conventional

  13. Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 6: Appendix G -- Baseline ecological risk assessment report

    SciTech Connect (OSTI)

    1996-09-01

    This Remedial Investigation (RI) Report characterizes the nature and extent of contamination, evaluates the fate and transport of contaminants, and assesses risk to human health and the environment resulting from waste disposal and other US Department of Energy (DOE) operations in Bear Creek Valley (BCV). BCV, which is located within the DOE Oak Ridge Reservation (ORR) encompasses multiple waste units containing hazardous and radioactive wastes arising from operations at the adjacent Oak Ridge Y-12 Plant. The primary waste units discussed in this RI Report are the S-3 Site, Oil Landfarm (OLF), Boneyard/Burnyard (BYBY), Sanitary Landfill 1 (SL 1), and Bear Creek Burial Grounds (BCBG). These waste units, plus the contaminated media resulting from environmental transport of the wastes from these units, are the subject of this RI. This BCV RI Report represents the first major step in the decision-making process for the BCV watershed. The RI results, in concert with the follow-on FS will form the basis for the Proposed Plan and Record of Decision for all BCV sites. This comprehensive decision document process will meet the objectives of the watershed approach for BCV. Appendix G contains ecological risks for fish, benthic invertebrates, soil invertebrates, plants, small mammals, deer, and predator/scavengers (hawks and fox). This risk assessment identified significant ecological risks from chemicals in water, sediment, soil, and shallow ground water. Metals and PCBs are the primary contaminants of concern.

  14. Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 1

    SciTech Connect (OSTI)

    1996-09-01

    This Remedial Investigation (RI) Report characterizes the nature and extent of contamination, evaluates the fate and transport of contaminants, and assesses risk to human health and the environment resulting from waste disposal and other US Department of Energy (DOE) operations in Bear Creek Valley (BCV). BCV, which is located within the DOE Oak Ridge Reservation (ORR) encompasses multiple waste units containing hazardous and radioactive wastes arising from operations at the adjacent Oak Ridge Y-12 Plant. The primary waste units discussed in this RI Report are the S-3 Site, Oil Landfarm (OLF), Boneyard/Burnyard (BYBY), Sanitary Landfill 1 (SL 1), and Bear Creek Burial Grounds (BCBG). These waste units, plus the contaminated media resulting from environmental transport of the wastes from these units, are the subject of this RI. This BCV RI Report represents the first major step in the decision-making process for the BCV watershed. The RI results, in concert with the follow-on FS will form the basis for the Proposed Plan and Record of Decision for all BCV sites. This comprehensive decision document process will meet the objectives of the watershed approach for BCV.

  15. Predicting sigma formation in mo-bearing stainless steels. (Conference...

    Office of Scientific and Technical Information (OSTI)

    Title: Predicting sigma formation in mo-bearing stainless steels. No abstract prepared. Authors: Perricone, Matthew ; Dupont, John Neuman ; Anderson, T. D. 1 ; Robino, Charles ...

  16. Reactor Physics Behavior of Transuranic-Bearing TRISO-Particle...

    Office of Scientific and Technical Information (OSTI)

    a Pressurized Water Reactor Citation Details In-Document Search Title: Reactor Physics Behavior of Transuranic-Bearing TRISO-Particle Fuel in a Pressurized Water Reactor You ...

  17. Reactor Physics Behavior of Transuranic-Bearing TRISO-Particle...

    Office of Scientific and Technical Information (OSTI)

    a Pressurized Water Reactor Citation Details In-Document Search Title: Reactor Physics Behavior of Transuranic-Bearing TRISO-Particle Fuel in a Pressurized Water Reactor ...

  18. Passive magnetic bearing element with minimal power losses

    DOE Patents [OSTI]

    Post, R.F.

    1998-12-08

    Systems employing passive magnetic bearing elements having minimal power losses are provided. Improved stabilizing elements are shown, employing periodic magnet arrays and inductively loaded circuits, but with improved characteristics compared to the elements disclosed in US Patent No. 5,495,221 entitled ``Dynamically Stable Magnetic Suspension/Bearing System.`` The improvements relate to increasing the magnitude of the force derivative, while at the same time reducing the power dissipated during the normal operation of the bearing system, to provide a passive bearing system that has virtually no losses under equilibrium conditions, that is, when the supported system is not subject to any accelerations except those of gravity. 8 figs.

  19. Passive magnetic bearing element with minimal power losses

    DOE Patents [OSTI]

    Post, Richard F.

    1998-01-01

    Systems employing passive magnetic bearing elements having minimal power losses are provided. Improved stabilizing elements are shown, employing periodic magnet arrays and inductively loaded circuits, but with improved characteristics compared to the elements disclosed in U.S. Patent No. 5,495,221 entitled "Dynamically Stable Magnetic Suspension/Bearing System." The improvements relate to increasing the magnitude of the force derivative, while at the same time reducing the power dissipated during the normal operation of the bearing system, to provide a passive bearing system that has virtually no losses under equilibrium conditions, that is, when the supported system is not subject to any accelerations except those of gravity.

  20. Rare Earth-Bearing Murataite Ceramics

    SciTech Connect (OSTI)

    Stefanovsky, Sergey; Stefanovsky, Olga; Yudintsev, Sergey; Nikonov, Boris

    2007-07-01

    Phase composition of the murataite-based ceramics containing 10 wt.% lanthanum, cerium, neodymium, europium, gadolinium, yttrium, zirconium oxides was studied. The ceramics were prepared by melting of oxide mixtures in 20 mL glass-carbon crucibles in air at {approx}1500 deg. C. They are composed of predominant murataite-type phases and minor extra phases: rutile, crichtonite, perovskite, ilmenite/pyrophanite, and zirconolite (in the Zr-bearing sample only). Three murataite-related phases with five- (5C), eight- (8C), and three-fold (3C) elementary fluorite unit cell are normally present in all the ceramics. These phases form core, intermediate zone, and rim of the murataite grains, respectively. They are predominant host phases for the rare earth elements whose concentrations are reduced in a row: 5C>8C>3C. Appreciate fraction of La and Ce may enter the perovskite phase. (authors)

  1. Resonant frequency method for bearing ball inspection

    DOE Patents [OSTI]

    Khuri-Yakub, B.T.; Chungkao Hsieh.

    1993-11-02

    The present invention provides for an inspection system and method for detecting defects in test objects which includes means for generating expansion inducing energy focused upon the test object at a first location, such expansion being allowed to contract, thereby causing pressure wave within and on the surface of the test object. Such expansion inducing energy may be provided by, for example, a laser beam or ultrasonic energy. At a second location, the amplitudes and phases of the acoustic waves are detected and the resonant frequencies' quality factors are calculated and compared to predetermined quality factor data, such comparison providing information of whether the test object contains a defect. The inspection system and method also includes means for mounting the bearing ball for inspection. 5 figures.

  2. Resonant frequency method for bearing ball inspection

    DOE Patents [OSTI]

    Khuri-Yakub, B. T.; Hsieh, Chung-Kao

    1993-01-01

    The present invention provides for an inspection system and method for detecting defects in test objects which includes means for generating expansion inducing energy focused upon the test object at a first location, such expansion being allowed to contract, thereby causing pressure wave within and on the surface of the test object. Such expansion inducing energy may be provided by, for example, a laser beam or ultrasonic energy. At a second location, the amplitudes and phases of the acoustic waves are detected and the resonant frequencies' quality factors are calculated and compared to predetermined quality factor data, such comparison providing information of whether the test object contains a defect. The inspection system and method also includes means for mounting the bearing ball for inspection.

  3. Passive magnetic bearing for a horizontal shaft

    DOE Patents [OSTI]

    Post, Richard F.

    2003-12-02

    A passive magnetic bearing is composed of a levitation element and a restorative element. The levitation element is composed of a pair of stationary arcuate ferromagnetic segments located within an annular radial-field magnet array. The magnet array is attached to the inner circumference of a hollow shaft end. An attractive force between the arcuate segments and the magnet array acts vertically to levitate the shaft, and also in a horizontal transverse direction to center the shaft. The restorative element is comprised of an annular Halbach array of magnets and a stationary annular circuit array located within the Halbach array. The Halbach array is attached to the inner circumference of the hollow shaft end. A repulsive force between the Halbach array and the circuit array increases inversely to the radial space between them, and thus acts to restore the shaft to its equilibrium axis of rotation when it is displaced therefrom.

  4. Uranium immobilization and nuclear waste

    SciTech Connect (OSTI)

    Duffy, C.J.; Ogard, A.E.

    1982-02-01

    Considerable information useful in nuclear waste storage can be gained by studying the conditions of uranium ore deposit formation. Further information can be gained by comparing the chemistry of uranium to nuclear fission products and other radionuclides of concern to nuclear waste disposal. Redox state appears to be the most important variable in controlling uranium solubility, especially at near neutral pH, which is characteristic of most ground water. This is probably also true of neptunium, plutonium, and technetium. Further, redox conditions that immobilize uranium should immobilize these elements. The mechanisms that have produced uranium ore bodies in the Earth's crust are somewhat less clear. At the temperatures of hydrothermal uranium deposits, equilibrium models are probably adequate, aqueous uranium (VI) being reduced and precipitated by interaction with ferrous-iron-bearing oxides and silicates. In lower temperature roll-type uranium deposits, overall equilibrium may not have been achieved. The involvement of sulfate-reducing bacteria in ore-body formation has been postulated, but is uncertain. Reduced sulfur species do, however, appear to be involved in much of the low temperature uranium precipitation. Assessment of the possibility of uranium transport in natural ground water is complicated because the system is generally not in overall equilibrium. For this reason, Eh measurements are of limited value. If a ground water is to be capable of reducing uranium, it must contain ions capable of reducing uranium both thermodynamically and kinetically. At present, the best candidates are reduced sulfur species.

  5. EM Waste and Materials Disposition & Transportation | Department...

    Office of Environmental Management (EM)

    Waste and Materials Disposition & Transportation EM Waste and Materials Disposition & Transportation DOE's Radioactive Waste Management Priorities: Continue to manage waste ...

  6. Method for primary containment of cesium wastes

    DOE Patents [OSTI]

    Angelini, Peter; Lackey, Walter J.; Stinton, David P.; Blanco, Raymond E.; Bond, Walter D.; Arnold, Jr., Wesley D.

    1983-01-01

    A method for producing a cesium-retentive waste form, characterized by a high degree of compositional stability and mechanical integrity, is provided by subjecting a cesium-loaded zeolite to heat under conditions suitable for stabilizing the zeolite and immobilizing the cesium, and coating said zeolite for sufficient duration within a suitable environment with at least one dense layer of pyrolytic carbon to seal therein said cesium to produce a final, cesium-bearing waste form. Typically, the zeolite is stabilized and the cesium immobilized in less than four hours by confinement within an air environment maintained at about 600.degree. C. Coatings are thereafter applied by confining the calcined zeolite within a coating environment comprising inert fluidizing and carbon donor gases maintained at 1,000.degree. C. for a suitable duration.

  7. Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste

    SciTech Connect (OSTI)

    1994-12-31

    This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation and amount of waste.

  8. Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste

    SciTech Connect (OSTI)

    1994-12-31

    This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation.

  9. Mr. John E. Kieling, Bureau Chief Hazardous Waste Bureau

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

    Enclosure 1: List of Additional Nitrate Salt Bearing Waste Containers Disposed at the WIPP Facility to which D001 is Provisionally Applied Container Number Waste Stream Shipment Number Emplacement Location LA00000087824 LA-MIN04-S.001 LA120183 Panel 6, Room 4, Row 48, Column 4, Height B LA00000091768 LA-MIN04-S.001 LA130086 Panel 6, Room 2, Row 18, Column 6, Height T LA00000091769 LA-MIN04-S.001 LA130089 Panel 6, Room 2, Row 24, Column 2, Height B LA00000088327 LA-MHD01.001 LA110043 Panel 5,

  10. Mr. John E. Kieling, Bureau Chief Hazardous Waste Bureau

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

    # 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. 16. 17. 18. 19. 20. 21. 22. 23. Enclosure 1: List of Additional Nitrate Salt Bearing Waste Containers Disposed at the WIPP Facility to which D001 is Provisionally App lied Container Number Waste Stream Shipment Number Emplacement location LA00000090315 LA-MHD01.001 LA120072 Panel 6, Room 5, Row 35, Column 1, Height B LA00000090712 LA-MHD01.001 LA130005 Panel 6, Room 3, Row 18, Column 6, Height B LA00000090715 LA-MHD01.001 LA130004 Panel 6,

  11. Waste Isolation Pilot Plant

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

    Waste Isolation Pilot Plant AFFIDAVIT FOR SURVIVING RELATIVE STATE ) ) ss: COUNTY OF ) That I, , am the...

  12. Waste Package Lifting Calculation

    SciTech Connect (OSTI)

    H. Marr

    2000-05-11

    The objective of this calculation is to evaluate the structural response of the waste package during the horizontal and vertical lifting operations in order to support the waste package lifting feature design. The scope of this calculation includes the evaluation of the 21 PWR UCF (pressurized water reactor uncanistered fuel) waste package, naval waste package, 5 DHLW/DOE SNF (defense high-level waste/Department of Energy spent nuclear fuel)--short waste package, and 44 BWR (boiling water reactor) UCF waste package. Procedure AP-3.12Q, Revision 0, ICN 0, calculations, is used to develop and document this calculation.

  13. Infectious waste feed system

    DOE Patents [OSTI]

    Coulthard, E. James

    1994-01-01

    An infectious waste feed system for comminuting infectious waste and feeding the comminuted waste to a combustor automatically without the need for human intervention. The system includes a receptacle for accepting waste materials. Preferably, the receptacle includes a first and second compartment and a means for sealing the first and second compartments from the atmosphere. A shredder is disposed to comminute waste materials accepted in the receptacle to a predetermined size. A trough is disposed to receive the comminuted waste materials from the shredder. A feeding means is disposed within the trough and is movable in a first and second direction for feeding the comminuted waste materials to a combustor.

  14. Permanent magnet design for high-speed superconducting bearings

    DOE Patents [OSTI]

    Hull, J.R.; Uherka, K.L.; Abdoud, R.G.

    1996-09-10

    A high temperature superconducting bearing including a permanent magnet rotor levitated by a high temperature superconducting structure is disclosed. The rotor preferably includes one or more concentric permanent magnet rings coupled to permanent magnet ring structures having substantially triangular and quadrangular cross-sections. Both alternating and single direction polarity magnet structures can be used in the bearing. 9 figs.

  15. Permanent magnet design for high-speed superconducting bearings

    DOE Patents [OSTI]

    Hull, John R.; Uherka, Kenneth L.; Abdoud, Robert G.

    1996-01-01

    A high temperature superconducting bearing including a permanent magnet rotor levitated by a high temperature superconducting structure. The rotor preferably includes one or more concentric permanent magnet rings coupled to permanent magnet ring structures having substantially triangular and quadrangular cross-sections. Both alternating and single direction polarity magnet structures can be used in the bearing.

  16. Phase 1 report on the Bear Creek Valley treatability study, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    1997-04-01

    Bear Creek Valley (BCV) is located within the US Department of Energy (DOE) Oak Ridge Reservation and encompasses multiple waste units containing hazardous and radioactive wastes associated with past operations at the adjacent Oak Ridge Y-12 Plant. The BCV Remedial Investigation determined that disposal of wastes at the S-3 Site, Boneyard/Burnyard (BYBY), and Bear Creek Burial Grounds (BCBG) has caused contamination of both deep and shallow groundwater. The primary contaminants include uranium, nitrate, and VOCs, although other metals such as aluminum, magnesium, and cadmium persist. The BCV feasibility study will describe several remedial options for this area, including both in situ and ex situ treatment of groundwater. This Treatability Study Phase 1 Report describes the results of preliminary screening of treatment technologies that may be applied within BCV. Four activities were undertaken in Phase 1: field characterization, laboratory screening of potential sorbents, laboratory testing of zero valent iron products, and field screening of three biological treatment systems. Each of these activities is described fully in technical memos attached in Appendices A through G.

  17. Summary.qxd

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

    ... Creates a cement-like solid. * Upgrade and permit the calciner * Calcine liquid mixed transuranic wasteSBW and add to bin sets. * Blend calcine with slag, caustic soda, and water ...

  18. Radioactive Waste Management Manual

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

    1999-07-09

    This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07.

  19. Hanford Dangerous Waste Permit

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

    Waste Treatment and Immobilization Plant (vit plant) Operating Unit #10 Aerial view of construction, July 2011 Where will the waste go? LAW canisters will go to shallow disposal at Hanford's Integrated Disposal Facility. HLW canisters will go to a For scale, here's the parking lot! Safe disposition of our nation's most dangerous waste relies on the vit plant's safe completion and ability to process waste for 20+ years. * Permitted for storage and treatment of Hanford's tank waste in unique

  20. Nuclear waste solidification

    DOE Patents [OSTI]

    Bjorklund, William J.

    1977-01-01

    High level liquid waste solidification is achieved on a continuous basis by atomizing the liquid waste and introducing the atomized liquid waste into a reaction chamber including a fluidized, heated inert bed to effect calcination of the atomized waste and removal of the calcined waste by overflow removal and by attrition and elutriation from the reaction chamber, and feeding additional inert bed particles to the fluidized bed to maintain the inert bed composition.

  1. Methane Recovery from Hydrate-bearing Sediments

    SciTech Connect (OSTI)

    J. Carlos Santamarina; Costas Tsouris

    2011-04-30

    Gas hydrates are crystalline compounds made of gas and water molecules. Methane hydrates are found in marine sediments and permafrost regions; extensive amounts of methane are trapped in the form of hydrates. Methane hydrate can be an energy resource, contribute to global warming, or cause seafloor instability. This study placed emphasis on gas recovery from hydrate bearing sediments and related phenomena. The unique behavior of hydrate-bearing sediments required the development of special research tools, including new numerical algorithms (tube- and pore-network models) and experimental devices (high pressure chambers and micromodels). Therefore, the research methodology combined experimental studies, particle-scale numerical simulations, and macro-scale analyses of coupled processes. Research conducted as part of this project started with hydrate formation in sediment pores and extended to production methods and emergent phenomena. In particular, the scope of the work addressed: (1) hydrate formation and growth in pores, the assessment of formation rate, tensile/adhesive strength and their impact on sediment-scale properties, including volume change during hydrate formation and dissociation; (2) the effect of physical properties such as gas solubility, salinity, pore size, and mixed gas conditions on hydrate formation and dissociation, and it implications such as oscillatory transient hydrate formation, dissolution within the hydrate stability field, initial hydrate lens formation, and phase boundary changes in real field situations; (3) fluid conductivity in relation to pore size distribution and spatial correlation and the emergence of phenomena such as flow focusing; (4) mixed fluid flow, with special emphasis on differences between invading gas and nucleating gas, implications on relative gas conductivity for reservoir simulations, and gas recovery efficiency; (5) identification of advantages and limitations in different gas production strategies with

  2. Waste Shipment Approval - 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 Acceptance Process Waste Shipment Approval About Us Hanford Site Solid Waste Acceptance Program What's New Acceptance Criteria Acceptance Process Becoming a new Hanford Customer Annual Waste Forecast and Funding Arrangements Waste Stream Approval Waste Shipment Approval Waste Receipt Quality Assurance Program Waste Specification Records Tools Points of Contact Waste Shipment Approval Email Email Page | Print Print

  3. Waste Processing | Department of Energy

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

    Processing Waste Processing Workers process and repackage waste at the Transuranic Waste Processing Center’s Cask Processing Enclosure. Workers process and repackage waste at the Transuranic Waste Processing Center's Cask Processing Enclosure. Transuranic waste, or TRU, is one of several types of waste handled by Oak Ridge's EM program. This waste contains manmade elements heavier than uranium, hence the name "trans" or "beyond" uranium. Transuranic waste material

  4. Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Uinit Contractor Operational Readiness Review, June 2012

    Office of Environmental Management (EM)

    Contractor Operational Readiness Review June 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background

  5. Radioactive Waste Management Manual

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

    1999-07-09

    This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. The purpose of the Manual is to catalog those procedural requirements and existing practices that ensure that all DOE elements and contractors continue to manage DOE's radioactive waste in a manner that is protective of worker and public health and safety, and the environment. Does not cancel other directives.

  6. Waste Isolation Pilot Plant

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

    2/25/16 WIPP Home Page About WIPP Contact Us Search About WIPP The nation's only deep geologic repository for nuclear waste The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) is a deep geologic repository for permanent disposal of a specific type of waste that is the byproduct of the nation's nuclear defense program. CH and RH Waste WIPP is the nation's only repository for the disposal of nuclear waste known as transuranic, or TRU, waste. It consists of clothing, tools,

  7. Waste management progress report

    SciTech Connect (OSTI)

    1997-06-01

    During the Cold War era, when DOE and its predecessor agencies produced nuclear weapons and components, and conducted nuclear research, a variety of wastes were generated (both radioactive and hazardous). DOE now has the task of managing these wastes so that they are not a threat to human health and the environment. This document is the Waste Management Progress Report for the U.S. Department of Energy dated June 1997. This progress report contains a radioactive and hazardous waste inventory and waste management program mission, a section describing progress toward mission completion, mid-year 1997 accomplishments, and the future outlook for waste management.

  8. Waste-to-Energy: Waste Management and Energy Production Opportunities...

    Office of Environmental Management (EM)

    Waste-to-Energy: Waste Management and Energy Production Opportunities Waste-to-Energy: Waste Management and Energy Production Opportunities July 24, 2014 9:00AM to 3:30PM EDT U.S. ...

  9. Paramont's Black Bear No. 4 mine does it right, again

    SciTech Connect (OSTI)

    Sanda, A.

    2007-07-15

    The Paramont Coal Company Virginia, LLC, a subsidiary of Alpha Natural Resources, recently won the '2007 overall award for excellence in mining and reclamation from the Virginia Division of Mined Land Reclamation and the Virginia Mining Association. Coal People Magazine recently visited Black Bear No. 4 mine where a settling pond was being removed and stream bed placed to drain the area, part of the 451-acre award winning reclamation project. The article recounts discussions with mining engineers about the company's operations with emphasis on the Black Bear No. 4 mine. Black Bear No. 1 mine won five state and national awards last year for conservation and land management practices. 8 photos.

  10. Montana grizzly bears protest exploratory drilling in wilderness area

    SciTech Connect (OSTI)

    Bieg, J.P.

    1983-04-01

    Grizzly bears require vast areas for their natural ranging habits and thrive best when isolated from humans. The continued encroachment of man, with increased recreation, logging, mining, and energy development, has reduced the bears' natural habitat until it is in danger of extinction. In 1975 Congress recognized the precarious future of the grizzly and listed it as a threatened species under the Endangered Species Act. The Forest Service has indicated that the impact of drilling, along with other uses of wilderness areas, could adversely affect the bears.

  11. Waste Treatment and Immobilization Plant HLW Waste Vitrification Facility |

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

    Department of Energy HLW Waste Vitrification Facility Waste Treatment and Immobilization Plant HLW Waste Vitrification Facility Full Document and Summary Versions are available for download Waste Treatment and Immobilization Plant HLW Waste Vitrification Facility (742.54 KB) Summary - WTP HLW Waste Vitrification Facility (137.99 KB) More Documents & Publications Waste Treatment and Immobilization Plant (WTP) Analytical Laboratory (LAB), Balance of Facilities (BOF) and Low-Activity Waste

  12. Hanford Tank Waste Residuals

    Office of Environmental Management (EM)

    Hanford Tank Waste Residuals DOE HLW Corporate Board November 6, 2008 Chris Kemp, DOE ORP Bill Hewitt, YAHSGS LLC Hanford Tanks & Tank Waste * Single-Shell Tanks (SSTs) - 27 million ...

  13. Nuclear Waste Partnership, LLC

    Office of Environmental Management (EM)

    Nuclear Waste Partnership, LLC Waste Isolation Pilot Plant Report from the Department of Energy Voluntary Protection Program Onsite Review March 17-27, 2015 U.S. Department of ...

  14. Notice of Preferred Sodium Bearing Waste Treatment Technology (DOE/EIS-0287) (08/03/05)

    Office of Environmental Management (EM)

    Collection Request Title: OE Recovery Act Financial Assistance Grants | Department of Energy OMB Action Approving DOE Submission to Extend Information Collection Request Title: OE Recovery Act Financial Assistance Grants Notice of OMB Action Approving DOE Submission to Extend Information Collection Request Title: OE Recovery Act Financial Assistance Grants The Office of Management and Budget (OMB) has issued a Notice of OMB Action approving the Department of Energy's request to extend for

  15. EP-AREAG-G-FO-DOP-124 Nitrate Salt Bearing TRU Waste Container Monitoring.pdf

    Office of Environmental Management (EM)

    Management (2007) | Department of Energy 423: Strengthening Federal Environmental, Energy, and Transportation Management (2007) EO 13423: Strengthening Federal Environmental, Energy, and Transportation Management (2007) It is the policy of the United States that Federal agencies conduct their environmental, transportation, and energy-related activities under the law in support of their respective missions in an environmentally, economically and fiscally sound, integrated, continuously

  16. Reaction of Inconel 690 and 693 in Iron Phosphate Melts: Alternative Glasses for Waste Vitrification

    SciTech Connect (OSTI)

    Day, Delbert E.

    2005-09-13

    The corrosion resistance of candidate materials used for the electrodes (Inconel 690 & 693) and the melt contact refractory (Monofrax K-3) in a Joule Heated Melter (JHM) has been investigated at the University of Missouri-Rolla (UMR) during the period from June 1, 2004 to August 31, 2005. This work was supported by the U.S. Department of Energy (DOE) Office of Biological and Environmental Research (DE-FG02-04ER63831). The unusual properties and characteristics of iron phosphate glasses, as viewed from the standpoint of alternative glasses for vitrifying nuclear and hazardous wastes which contain components that make them poorly suited for vitrification in borosilicate glass, were recently discovered at UMR. The expanding national and international interest in iron phosphate glasses for waste vitrification stems from their rapid melting and chemical homogenization which results in higher furnace output, their high waste loading that varies from 32 wt% up to 75 wt% for the Hanford LAW and HLW, respectively, and the outstanding chemical durability of the iron phosphate wasteforms which meets all present DOE requirements (PCT and VHT). The higher waste loading in iron phosphate glasses, compared to the baseline borosilicate glass, can reduce the time and cost of vitrification considerably since a much smaller mass of glass will be produced, for example, about 43% less glass when the LAW at Hanford is vitrified in an iron phosphate glass according to PNNL estimates. In view of the promising performance of iron phosphate glasses, information is needed for how to best melt these glasses on the scale needed for practical use. Melting iron phosphate glasses in a JHM is considered the preferred method at this time because its design could be nearly identical to the JHM now used to melt borosilicate glasses at the Defense Waste Processing Facility (DWPF), Westinghouse Savannah River Co. Therefore, it is important to have information for the corrosion of candidate electrode

  17. Big Bear City, California: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Hide Map This article is a stub. You can help OpenEI by expanding it. Big Bear City is a census-designated place in San Bernardino County, California.1...

  18. Big Bear Lake, California: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Hide Map This article is a stub. You can help OpenEI by expanding it. Big Bear Lake is a city in San Bernardino County, California. It falls under California's...

  19. Cooling system for a bearing of a turbine rotor

    DOE Patents [OSTI]

    Schmidt, Mark Christopher

    2002-01-01

    In a gas turbine, a bore tube assembly radially inwardly of an aft bearing conveys cooling steam to the buckets of the turbine and returns the cooling steam to a return. To cool the bearing and thermally insulate the bearing from the cooling steam paths, a radiation shield is spaced from the bore tube assembly by a dead air gap. Additionally, an air passageway is provided between the radiation shield and the inner surface of an aft shaft forming part of the rotor. Air is supplied from an inlet for flow along the passage and radially outwardly through bores in the aft shaft disk to cool the bearing and insulate it from transfer of heat from the cooling steam.

  20. BPA employees help rescue bear cub in Shelton

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

    energized high-voltage electrical equipment. The bear spent a chilly night in a nearby tree before being lured to a trap with donuts as bait. "We saw the little guy on our...

  1. Waste Specification Records - Hanford Site

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

    Specification Records About Us Hanford Site Solid Waste Acceptance Program What's New Acceptance Criteria Acceptance Process Becoming a new Hanford Customer Annual Waste Forecast and Funding Arrangements Waste Stream Approval Waste Shipment Approval Waste Receipt Quality Assurance Program Waste Specification Records Tools Points of Contact Waste Specification Records Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size Waste Specification Records (WSRds) are the tool

  2. Solid waste handling

    SciTech Connect (OSTI)

    Parazin, R.J.

    1995-05-31

    This study presents estimates of the solid radioactive waste quantities that will be generated in the Separations, Low-Level Waste Vitrification and High-Level Waste Vitrification facilities, collectively called the Tank Waste Remediation System Treatment Complex, over the life of these facilities. This study then considers previous estimates from other 200 Area generators and compares alternative methods of handling (segregation, packaging, assaying, shipping, etc.).

  3. MAGNOX:BUTEX URANIUM BEARING GLASSES PHYSICAL AND CHEMICAL ANALYSIS DATA PACKAGE

    SciTech Connect (OSTI)

    Peeler, D.; Imrich, K.; Click, D.

    2011-03-08

    Sellafield Ltd (United Kingdom) has requested technical support from the Savannah River National Laboratory (SRNL) to characterize a series of uranium-bearing, mixed alkali borosilicate glasses [WFO (2010)]. The specific glasses to be characterized are based on different blends of Magnox (WRW17 simulant) and Butex (or HASTs 1 and 2) waste types as well as different incorporation rates (or waste loadings) of each blend. Specific Magnox:Butex blend ratios of interest include: 75:25, 60:40, and 50:50. Each of these waste blend ratios will be mixed with a base glass additive composition targeting waste loadings (WLs) of 25, 28, and 32% which will result in nine different glasses. The nine glasses are to be fabricated and physically characterized to provide Sellafield Ltd with the technical data to evaluate the impacts of various Magnox:Butex blend ratios and WLs on key glass properties of interest. It should be noted that the use of 'acceptable' in the Work for Other (WFO) was linked to the results of a durability test (more specifically the Soxhlet leach test). Other processing (e.g., viscosity ({eta}), liquidus temperature (T{sub L})) or product performance (e.g., Product Consistency Test (PCT) results - in addition to the Soxhlet leach test) property constraints were not identified. For example, a critical hold point in the classification of an 'acceptable glass' prior to processing high-level waste (HLW) through the Defense Waste Processing Facility (DWPF) is an evaluation of specific processing and product performance properties against pre-defined constraints. This process is referred to as Slurry Mix Evaporator (SME) acceptability in which predicted glass properties (based on compositional measurements) are compared to predefined constraints to determine whether the glass is acceptable [Brown and Postles (1995)]. As an example, although the nominal melter temperature at DWPF is 1150 C, there is a T{sub L} constraint (without uncertainties applied) of 1050 C. Any

  4. Cryocooler applications for high-temperature superconductor magnetic bearings.

    SciTech Connect (OSTI)

    Niemann, R. C.

    1998-05-22

    The efficiency and stability of rotational magnetic suspension systems are enhanced by the use of high-temperature superconductor (HTS) magnetic bearings. Fundamental aspects of the HTS magnetic bearings and rotational magnetic suspension are presented. HTS cooling can be by liquid cryogen bath immersion or by direct conduction, and thus there are various applications and integration issues for cryocoolers. Among the numerous cryocooler aspects to be considered are installation; operating temperature; losses; and vacuum pumping.

  5. High performance magnetic bearing systems using high temperature superconductors

    DOE Patents [OSTI]

    Abboud, R.G.

    1998-05-05

    Disclosed are a magnetic bearing apparatus and a method for providing at least one stabilizing force in a magnetic bearing structure with a superconducting magnetic assembly and a magnetic assembly, by providing a superconducting magnetic member in the superconducting magnetic assembly with a plurality of domains and arranging said superconducting magnetic member such that at least one domain has a domain C-axis vector alignment angularly disposed relative to a reference axis of the magnetic member in the magnetic assembly. 7 figs.

  6. High performance magnetic bearing systems using high temperature superconductors

    DOE Patents [OSTI]

    Abboud, Robert G.

    1998-01-01

    A magnetic bearing apparatus and a method for providing at least one stabilizing force in a magnetic bearing structure with a superconducting magnetic assembly and a magnetic assembly, by providing a superconducting magnetic member in the superconducting magnetic assembly with a plurality of domains and arranging said superconducting magnetic member such that at least one domain has a domain C-axis vector alignment angularly disposed relative to a reference axis of the magnetic member in the magnetic assembly.

  7. Radial Flow Bearing Heat Exchanger | Department of Energy

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

    Radial Flow Bearing Heat Exchanger Radial Flow Bearing Heat Exchanger Sandia's Radial Flow Heat Exchanger Sandia's Radial Flow Heat Exchanger Lead Performer: Sandia National Laboratories - Albuquerque, NM Partners: -- Tribologix - Golden, CO -- United Technologies Research Center - East Hartford, CT -- University of Maryland - College Park, MD -- Oak Ridge National Laboratory - Oak Ridge, TN -- Whirlpool - Benton Harbor, MI -- Optimized Thermal Systems - College Park, MD DOE Funding: $5,472,285

  8. A Simplified Thermohydrodynamic Model for Fluid Film Bearings

    Energy Science and Technology Software Center (OSTI)

    1994-03-01

    CADJOB was constructed with the industrial designer in mind. The objective of the program is to assist the mechanical designer in selecting a journal bearing (single or multi-pad, tilting or fixed-pad, single or multi-slot inlet, isothermal or THD operation) that will satisfy, specific working conditions. CADJOB may also be used for instructional purposes, to provide the student with insight into the relative importance of the various bearing parameters.

  9. DOE - Office of Legacy Management -- American Bearing Corp - IN 09

    Office of Legacy Management (LM)

    Bearing Corp - IN 09 FUSRAP Considered Sites Site: American Bearing Corp. (IN.09 ) Eliminated from further consideration under FUSRAP - Referred to NRC Designated Name: Not Designated Alternate Name: None Location: 429 South Harding Street , Indianapolis , Indiana IN.09-1 Evaluation Year: 1986 IN.09-3 Site Operations: Uranium metal fabrication work during the mid-1950s IN.09-3 Site Disposition: Eliminated - No Authority - NRC licensed IN.09-2 IN.09-4 Radioactive Materials Handled: Yes Primary

  10. Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence.

    Office of Scientific and Technical Information (OSTI)

    Literature Review and DOE-LM Site Surveys (Technical Report) | SciTech Connect Technical Report: Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence. Literature Review and DOE-LM Site Surveys Citation Details In-Document Search Title: Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence. Literature Review and DOE-LM Site Surveys This report on evaporite mineralization was completed as an Ancillary Work Plan for the Applied Studies and Technology program

  11. Waste Heat Recovery

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

    - PRE-DECISIONAL - DRAFT 1 Waste Heat Recovery 1 Technology Assessment 2 Contents 3 1. Introduction to the Technology/System ............................................................................................... 2 4 1.1. Introduction to Waste Heat Recovery .......................................................................................... 2 5 1.2. Challenges and Barriers for Waste Heat Recovery ..................................................................... 13 6 1.3. Public

  12. 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.

  13. Bear Head LNG Corporation and Bear Head LNG (USA), LLC- FE Dkt. No.- 15-33-LNG

    Broader source: Energy.gov [DOE]

    The Office of Fossil Energy gives notice of receipt of an application filed on February 25, 2015, by Bear Head LNG, requesting long-term multi-contract authority as further described in their...

  14. Advances in the Glass Formulations for the Hanford Tank Waste Treatment and Immobilization Plant

    SciTech Connect (OSTI)

    Kruger, Albert A.; Vienna, John D.; Kim, Dong Sang

    2015-01-14

    The Department of Energy-Office of River Protection (DOE-ORP) is constructing the Hanford Tank Waste Treatment and Immobilization Plant (WTP) to treat radioactive waste currently stored in underground tanks at the Hanford site in Washington. The WTP that is being designed and constructed by a team led by Bechtel National, Inc. (BNI) will separate the tank waste into High Level Waste (HLW) and Low Activity Waste (LAW) fractions with the majority of the mass (~90%) directed to LAW and most of the activity (>95%) directed to HLW. The pretreatment process, envisioned in the baseline, involves the dissolution of aluminum-bearing solids so as to allow the aluminum salts to be processed through the cesium ion exchange and report to the LAW Facility. There is an oxidative leaching process to affect a similar outcome for chromium-bearing wastes. Both of these unit operations were advanced to accommodate shortcomings in glass formulation for HLW inventories. A by-product of this are a series of technical challenges placed upon materials selected for the processing vessels. The advances in glass formulation play a role in revisiting the flow sheet for the WTP and hence, the unit operations that were being imposed by minimal waste loading requirements set forth in the contract for the design and construction of the plant. Another significant consideration to the most recent revision of the glass models are the impacts on resolution of technical questions associated with current efforts for design completion.

  15. Municipal waste processing apparatus

    DOE Patents [OSTI]

    Mayberry, J.L.

    1988-04-13

    This invention relates to apparatus for processing municipal waste, and more particularly to vibrating mesh screen conveyor systems for removing grit, glass, and other noncombustible materials from dry municipal waste. Municipal waste must be properly processed and disposed of so that it does not create health risks to the community. Generally, municipal waste, which may be collected in garbage trucks, dumpsters, or the like, is deposited in processing areas such as landfills. Land and environmental controls imposed on landfill operators by governmental bodies have increased in recent years, however, making landfill disposal of solid waste materials more expensive. 6 figs.

  16. Radioactive Waste Management Manual

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

    1999-07-09

    This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07. Admin Chg 2, dated 6-8-11, supersedes DOE M 435.1-1 Chg 1.

  17. Direct cementitious waste option study report

    SciTech Connect (OSTI)

    Dafoe, R.E.; Losinski, S.J.

    1998-02-01

    A settlement agreement between the Department of Energy (DOE) and the State of Idaho mandates that all high-level radioactive waste (HLW) now stored at the Idaho Chemical Processing Plant (ICPP) will be treated so that it is ready to be moved out of Idaho for disposal by a target data of 2035. This study investigates the direct grouting of all ICPP calcine (including the HLW dry calcine and those resulting from calcining sodium-bearing liquid waste currently residing in the ICPP storage tanks) as the treatment method to comply with the settlement agreement. This method involves grouting the calcined waste and casting the resulting hydroceramic grout into stainless steel canisters. These canisters will be stored at the Idaho National Engineering and Environmental Laboratory (INEEL) until they are sent to a national geologic repository. The operating period for grouting treatment will be from 2013 through 2032, and all the HLW will be treated and in interim storage by the end of 2032.

  18. Mixed waste: Proceedings

    SciTech Connect (OSTI)

    Moghissi, A.A.; Blauvelt, R.K.; Benda, G.A.; Rothermich, N.E.

    1993-12-31

    This volume contains the peer-reviewed and edited versions of papers submitted for presentation a the Second International Mixed Waste Symposium. Following the tradition of the First International Mixed Waste Symposium, these proceedings were prepared in advance of the meeting for distribution to participants. The symposium was organized by the Mixed Waste Committee of the American Society of Mechanical Engineers. The topics discussed at the symposium include: stabilization technologies, alternative treatment technologies, regulatory issues, vitrification technologies, characterization of wastes, thermal technologies, laboratory and analytical issues, waste storage and disposal, organic treatment technologies, waste minimization, packaging and transportation, treatment of mercury contaminated wastes and bioprocessing, and environmental restoration. Individual abstracts are catalogued separately for the data base.

  19. An advanced feed pump based on magnetic bearings

    SciTech Connect (OSTI)

    Hanson, L.

    1996-11-01

    Pumps have not used magnetic bearings commercially due to their high initial cost and the perception of a high risk to reward ratio. However, by taking advantage of the capability of the bearings to operate submerged in the pumped liquid, an advanced boiler feed pump has been developed with measurably improved efficiency and reduced seal maintenance. When the economic value of these improvements are evaluated against the additional first cost of the bearing change, attractive paybacks are generated for most new plant applications and even for some retrofits where the first cost reductions from eliminating the oil system, bearings, and seals do not apply. These savings are in addition to the benefits long recognized for magnetic bearings: improved reliability; built-in remote monitoring and diagnostics; elimination of the pressure feed oil system and its maintenance and potential fire hazard. Based on these advantages a research and development prototype pump incorporating the new technology was built and tested. A commercial opportunity to demonstrate this new design arose in 1994 and resulted in the sale of an eight stage, 3500 HP feed pump to Tampa Electric Company for their new Polk Station Generating Plant. This is the largest known magnetic bearing pump delivered for commercial operation worldwide. The pump was shipped during August 1995 and is expected to enter service during the first half of 1996. This paper will briefly introduce magnetic bearings and then discuss the design of the advanced pump. The basis for predicting improved efficiency and estimating its value will be presented followed by the experience in manufacturing and testing the pump for Polk Generating Station.

  20. Waste Stream Approval - Hanford Site

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

    Stream Approval About Us Hanford Site Solid Waste Acceptance Program What's New Acceptance Criteria Acceptance Process Becoming a new Hanford Customer Annual Waste Forecast and Funding Arrangements Waste Stream Approval Waste Shipment Approval Waste Receipt Quality Assurance Program Waste Specification Records Tools Points of Contact Waste Stream Approval Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size After funding approval is in place, the next step is to

  1. Laboratory Waste | Sample Preparation Laboratories

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

    Laboratory Waste Sharps Broken Glass Containment Hazardous Waste All waste produced in the Sample Prep Labs should be appropriately disposed of at SLAC. You are prohibited to transport waste back to your home institution. Designated areas exist in the labs for sharps, broken glass, and hazardous waste. Sharps, broken glass, and hazardous waste must never be disposed of in the trash cans or sink drains. Containment Bottles, jars, and plastic bags are available for containing chemical waste. Place

  2. EVALUATION OF A LOW FRICTION - HIGH EFFICIENCY ROLLER BEARING ENGINE

    SciTech Connect (OSTI)

    Kolarik, Robert V. II; Shattuck, Charles W.; Copper, Anthony P.

    2009-06-30

    This Low Friction (High Efficiency Roller Bearing) Engine (LFE) report presents the work done by The Timken Company to conduct a technology demonstration of the benefits of replacing hydrodynamic bearings with roller bearings in the crankshaft and camshaft assemblies of an internal combustion engine for the purpose of collecting data sufficient to prove merit. The engines in the present study have been more extensively converted to roller bearings than any previous studies (40 needle roller bearings per engine) to gain understanding of the full potential of application of bearing technology. The project plan called for comparative testing of a production vehicle which was already respected for having demonstrated low engine friction levels with a rollerized version of that engine. Testing was to include industry standard tests for friction, emissions and fuel efficiency conducted on instrumented dynamometers. Additional tests for fuel efficiency, cold start resistance and other measures of performance were to be made in the actual vehicle. Comparative measurements of noise, vibration and harshness (NVH), were planned, although any work to mitigate the suspected higher NVH level in the rollerized engine was beyond the scope of this project. Timken selected the Toyota Avalon with a 3.5L V-6 engine as the test vehicle. In an attempt to minimize cost and fabrication time, a ‘made-from’ approach was proposed in which as many parts as possible would be used or modified from production parts to create the rollerized engine. Timken commissioned its test partner, FEV Engine Technology, to do a feasibility study in which they confirmed that using such an approach was possible to meet the required dimensional restrictions and tolerances. In designing the roller bearing systems for the crank and cam trains, Timken utilized as many production engine parts as possible. The crankshafts were produced from production line forgings, which use Timken steel, modified with special

  3. Mitigation of Micropitting in Wind Turbine Main Shaft Bearings

    SciTech Connect (OSTI)

    Sethuraman, Latha; Guo, Yi; Sheng, Shuangwen

    2015-09-03

    In recent years, increasing evidence of failures has been reported from spherical roller main bearings used in three-point mounting (TPM) drivetrains of wind turbines. One of the leading causes has been micropitting, a failure mode that is possibly overlooked by design, selection and life-prediction tools. It remains to be seen if retrofitting problematic spherical roller bearings (SRBs) with improved bearing design solutions can improve their durability. Questions to ask might be: ‘Are the operating conditions of the main bearing well understood?’ and ‘Are the failures caused by deficient design practice or other unidentified external sources within the system?’ These questions fundamentally challenge the underlying design basis and encourage the need for a system analysis approach that is currently being undertaken by researchers from the National Renewable Energy Laboratory (NREL). Specifically, this article discusses a few potential design alternatives and system-level reassessment to circumvent micropitting in main bearings used in TPM drivetrains.

  4. Magnetic bearings for free-piston Stirling engines

    SciTech Connect (OSTI)

    Curwen, P.W.; Fleming, D.P.; Rao, D.K.; Wilson, D.S.

    1992-08-01

    The feasibility and efficacy of applying magnetic bearings to free-piston Stirling-cycle power conversion machinery currently being developed for long-term space missions are assessed. The study was performed for a 50-kWe Reference Stirling Space Power Converter (RSSPC) which currently uses hydrostatic gas bearings to support the reciprocating displacer and power piston assemblies. Active magnetic bearings of the attractive electromagnetic type are feasible for the RSSPC power piston. Magnetic support of the displacer assembly would require unacceptable changes to the design of the current RSSPC. However, magnetic suspension of both displacer and power piston is feasible for a relative-displacer version of the RSSPC. Magnetic suspension of the RSSPC power piston can potentially increase overall efficiency by 0.5 to 1 percent (0.1 to 0.3 efficiency points). Magnetic bearings will also overcome several operational concerns associated with hydrostatic gas bearing systems. These advantages, however, are accompanied by a 5 percent increase in specific mass of the RSSPC.

  5. Enterprise Assessments Operational Awareness Record, Waste Treatment...

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

    waste system of the Waste Treatment and Immobilization Plant Low Activity Waste Facility. ... Operational Awareness Record, Waste Treatment and Immobilization Plant - December 2014 ...

  6. Solid Waste Management Plan. Revision 4

    SciTech Connect (OSTI)

    1995-04-26

    The waste types discussed in this Solid Waste Management Plan are Municipal Solid Waste, Hazardous Waste, Low-Level Mixed Waste, Low-Level Radioactive Waste, and Transuranic Waste. The plan describes for each type of solid waste, the existing waste management facilities, the issues, and the assumptions used to develop the current management plan.

  7. Transuranic (TRU) Waste | Department of Energy

    Office of Environmental Management (EM)

    Transuranic (TRU) Waste Transuranic (TRU) Waste Transuranic (TRU) Waste Defined by the WIPP Land Withdrawal Act as "waste containing more than 100 nanocuries of alpha-emitting ...

  8. Evaluation Of Used Fuel Disposition In Clay-Bearing Rock

    Office of Energy Efficiency and Renewable Energy (EERE)

    Radioactive waste disposal in shale/argillite rock formations has been widely considered given its desirable isolation properties, e.g., low permeability, potential geochemically reduced conditions...

  9. Underground waste barrier structure

    DOE Patents [OSTI]

    Saha, Anuj J.; Grant, David C.

    1988-01-01

    Disclosed is an underground waste barrier structure that consists of waste material, a first container formed of activated carbonaceous material enclosing the waste material, a second container formed of zeolite enclosing the first container, and clay covering the second container. The underground waste barrier structure is constructed by forming a recessed area within the earth, lining the recessed area with a layer of clay, lining the clay with a layer of zeolite, lining the zeolite with a layer of activated carbonaceous material, placing the waste material within the lined recessed area, forming a ceiling over the waste material of a layer of activated carbonaceous material, a layer of zeolite, and a layer of clay, the layers in the ceiling cojoining with the respective layers forming the walls of the structure, and finally, covering the ceiling with earth.

  10. Waste from grocery stores

    SciTech Connect (OSTI)

    Lieb, K.

    1993-11-01

    The Community Recycling Center, Inc., (CRC, Champaign, Ill.), last year conducted a two-week audit of waste generated at two area grocery stores. The stores surveyed are part of a 10-store chain. For two of the Kirby Foods Stores, old corrugated containers (OCC) accounted for 39-45% of all waste. The summary drew correlations between the amount of OCC and the sum of food and garbage waste. The study suggested that one can reasonably estimate volumes of waste based on the amount of OCC because most things come in a box. Auditors set up a series of containers to make the collection process straightforward. Every day the containers were taken to local recycling centers and weighed. Approximate waste breakdowns for the two stores were as follows: 45% OCC; 35% food waste; 20% nonrecyclable or noncompostable items; and 10% other.

  11. Levitation pressure and friction losses in superconducting bearings

    DOE Patents [OSTI]

    Hull, John R.

    2001-01-01

    A superconducting bearing having at least one permanent magnet magnetized with a vertical polarization. The lower or stator portion of the bearing includes an array of high-temperature superconducting elements which are comprised of a plurality of annular rings. An annular ring is located below each permanent magnet and an annular ring is offset horizontally from at least one of the permanent magnets. The rings are composed of individual high-temperature superconducting elements located circumferentially along the ring. By constructing the horizontally-offset high-temperature superconducting ring so that the c-axis is oriented in a radial direction, a higher levitation force can be achieved. Such an orientation will also provide substantially lower rotational drag losses in the bearing.

  12. Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 5: Appendix F -- Baseline human health risk assessment report

    SciTech Connect (OSTI)

    1996-09-01

    This Remedial Investigation (RI) Report characterizes the nature and extent of contamination, evaluates the fate and transport of contaminants, and assesses risk to human health and the environment resulting from waste disposal and other US Department of Energy (DOE) operations in Bear Creek Valley (BCV). BCV, which is located within the DOE Oak Ridge Reservation (ORR) encompasses multiple waste units containing hazardous and radioactive wastes arising from operations at the adjacent Oak Ridge Y-12 Plant. The primary waste units discussed in this RI Report are the S-3 Site, Oil Landfarm (OLF), Boneyard/Burnyard (BYBY), Sanitary Landfill 1 (SL 1), and Bear Creek Burial Grounds (BCBG). These waste units, plus the contaminated media resulting from environmental transport of the wastes from these units, are the subject of this RI. This BCV RI Report represents the first major step in the decision-making process for the BCV watershed. The RI results, in concert with the follow-on FS will form the basis for the Proposed Plan and Record of Decision for all BCV sites. This comprehensive decision document process will meet the objectives of the watershed approach for BCV. Appendix F documents potential risks and provides information necessary for making remediation decisions. A quantitative analysis of the inorganic, organic, and radiological site-related contaminants found in various media is used to characterize the potential risks to human health associated with exposure to these contaminants.

  13. Method for disposing of hazardous wastes

    DOE Patents [OSTI]

    Burton, Frederick G.; Cataldo, Dominic A.; Cline, John F.; Skiens, W. Eugene

    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.

  14. Hanford Dangerous Waste Permit

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

    Dangerous Waste Permit Suzanne Dahl and Jeff Lyon Nuclear Waste Program April 17, 2012 Tank-Related Units Why have permits? * To regulate dangerous waste treatment, storage, and disposal facilities: - Thermal treatment units - Landfills - Tank systems - Container storage - Containment buildings * To protect humans and the environment Parts of the Unit Permit * Fact Sheet * Unit description * Operations and processes * Permit conditions * Requirements or limitations to maintain safe operating

  15. Waste to Energy

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

    pellets or logs from wood, plants, or paper So, what ... Waste to energy - gasification http:... George Roe Research Professor Alaska Center ...

  16. Waste inspection tomography (WIT)

    SciTech Connect (OSTI)

    Bernardi, R.T.

    1995-10-01

    Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting, isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU.

  17. Hanford Dangerous Waste Permit

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

    * Removes water and volatile organics from tank waste. * Decreases the volume of water to create room in double-shell tanks, allowing them to accept waste from noncompliant single- shell tanks. * Treats up to 1 million gallons to free up about 500,000 gallons in the double-shell tanks in each campaign. * Near PUREX and most of the double-shell tanks in the 200 East Area. * Began operating in 1977. Where does the waste come from? Waste comes to the 242-A Evaporator from the double-shell tanks.

  18. Vitrification of waste

    DOE Patents [OSTI]

    Wicks, George G.

    1999-01-01

    A method for encapsulating and immobilizing waste for disposal. Waste, preferably, biologically, chemically and radioactively hazardous, and especially electronic wastes, such as circuit boards, are placed in a crucible and heated by microwaves to a temperature in the range of approximately 300.degree. C. to 800.degree. C. to incinerate organic materials, then heated further to a temperature in the range of approximately 1100.degree. C. to 1400.degree. C. at which temperature glass formers present in the waste will cause it to vitrify. Glass formers, such as borosilicate glass, quartz or fiberglass can be added at the start of the process to increase the silicate concentration sufficiently for vitrification.

  19. Vitrification of waste

    DOE Patents [OSTI]

    Wicks, G.G.

    1999-04-06

    A method is described for encapsulating and immobilizing waste for disposal. Waste, preferably, biologically, chemically and radioactively hazardous, and especially electronic wastes, such as circuit boards, are placed in a crucible and heated by microwaves to a temperature in the range of approximately 300 C to 800 C to incinerate organic materials, then heated further to a temperature in the range of approximately 1100 C to 1400 C at which temperature glass formers present in the waste will cause it to vitrify. Glass formers, such as borosilicate glass, quartz or fiberglass can be added at the start of the process to increase the silicate concentration sufficiently for vitrification.

  20. Pioneering Nuclear Waste Disposal

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

    ... agen- cies, scientific advisory panels, and concerned citizens. * As a ... It also prohibited the disposal of high-level radioactive waste and spent nuclear fuel. In 1996, ...

  1. WASTE PACKAGE TRANSPORTER DESIGN

    SciTech Connect (OSTI)

    D.C. Weddle; R. Novotny; J. Cron

    1998-09-23

    The purpose of this Design Analysis is to develop preliminary design of the waste package transporter used for waste package (WP) transport and related functions in the subsurface repository. This analysis refines the conceptual design that was started in Phase I of the Viability Assessment. This analysis supports the development of a reliable emplacement concept and a retrieval concept for license application design. The scope of this analysis includes the following activities: (1) Assess features of the transporter design and evaluate alternative design solutions for mechanical components. (2) Develop mechanical equipment details for the transporter. (3) Prepare a preliminary structural evaluation for the transporter. (4) Identify and recommend the equipment design for waste package transport and related functions. (5) Investigate transport equipment interface tolerances. This analysis supports the development of the waste package transporter for the transport, emplacement, and retrieval of packaged radioactive waste forms in the subsurface repository. Once the waste containers are closed and accepted, the packaged radioactive waste forms are termed waste packages (WP). This terminology was finalized as this analysis neared completion; therefore, the term disposal container is used in several references (i.e., the System Description Document (SDD)) (Ref. 5.6). In this analysis and the applicable reference documents, the term ''disposal container'' is synonymous with ''waste package''.

  2. Waste minimization assessment procedure

    SciTech Connect (OSTI)

    Kellythorne, L.L. )

    1993-01-01

    Perry Nuclear Power Plant began developing a waste minimization plan early in 1991. In March of 1991 the plan was documented following a similar format to that described in the EPA Waste Minimization Opportunity Assessment Manual. Initial implementation involved obtaining management's commitment to support a waste minimization effort. The primary assessment goal was to identify all hazardous waste streams and to evaluate those streams for minimization opportunities. As implementation of the plan proceeded, non-hazardous waste streams routinely generated in large volumes were also evaluated for minimization opportunities. The next step included collection of process and facility data which would be useful in helping the facility accomplish its assessment goals. This paper describes the resources that were used and which were most valuable in identifying both the hazardous and non-hazardous waste streams that existed on site. For each material identified as a waste stream, additional information regarding the materials use, manufacturer, EPA hazardous waste number and DOT hazard class was also gathered. Once waste streams were evaluated for potential source reduction, recycling, re-use, re-sale, or burning for heat recovery, with disposal as the last viable alternative.

  3. Norcal Waste Systems, Inc.

    SciTech Connect (OSTI)

    Not Available

    2002-12-01

    Fact sheet describes the LNG long-haul heavy-duty trucks at Norcal Waste Systems Inc.'s Sanitary Fill Company.

  4. Decomposition of carbohydrate wastes

    DOE Patents [OSTI]

    Appell, Herbert R.; Pantages, Peter

    1976-11-02

    Carbohydrate waste materials are decomposed to form a gaseous fuel product by contacting them with a transition metal catalyst at elevated temperature substantially in the absence of water.

  5. Waste treatment process for removal of contaminants from aqueous, mixed-waste solutions using sequential chemical treatment and crossflow microfiltration, followed by dewatering

    DOE Patents [OSTI]

    Vijayan, S.; Wong, C.F.; Buckley, L.P.

    1994-11-22

    In processes of this invention aqueous waste solutions containing a variety of mixed waste contaminants are treated to remove the contaminants by a sequential addition of chemicals and adsorption/ion exchange powdered materials to remove the contaminants including lead, cadmium, uranium, cesium-137, strontium-85/90, trichloroethylene and benzene, and impurities including iron and calcium. Staged conditioning of the waste solution produces a polydisperse system of size enlarged complexes of the contaminants in three distinct configurations: water-soluble metal complexes, insoluble metal precipitation complexes, and contaminant-bearing particles of ion exchange and adsorbent materials. The volume of the waste is reduced by separation of the polydisperse system by cross-flow microfiltration, followed by low-temperature evaporation and/or filter pressing. The water produced as filtrate is discharged if it meets a specified target water quality, or else the filtrate is recycled until the target is achieved. 1 fig.

  6. Waste treatment process for removal of contaminants from aqueous, mixed-waste solutions using sequential chemical treatment and crossflow microfiltration, followed by dewatering

    DOE Patents [OSTI]

    Vijayan, Sivaraman; Wong, Chi F.; Buckley, Leo P.

    1994-01-01

    In processes of this invention aqueous waste solutions containing a variety of mixed waste contaminants are treated to remove the contaminants by a sequential addition of chemicals and adsorption/ion exchange powdered materials to remove the contaminants including lead, cadmium, uranium, cesium-137, strontium-85/90, trichloroethylene and benzene, and impurities including iron and calcium. Staged conditioning of the waste solution produces a polydisperse system of size enlarged complexes of the contaminants in three distinct configurations: water-soluble metal complexes, insoluble metal precipitation complexes, and contaminant-bearing particles of ion exchange and adsorbent materials. The volume of the waste is reduced by separation of the polydisperse system by cross-flow microfiltration, followed by low-temperature evaporation and/or filter pressing. The water produced as filtrate is discharged if it meets a specified target water quality, or else the filtrate is recycled until the target is achieved.

  7. Transfer Lines to Connect Liquid Waste Facilities and Salt Waste...

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

    ... of tank waste at SRS. SWPF will separate the salt waste into a low-volume, high radioactivity fraction for vitrification in the Defense Waste Processing Facility (DWPF) and ...

  8. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Serne, R. Jeffrey

    2012-09-26

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

  9. Report: EM Tank Waste Subcommittee Full Report for Waste Treatment...

    Office of Environmental Management (EM)

    Triay: As discussed during our September 15th public meeting, enclosed please find the Environmental Management Advisory Board EM Tank Waste Subcommittee Report for Waste Treatment ...

  10. Waste Treatment and Immobilation Plant HLW Waste Vitrification...

    Office of Environmental Management (EM)

    6 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) HLW Waste Vitrification Facility L. Holton D. Alexander C. Babel H. Sutter J. Young August ...

  11. METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE

    SciTech Connect (OSTI)

    WEBER RA

    2009-01-16

    The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient potential energy to break up material and release gas and are assigned to waste group B. These tanks are considered to represent a potential induced flammable gas release hazard, but no spontaneous buoyant displacement flammable gas release hazard. Tanks that are not waste group C tanks and have an energy ratio {ge} 3.0, but that pass the third criterion (buoyancy ratio < 1.0, see below) are also assigned to waste group B. Even though the designation as a waste

  12. METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE

    SciTech Connect (OSTI)

    FOWLER KD

    2007-12-27

    This document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 7 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs. The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient potential energy to break up

  13. Processing of solid mixed waste containing radioactive and hazardous materials

    DOE Patents [OSTI]

    Gotovchikov, Vitaly T.; Ivanov, Alexander V.; Filippov, Eugene A.

    1998-05-12

    Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

  14. Processing of solid mixed waste containing radioactive and hazardous materials

    DOE Patents [OSTI]

    Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

    1998-05-12

    Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter. 6 figs.

  15. Heterogeneous waste processing

    DOE Patents [OSTI]

    Vanderberg, Laura A.; Sauer, Nancy N.; Brainard, James R.; Foreman, Trudi M.; Hanners, John L.

    2000-01-01

    A combination of treatment methods are provided for treatment of heterogeneous waste including: (1) treatment for any organic compounds present; (2) removal of metals from the waste; and, (3) bulk volume reduction, with at least two of the three treatment methods employed and all three treatment methods emplyed where suitable.

  16. Radioactive waste disposal package

    DOE Patents [OSTI]

    Lampe, Robert F.

    1986-11-04

    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.

  17. 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.

  18. Radioactive waste storage issues

    SciTech Connect (OSTI)

    Kunz, D.E.

    1994-08-15

    In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

  19. Nuclear waste solutions

    DOE Patents [OSTI]

    Walker, Darrel D.; Ebra, Martha A.

    1987-01-01

    High efficiency removal of technetium values from a nuclear waste stream is achieved by addition to the waste stream of a precipitant contributing tetraphenylphosphonium cation, such that a substantial portion of the technetium values are precipitated as an insoluble pertechnetate salt.

  20. Improving medical waste disposal

    SciTech Connect (OSTI)

    O'Connor, L.

    1994-05-01

    This article describes the use of electron-beam irradiation, steam detoxification, and microwave disinfection systems rather than incineration to rid the waste stream of medical scraps. The topics of the article include biological waste stream sources and amounts, pyrolysis and oxidation, exhaust gas cleanup, superheated steam sterilization and detoxification.

  1. Optimization of superconducting tiling pattern for superconducting bearings

    DOE Patents [OSTI]

    Hull, John R. (Hinsdale, IL)

    1996-01-01

    An apparatus and method for reducing magnetic field inhomogeneities which produce rotational loss mechanisms in high temperature superconducting magnetic bearings. Magnetic field inhomogeneities are reduced by dividing high temperature superconducting structures into smaller structures, and arranging the smaller structures into tiers which stagger the magnetic field maximum locations of the smaller structures.

  2. Optimization of superconducting tiling pattern for superconducting bearings

    DOE Patents [OSTI]

    Hull, J.R.

    1996-09-17

    An apparatus and method for reducing magnetic field inhomogeneities which produce rotational loss mechanisms in high temperature superconducting magnetic bearings are disclosed. Magnetic field inhomogeneities are reduced by dividing high temperature superconducting structures into smaller structures, and arranging the smaller structures into tiers which stagger the magnetic field maximum locations of the smaller structures. 20 figs.

  3. PRESSURE DEVELOPMENT IN SEALED CONTAINERS WITH PLUTONIUM BEARING MATERIALS

    SciTech Connect (OSTI)

    Duffey, J.; Livingston, R.

    2010-02-01

    Gas generation by plutonium-bearing materials in sealed containers has been studied. The gas composition and pressure are determined over periods from months to years. The Pu-bearing materials studied represent those produced by all of the major processes used by DOE in the processing of plutonium and include the maximum amount of water (0.5% by weight) allowed by DOE's 3013 Standard. Hydrogen generation is of high interest and the Pu-bearing materials can be classed according to how much hydrogen is generated. Hydrogen generation by high-purity plutonium oxides packaged under conditions typical for actual 3013 materials is minimal, with very low generation rates and low equilibrium pressures. Materials with chloride salt impurities have much higher hydrogen gas generation rates and result in the highest observed equilibrium hydrogen pressures. Other materials such as those with high metal oxide impurities generate hydrogen at rates in between these extremes. The fraction of water that is converted to hydrogen gas as equilibrium is approached ranges from 0% to 25% under conditions typical of materials packaged to the 3013 Standard. Generation of both hydrogen and oxygen occurs when liquid water is present. The material and moisture conditions that result in hydrogen and oxygen generation for high-purity plutonium oxide and chloride salt-bearing plutonium oxide materials have been characterized. Other gases that are observed include nitrous oxide, carbon dioxide, carbon monoxide, and methane.

  4. Gearbox Reliability Collaborative High Speed Shaft Tapered Roller Bearing Calibration

    SciTech Connect (OSTI)

    Keller, J.; Guo, Y.; McNiff, B.

    2013-10-01

    The National Renewable Energy Laboratory (NREL) Gearbox Reliability Collaborative (GRC) is a project investigating gearbox reliability primarily through testing and modeling. Previous dynamometer testing focused upon acquiring measurements in the planetary section of the test gearbox. Prior to these tests, the strain gages installed on the planetary bearings were calibrated in a load frame.

  5. Waste Determination Equivalency - 12172

    SciTech Connect (OSTI)

    Freeman, Rebecca D.

    2012-07-01

    The Savannah River Site (SRS) is a Department of Energy (DOE) facility encompassing approximately 800 square kilometers near Aiken, South Carolina which began operations in the 1950's with the mission to produce nuclear materials. The SRS contains fifty-one tanks (2 stabilized, 49 yet to be closed) distributed between two liquid radioactive waste storage facilities at SRS containing carbon steel underground tanks with storage capacities ranging from 2,800,000 to 4,900,000 liters. Treatment of the liquid waste from these tanks is essential both to closing older tanks and to maintaining space needed to treat the waste that is eventually vitrified or disposed of onsite. Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005 (NDAA) provides the Secretary of Energy, in consultation with the Nuclear Regulatory Commission (NRC), a methodology to determine that certain waste resulting from prior reprocessing of spent nuclear fuel are not high-level radioactive waste if it can be demonstrated that the waste meets the criteria set forth in Section 3116(a) of the NDAA. The Secretary of Energy, in consultation with the NRC, signed a determination in January 2006, pursuant to Section 3116(a) of the NDAA, for salt waste disposal at the SRS Saltstone Disposal Facility. This determination is based, in part, on the Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site and supporting references, a document that describes the planned methods of liquid waste treatment and the resulting waste streams. The document provides descriptions of the proposed methods for processing salt waste, dividing them into 'Interim Salt Processing' and later processing through the Salt Waste Processing Facility (SWPF). Interim Salt Processing is separated into Deliquification, Dissolution, and Adjustment (DDA) and Actinide Removal Process/Caustic Side Solvent Extraction Unit (ARP/MCU). The Waste Determination was signed by the

  6. Overview of mixed waste issues

    SciTech Connect (OSTI)

    Piciulo, P.L.; Bowerman, B.S.; Kempf, C.R.; MacKenzie, D.R.; Siskind, B.

    1986-01-01

    Based on BNL's study it was concluded that there are LLWs which contain chemically hazardous components. Scintillation liquids may be considered an EPA listed hazardous waste and are, therefore, potential mixed wastes. Since November, 1985 no operating LLW disposal site will accept these wastes for disposal. Unless such wastes contain de minimis quantities of radionuclides, they cannot be disposed of at an EPA an EPA permitted site. Currently generators of LSC wastes can ship de minimis wastes to be burned at commercial facilities. Oil wastes will also eventually be an EPA listed waste and thus will have to be considered a potential radioactive mixed wasted unless NRC establishes de minimis levels of radionuclides below which oils can be managed as hazardous wastes. Regarding wastes containing lead metal there is some question as to the extent of the hazard posed by lead disposed in a LLW burial trench. Chromium-containing wastes would have to be tested to determine whether they are potential mixed wastes. There may be other wastes that are mixed wastes; the responsibility for determining this rests with the waste generator. It is believed that there are management options for handling potential mixed wastes but there is no regulatory guidance. BNL has identified and evaluated a variety of treatment options for the management of potential radioactive mixed wastes. The findings of that study showed that application of a management option with the purpose of addressing EPA concern can, at the same time, address stabilization and volume reduction concerns of NRC.

  7. 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...

  8. Waste Specification Records - Hanford Site

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

    Specification Records About Us Hanford Site Solid Waste Acceptance Program What's New Acceptance Criteria Acceptance Process Becoming a new Hanford Customer Annual Waste Forecast...

  9. High-Level Waste Inventory

    Office of Environmental Management (EM)

    Analysis of Alternatives for Disposition of the Idaho Calcined High-Level Waste Inventory ... of the Idaho Calcined High-Level Waste Inventory Volume 1- Summary Report April ...

  10. Enhanced Tank Waste Strategy Update

    Office of Environmental Management (EM)

    in the EM complex Radioactive tank waste stabilization, treatment, and disposal ... Programmatic support activities* 10% Radioactive tank waste stabilization, treatment and ...

  11. Vitrification of NORM wastes

    SciTech Connect (OSTI)

    Chapman, C.

    1994-05-01

    Vitrification of wastes is a relatively new application of none of man`s oldest manufacturing processes. During the past 25 years it has been developed and accepted internationally for immobilizing the most highly radioactive wastes from spent nuclear fuel. By the year 2005, there will be nine operating high-level radioactive vitrification plants. Many of the technical ``lessons learned`` from this international program can be applied to much less hazardous materials such as naturally occurring radioactive material (NORM). With the deployment of low capital and operating cost systems, vitrification should become a broadly applied process for treating a large variety of wastes. In many situations, the wastes can be transformed into marketable products. This paper will present a general description of waste vitrification, summarize some of its key advantages, provide some test data for a small sample of one NORM, and suggest how this process may be applied to NORM.

  12. AVLIS production plant waste management plan

    SciTech Connect (OSTI)

    Not Available

    1984-11-15

    Following the executive summary, this document contains the following: (1) waste management facilities design objectives; (2) AVLIS production plant wastes; (3) waste management design criteria; (4) waste management plan description; and (5) waste management plan implementation. 17 figures, 18 tables.

  13. The use of filtered bags to increase waste payload capacity

    SciTech Connect (OSTI)

    Dustin, D.F.; Thorp, D.T.; Rivera, M.A.

    1998-03-03

    For the past few years, the Department of Energy has favored the direct disposal of low plutonium content residue materials from Rocky Flats rather than engage in expensive and time consuming plutonium recovery operations. One impediment to direct disposal has been the wattage limit imposed by the Waste Isolation Pilot Plant on hydrogenous materials such as combustibles and sludges. The issue of concern is the radiolytic generation and accumulation of hydrogen and other explosive gases in waste containers. The wattage limits that existed through 1996 restricted the amount of plutonium bearing hydrogenous materials that could be packaged in a WIPP bound waste drum to only a fraction of the capacity of a drum. Typically, only about one kilogram of combustible residue could be packaged in a waste drum before the wattage limit was exceeded resulting in an excessively large number of drums to be procured, stored, shipped, and interred. The Rocky Flats Environmental Technology Site has initiated the use of filtered plastic bags (called bag-out bags) used to remove transuranic waste materials from glove box lines. The bags contain small, disk like HEPA filters which are effective in containing radioactively contaminated particulate material but allow for the diffusion of hydrogen gas. Used in conjunction with filtered 55 gallon drums, filtered bag-out bags were pursued as a means to increase the allowable wattage limits for selected residue materials. In February 1997, the Nuclear Regulatory Commission approved the use of filtered bag-out bags for transuranic waste materials destined for WIPP. The concomitant increase in wattage limits now allows for approximately four times the payload per waste drum for wattage limited materials.

  14. Technical viability and development needs for waste forms and facilities

    SciTech Connect (OSTI)

    Pegg, I.; Gould, T.

    1996-05-01

    The objective of this breakout session was to provide a forum to discuss technical issues relating to plutonium-bearing waste forms and their disposal facilities. Specific topics for discussion included the technical viability and development needs associated with the waste forms and/or disposal facilities. The expected end result of the session was an in-depth (so far as the limited time would allow) discussion of key issues by the session participants. The session chairs expressed allowance for, and encouragement of, alternative points of view, as well as encouragement for discussion of any relevant topics not addressed in the paper presentations. It was not the intent of this session to recommend or advocate any one technology over another.

  15. Steam Reforming, 6-in. Bench-Scale Design and Testing Project -- Technical and Functional Requirements Description

    SciTech Connect (OSTI)

    Losinski, Sylvester John; Marshall, Douglas William

    2002-08-01

    Feasibility studies and technology development work are currently being performed on several processes to treat radioactive liquids and solids currently stored at the Idaho Nuclear Technology and Engineering Center (INTEC), located within the Idaho National Engineering and Environmental Laboratory (INEEL). These studies and development work will be used to select a treatment process for treatment of the radioactive liquids and solids to meet treatment milestones of the Settlement Agreement between the Department of Energy and the State of Idaho. One process under consideration for treating the radioactive liquids and solids, specifically Sodium-Bearing Waste (SBW) and tank heel solids, is fluid bed steam reforming (FBSR). To support both feasibility and development studies a bench-scale FBSR is being designed and constructed. This report presents the technical and functional requirements, experimental objectives, process flow sheets, and equipment specifications for the bench-scale FBSR.

  16. Hanford Dangerous Waste Permit

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

    Double-Shell Tank System 204-AR Waste Unloading Facility Operating Unit #12 241-AP Tank Farm construction. See black pickup trucks for scale. The DSTs have limited capacity and are aging. Maintaining these tanks is important to ensure that waste is ready to supply the Waste Treatment Plant. The permit requires continuous leak detection to protect humans and the environment. 200 West & East * 28 tanks in 6 groups, or tank farms. * Capacity: 1 - 1.2 million gallons each. * The double-shell

  17. Hanford Dangerous Waste Permit

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

    We don't expect any risk from this site. The permit ensures operation and closure of this facility do not harm humans or the environment. Liquid Effluent Retention Facility Effluent Treatment Facility Operating Unit #3 What happens to the waste it receives? LERF has three lined basins with a capacity of 88.5 million liters. ETF removes or destroys dangerous waste in liquid waste. It uses treatments such as filters, reverse osmosis, pH adjustment, and ultraviolet light. Water is treated, then

  18. 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.

  19. 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.

  20. Syntaxin 1a Variants Lacking an N-peptide or Bearing the LE Mutation...

    Office of Scientific and Technical Information (OSTI)

    an N-peptide or Bearing the LE Mutation Bind to Munc18a in a Closed Conformation Citation Details In-Document Search Title: Syntaxin 1a Variants Lacking an N-peptide or Bearing ...

  1. Method for calcining radioactive wastes

    DOE Patents [OSTI]

    Bjorklund, William J.; McElroy, Jack L.; Mendel, John E.

    1979-01-01

    This invention relates to a method for the preparation of radioactive wastes in a low leachability form by calcining the radioactive waste on a fluidized bed of glass frit, removing the calcined waste to melter to form a homogeneous melt of the glass and the calcined waste, and then solidifying the melt to encapsulate the radioactive calcine in a glass matrix.

  2. Generating power with waste wood

    SciTech Connect (OSTI)

    Atkins, R.S.

    1995-02-01

    Among the biomass renewables, waste wood has great potential with environmental and economic benefits highlighting its resume. The topics of this article include alternate waste wood fuel streams; combustion benefits; waste wood comparisons; waste wood ash; pilot scale tests; full-scale test data; permitting difficulties; and future needs.

  3. Methane generation from waste materials

    SciTech Connect (OSTI)

    Samani, Zohrab A.; Hanson, Adrian T.; Macias-Corral, Maritza

    2010-03-23

    An organic solid waste digester for producing methane from solid waste, the digester comprising a reactor vessel for holding solid waste, a sprinkler system for distributing water, bacteria, and nutrients over and through the solid waste, and a drainage system for capturing leachate that is then recirculated through the sprinkler system.

  4. Contained recovery of oily waste

    DOE Patents [OSTI]

    Johnson, Jr., Lyle A.; Sudduth, Bruce C.

    1989-01-01

    A method is provided for recovering oily waste from oily waste accumulations underground comprising sweeping the oily waste accumulation with hot water to recover said oily waste, wherein said area treated is isolated from surrounding groundwater hydraulically. The hot water may be reinjected after the hot-water displacement or may be treated to conform to any discharge requirements.

  5. Wind Turbine Design Guideline DG03: Yaw and Pitch Rolling Bearing Life

    SciTech Connect (OSTI)

    Harris, T.; Rumbarger, J. H.; Butterfield, C. P.

    2009-12-01

    This report describes the design criteria, calculation methods, and applicable standards recommended for use in performance and life analyses of ball and roller (rolling) bearings for yaw and pitch motion support in wind turbine applications. The formulae presented here for rolling bearing analytical methods and bearing-life ratings are consistent with methods in current use by wind turbine designers and rolling-bearing manufacturers.

  6. Hanford Site Secondary Waste Roadmap

    SciTech Connect (OSTI)

    Westsik, Joseph H.

    2009-01-29

    Summary The U.S. Department of Energy (DOE) is making plans to dispose of 54 million gallons of radioactive tank wastes at the Hanford Site near Richland, Washington. The high-level wastes and low-activity wastes will be vitrified and placed in permanent disposal sites. Processing of the tank wastes will generate secondary wastes, including routine solid wastes and liquid process effluents, and these need to be processed and disposed of also. The Department of Energy Office of Waste Processing sponsored a meeting to develop a roadmap to outline the steps necessary to design the secondary waste forms. Representatives from DOE, the U.S. Environmental Protection Agency, the Washington State Department of Ecology, the Oregon Department of Energy, Nuclear Regulatory Commission, technical experts from the DOE national laboratories, academia, and private consultants convened in Richland, Washington, during the week of July 21-23, 2008, to participate in a workshop to identify the risks and uncertainties associated with the treatment and disposal of the secondary wastes and to develop a roadmap for addressing those risks and uncertainties. This report describes the results of the roadmap meeting in Richland. Processing of the tank wastes will generate secondary wastes, including routine solid wastes and liquid process effluents. The secondary waste roadmap workshop focused on the waste streams that contained the largest fractions of the 129I and 99Tc that the Integrated Disposal Facility risk assessment analyses were showing to have the largest contribution to the estimated IDF disposal impacts to groundwater. Thus, the roadmapping effort was to focus on the scrubber/off-gas treatment liquids with 99Tc to be sent to the Effluent Treatment Facility for treatment and solidification and the silver mordenite and carbon beds with the captured 129I to be packaged and sent to the IDF. At the highest level, the secondary waste roadmap includes elements addressing regulatory and

  7. Centrifugally activated bearing for high-speed rotating machinery

    DOE Patents [OSTI]

    Post, Richard F.

    1994-01-01

    A centrifugally activated bearing is disclosed. The bearing includes an annular member that extends laterally and radially from a central axis. A rotating member that rotates about the central axis relative to the annular member is also included. The rotating member has an interior chamber that surrounds the central axis and in which the annular member is suspended. Furthermore, the interior chamber has a concave shape for retaining a lubricant therein while the rotating member is at rest and for retaining a lubricant therein while the rotating member is rotating. The concave shape is such that while the rotating member is rotating a centrifugal force causes a lubricant to be forced away from the central axis to form a cylindrical surface having an axis collinear with the central axis. This centrifugally displaced lubricant provides restoring forces to counteract lateral displacement during operation.

  8. Centrifugally activated bearing for high-speed rotating machinery

    DOE Patents [OSTI]

    Post, R.F.

    1994-02-15

    A centrifugally activated bearing is disclosed. The bearing includes an annular member that extends laterally and radially from a central axis. A rotating member that rotates about the central axis relative to the annular member is also included. The rotating member has an interior chamber that surrounds the central axis and in which the annular member is suspended. Furthermore, the interior chamber has a concave shape for retaining a lubricant therein while the rotating member is at rest and for retaining a lubricant therein while the rotating member is rotating. The concave shape is such that while the rotating member is rotating a centrifugal force causes a lubricant to be forced away from the central axis to form a cylindrical surface having an axis collinear with the central axis. This centrifugally displaced lubricant provides restoring forces to counteract lateral displacement during operation. 4 figures.

  9. Failure Atlas for Rolling Bearings in Wind Turbines

    SciTech Connect (OSTI)

    Tallian, T. E.

    2006-01-01

    This Atlas is structured as a supplement to the book: T.E. Tallian: Failure Atlas for Hertz Contact Machine Elements, 2nd edition, ASME Press New York, (1999). The content of the atlas comprises plate pages from the book that contain bearing failure images, application data, and descriptions of failure mode, image, and suspected failure causes. Rolling bearings are a critical component of the mainshaft system, gearbox and generator in the rapidly developing technology of power generating wind turbines. The demands for long service life are stringent; the design load, speed and temperature regimes are demanding and the environmental conditions including weather, contamination, impediments to monitoring and maintenance are often unfavorable. As a result, experience has shown that the rolling bearings are prone to a variety of failure modes that may prevent achievement of design lives. Morphological failure diagnosis is extensively used in the failure analysis and improvement of bearing operation. Accumulated experience shows that the failure appearance and mode of failure causation in wind turbine bearings has many distinguishing features. The present Atlas is a first effort to collect an interpreted database of specifically wind turbine related rolling bearing failures and make it widely available. This Atlas is structured as a supplement to the book: T. E. Tallian: Failure Atlas for Hertz Contact Machine Elements, 2d edition, ASME Press New York, (1999). The main body of that book is a comprehensive collection of self-contained pages called Plates, containing failure images, bearing and application data, and three descriptions: failure mode, image and suspected failure causes. The Plates are sorted by main failure mode into chapters. Each chapter is preceded by a general technical discussion of the failure mode, its appearance and causes. The Plates part is supplemented by an introductory part, describing the appearance classification and failure classification

  10. Preliminary relative permeability estimates of methanehydrate-bearing sand

    SciTech Connect (OSTI)

    Seol, Yongkoo; Kneafsey, Timothy J.; Tomutsa, Liviu; Moridis,George J.

    2006-05-08

    The relative permeability to fluids in hydrate-bearing sediments is an important parameter for predicting natural gas production from gas hydrate reservoirs. We estimated the relative permeability parameters (van Genuchten alpha and m) in a hydrate-bearing sand by means of inverse modeling, which involved matching water saturation predictions with observations from a controlled waterflood experiment. We used x-ray computed tomography (CT) scanning to determine both the porosity and the hydrate and aqueous phase saturation distributions in the samples. X-ray CT images showed that hydrate and aqueous phase saturations are non-uniform, and that water flow focuses in regions of lower hydrate saturation. The relative permeability parameters were estimated at two locations in each sample. Differences between the estimated parameter sets at the two locations were attributed to heterogeneity in the hydrate saturation. Better estimates of the relative permeability parameters require further refinement of the experimental design, and better description of heterogeneity in the numerical inversions.

  11. Bearing repair services offer a cost-effective alternative to expensive replacement

    SciTech Connect (OSTI)

    2009-02-15

    The article, based on a presentation during MINExpo 2008, explains how advancement is bearing design, material, maintenance and repair methods have greatly improved the potential for and popularity of bearing repair as an effective way to extend bearing life. The Trinken Co. offers a variety of service options including repair, recertification, reconditioning and remanufacturing. Benefits of a quality repair program are outlined. 2 photos.

  12. UMC Construction Waste (4493)

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

    collect all Construction waste identified in 2006 and excess through plant sales, recycle through plant scrap metal recycle program, dispose in Y-12 on-site landfill, or ship to...

  13. Waste and Recycling

    ScienceCinema (OSTI)

    McCarthy, Kathy

    2013-05-28

    Nuclear engineer Dr. Kathy McCarthy talks about nuclear energy, the challenge of nuclear waste and the research aimed at solutions. For more information about nuclear energy research, visit http://www.facebook.com/idahonationallaboratory.

  14. Treatment of organic waste

    DOE Patents [OSTI]

    Grantham, LeRoy F.

    1979-01-01

    An organic waste containing at least one element selected from the group consisting of strontium, cesium, iodine and ruthenium is treated to achieve a substantial reduction in the volume of the waste and provide for fixation of the selected element in an inert salt. The method of treatment comprises introducing the organic waste and a source of oxygen into a molten salt bath maintained at an elevated temperature to produce solid and gaseous reaction products. The gaseous reaction products comprise carbon dioxide and water vapor, and the solid reaction products comprise the inorganic ash constituents of the organic waste and the selected element which is retained in the molten salt. The molten salt bath comprises one or more alkali metal carbonates, and may optionally include from 1 to about 25 wt.% of an alkali metal sulfate.

  15. Women of Waste Management

    Broader source: Energy.gov [DOE]

    PHOENIX - For the seventh year at the Waste Management Conference, EM contractor Fluor hosted a discussion on the expanding role of women in environmental management this month in a panel session attended by more than 250 people.

  16. Pioneering Nuclear Waste Disposal

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

    18 19 T he WIPP's first waste receipt, 11 years later than originally planned, was a ... Far from ending, however, the WIPP story has really just begun. For the next 35 years, the ...

  17. Pioneering Nuclear Waste Disposal

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

    ... The names below are those who were on the team on the day of first waste receipt. The U.S. ... Brannan, David Brewer, Danny Britain, Randy Britain, Stacey Brooks, Susan Brown, Barry ...

  18. Uranium- and thorium-bearing pegmatites of the United States

    SciTech Connect (OSTI)

    Adams, J.W.; Arengi, J.T.; Parrish, I.S.

    1980-04-01

    This report is part of the National Uranium Resource Evaluation (NURE) Program designed to identify criteria favorable for the occurrence of the world's significant uranium deposits. This project deals specifically with uranium- and thorium-bearing pegmatites in the United States and, in particular, their distribution and origin. From an extensive literature survey and field examination of 44 pegmatite localities in the United States and Canada, the authors have compiled an index to about 300 uranium- and thorium-bearing pegmatites in the United States, maps giving location of these deposits, and an annotated bibliography to some of the most pertinent literature on the geology of pegmatites. Pegmatites form from late-state magma differentiates rich in volatile constituents with an attendant aqueous vapor phase. It is the presence of an aqueous phase which results in the development of the variable grain size which characterizes pegmatites. All pegmatites occur in areas of tectonic mobility involving crustal material usually along plate margins. Those pegmatites containing radioactive mineral species show, essentially, a similar distribution to those without radioactive minerals. Criteria such as tectonic setting, magma composition, host rock, and elemental indicators among others, all serve to help delineate areas more favorable for uranium- and thorium-bearing pegmatites. The most useful guide remains the radioactivity exhibited by uranium- and thorium-bearing pegmatites. Although pegmatites are frequently noted as favorable hosts for radioactive minerals, the general paucity and sporadic distribution of these minerals and inherent mining and milling difficulties negate the resource potential of pegmatites for uranium and thorium.

  19. Waste Isolation Pilot Plant

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

    Plans and Reports WIPP Recovery Plan The Waste Isolation Pilot Plant (WIPP) Recovery Plan outlines the necessary steps to resume limited waste disposal operations in the first quarter of calendar year 2016. WIPP operations were suspended following an underground truck fire and a radiological release in February 2014. The recovery plan was issued on Sept. 30, 2014. Key elements of the recovery plan include strengthening safety programs, regulatory compliance, decontamination of the underground,

  20. Waste Isolation Pilot Plant

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

    Protective Actions Actions to Protect Workers, Public and the Environment The February 14 radioactivity release was a watershed event for the Waste Isolation Pilot Plant (WIPP). It was the first accident of its kind in the 15-year operating history of the transuranic nuclear waste repository. No workers were underground when the release occurred. There were 11 workers on the night shift at the time of the release and two additional employees entered the site in response to the accident. These 13

  1. Defense Waste Management Programs

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

    Waste Management Programs - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced

  2. Citrus Waste Biomass Program

    SciTech Connect (OSTI)

    Karel Grohman; Scott Stevenson

    2007-01-30

    Renewable Spirits is developing an innovative pilot plant bio-refinery to establish the commercial viability of ehtanol production utilizing a processing waste from citrus juice production. A novel process based on enzymatic hydrolysis of citrus processing waste and fermentation of resulting sugars to ethanol by yeasts was successfully developed in collaboration with a CRADA partner, USDA/ARS Citrus and Subtropical Products Laboratory. The process was also successfully scaled up from laboratory scale to 10,000 gal fermentor level.

  3. Contents TRU Waste Celebration

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

    9 September 2005 A publication for all members of the NNSA/NSO family Contents TRU Waste Celebration by Katherine Schwartz On July 28, 2005, Bechtel Nevada hosted a function to commemorate the dedication and hard work of every Joanne Norton of meeting the milestone of completion of characterization of all legacy waste drums stored at the NTS for 30 years." , assistant general manager for Environmental Management at BN, was equally pleased. making direct contact with it. the dedicated

  4. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

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

    NOV 2 3 2015 New Mexico Environment Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, New Mexico 87505-6303 Subject: Transm ittal of the Waste Isolation Pilot Plant Project 2015 Waste Minimization Report, Permit Number NM4890139088-TSDF Dear Mr. Kieling: The purpose of this letter is to provide you with the Waste Isolation Pilot Plant (WIPP) Project 2015 Waste Minimization Report. This report, required by and prepared in accordance with the WIPP Hazardous Waste Facility Permit Part 2,

  5. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

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

    Carlsbad, New Mexico 8822 1 NOV 2 3 2011 Mr. John Kieling , Acting Bureau Chief Hazardous Waste Bureau New Mexico Environme nt Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, New Mexico 87505-6303 Subject: Transmittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report Dear Mr. Kieling: This letter provides the submittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report. This report is required by and has bee n prepared in accordance with the WIPP

  6. 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

  7. Waste Management | Department of Energy

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

    Management Waste Management Nuclear Materials Disposition Nuclear Materials Disposition In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel. These are not waste. They are nuclear materials no longer needed for national security or other purposes, including spent nuclear fuel, special nuclear materials (as defined by the Atomic Energy Act) and other Nuclear Materials. Read more Tank Waste and Waste Processing Tank Waste

  8. NEXT GENERATION MELTER(S) FOR VITRIFICATION OF HANFORD WASTE STATUS AND DIRECTION

    SciTech Connect (OSTI)

    RAMSEY WG; GRAY MF; CALMUS RB; EDGE JA; GARRETT BG

    2011-01-13

    Vitrification technology has been selected to treat high-level waste (HLW) at the Hanford Site, the West Valley Demonstration Project and the Savannah River Site (SRS), and low activity waste (LAW) at Hanford. In addition, it may potentially be applied to other defense waste streams such as sodium bearing tank waste or calcine. Joule-heated melters (already in service at SRS) will initially be used at the Hanford Site's Waste Treatment and Immobilization Plant (WTP) to vitrify tank waste fractions. The glass waste content and melt/production rates at WTP are limited by the current melter technology. Significant reductions in glass volumes and mission life are only possible with advancements in melter technology coupled with new glass formulations. The Next Generation Melter (NGM) program has been established by the U.S. Department of Energy's (DOE's), Environmental Management Office of Waste Processing (EM-31) to develop melters with greater production capacity (absolute glass throughput rate) and the ability to process melts with higher waste fractions. Advanced systems based on Joule-Heated Ceramic Melter (JHCM) and Cold Crucible Induction Melter (CCIM) technologies will be evaluated for HLW and LAW processing. Washington River Protection Solutions (WRPS), DOE's tank waste contractor, is developing and evaluating these systems in cooperation with EM-31, national and university laboratories, and corporate partners. A primary NGM program goal is to develop the systems (and associated flowsheets) to Technology Readiness Level 6 by 2016. Design and testing are being performed to optimize waste glass process envelopes with melter and balance of plant requirements. A structured decision analysis program will be utilized to assess the performance of the competing melter technologies. Criteria selected for the decision analysis program will include physical process operations, melter performance, system compatibility and other parameters.

  9. Hanford Site annual dangerous waste report. Volume 1, Part 2, Generator dangerous waste report dangerous waste: Calendar Year 1993

    SciTech Connect (OSTI)

    Not Available

    1993-12-31

    This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, weight, waste description, and waste designation.

  10. FY94 site characterization and multilevel well installation at a west Bear Creek Valley research site on the Oak Ridge Reservation

    SciTech Connect (OSTI)

    Moline, G.R.; Schreiber, M.E.

    1996-03-01

    The goals of this project are to collect data that will assist in determining what constitutes a representative groundwater sample in fractured shale typical of much of the geology underlying the ORR waste disposal sites, and to determine how monitoring-well construction and sampling methods impact the representativeness of the sample. This report details the FY94 field activities at a research site in west Bear Creek Valley on the Oak Ridge Reservation (ORR). These activities funded by the Energy Systems Groundwater Program Office through the Oak Ridge Reservation Hydrologic and Geologic Studies (ORRHAGS) task, focus on developing appropriate sampling protocols for the type of fractured media that underlies many of the ORR waste disposal sites. Currently accepted protocols were developed for porous media and are likely to result in nonrepresentative samples in fractured systems.

  11. Salt Waste Processing Facility Fact Sheet | Department of Energy

    Office of Environmental Management (EM)

    Waste Management Tank Waste and Waste Processing Salt Waste Processing Facility Fact Sheet Salt Waste Processing Facility Fact Sheet Nuclear material production operations at ...

  12. Los Alamos exceeds waste shipping goal

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

    exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped more than 3,000 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste headed to the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste headed to the Waste Isolation Pilot Plant in southeastern New Mexico.

  13. Los Alamos exceeds waste shipping goal

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

    Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot

  14. Los Alamos exceeds waste shipping goal

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

    Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot

  15. Waste Isolation Pilot Plant | Department of Energy

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

    Waste Isolation Pilot Plant Waste Isolation Pilot Plant Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations The mission of the Waste Isolation Pilot Plant site is to provide permanent, underground disposal of TRU and TRU-mixed wastes (wastes that also have hazardous chemical components). TRU waste consists of clothing, tools, and debris left from the research and production of nuclear weapons. TRU waste is

  16. High-Speed Shaft Bearing Loads Testing and Modeling in the NREL Gearbox Reliability Collaborative: Preprint

    SciTech Connect (OSTI)

    McNiff, B.; Guo, Y.; Keller, J.; Sethuraman, L.

    2014-12-01

    Bearing failures in the high speed output stage of the gearbox are plaguing the wind turbine industry. Accordingly, the National Renewable Energy Laboratory (NREL) Gearbox Reliability Collaborative (GRC) has performed an experimental and theoretical investigation of loads within these bearings. The purpose of this paper is to describe the instrumentation, calibrations, data post-processing and initial results from this testing and modeling effort. Measured HSS torque, bending, and bearing loads are related to model predictions. Of additional interest is examining if the shaft measurements can be simply related to bearing load measurements, eliminating the need for invasive modifications of the bearing races for such instrumentation.

  17. Waste Treatment Plant - 12508

    SciTech Connect (OSTI)

    Harp, Benton; Olds, Erik

    2012-07-01

    The Waste Treatment Plant (WTP) will immobilize millions of gallons of Hanford's tank waste into solid glass using a proven technology called vitrification. The vitrification process will turn the waste into a stable glass form that is safe for long-term storage. Our discussion of the WTP will include a description of the ongoing design and construction of this large, complex, first-of-a-kind project. The concept for the operation of the WTP is to separate high-level and low-activity waste fractions, and immobilize those fractions in glass using vitrification. The WTP includes four major nuclear facilities and various support facilities. Waste from the Tank Farms is first pumped to the Pretreatment Facility at the WTP through an underground pipe-in-pipe system. When construction is complete, the Pretreatment Facility will be 12 stories high, 540 feet long and 215 feet wide, making it the largest of the four major nuclear facilities that compose the WTP. The total size of this facility will be more than 490,000 square feet. More than 8.2 million craft hours are required to construct this facility. Currently, the Pretreatment Facility is 51 percent complete. At the Pretreatment Facility the waste is pumped to the interior waste feed receipt vessels. Each of these four vessels is 55-feet tall and has a 375,000 gallon capacity, which makes them the largest vessels inside the Pretreatment Facility. These vessels contain a series of internal pulse-jet mixers to keep incoming waste properly mixed. The vessels are inside the black-cell areas, completely enclosed behind thick steel-laced, high strength concrete walls. The black cells are designed to be maintenance free with no moving parts. Once hot operations commence the black-cell area will be inaccessible. Surrounded by black cells, is the 'hot cell canyon'. The hot cell contains all the moving and replaceable components to remove solids and extract liquids. In this area, there is ultrafiltration equipment, cesium

  18. Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan

    SciTech Connect (OSTI)

    Randklev, E.H.

    1993-06-01

    The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented.

  19. SECONDARY WASTE MANAGEMENT STRATEGY FOR EARLY LOW ACTIVITY WASTE TREATMENT

    SciTech Connect (OSTI)

    TW, CRAWFORD

    2008-07-17

    This study evaluates parameters relevant to River Protection Project secondary waste streams generated during Early Low Activity Waste operations and recommends a strategy for secondary waste management that considers groundwater impact, cost, and programmatic risk. The recommended strategy for managing River Protection Project secondary waste is focused on improvements in the Effiuent Treatment Facility. Baseline plans to build a Solidification Treatment Unit adjacent to Effluent Treatment Facility should be enhanced to improve solid waste performance and mitigate corrosion of tanks and piping supporting the Effiuent Treatment Facility evaporator. This approach provides a life-cycle benefit to solid waste performance and reduction of groundwater contaminants.

  20. Enterprise Assessments Operational Awareness Record, Waste Treatment...

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

    systems of the Waste Treatment and Immobilization Plant Low Activity Waste Facility. ... Operational Awareness Record, Waste Treatment and Immobilization Plant - December 2014 ...

  1. BT16 Municipal Solid Waste Resources

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

    Municipal Solid Waste Resources Municipal solid waste (MSW) is a source of biomass ... trimmings, paper and paperboard, plastics, rubber, leather, textiles, and food wastes. ...

  2. Hanford Waste Services Ltd | Open Energy Information

    Open Energy Info (EERE)

    Hanford Waste Services Ltd Jump to: navigation, search Name: Hanford Waste Services Ltd. Place: Wolverhampton, United Kingdom Zip: Wv2 1HR Product: Waste to Energy facility with...

  3. Independent Activity Report, Waste Treatment and Immobilization...

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

    Waste Treatment and Immobilization Plant - March 2013 Independent Activity Report, Waste Treatment and Immobilization Plant - March 2013 March 2013 Follow-up of Waste Treatment and...

  4. Waste Processing Annual Technology Development Report 2007 |...

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

    More Documents & Publications System Planning for Low-Activity Waste at Hanford Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility Caustic Recovery Technology

  5. Densified waste form and method for forming

    DOE Patents [OSTI]

    Garino, Terry J.; Nenoff, Tina M.; Sava Gallis, Dorina Florentina

    2016-05-17

    Materials and methods of making densified waste forms for temperature sensitive waste material, such as nuclear waste, formed with low temperature processing using metallic powder that forms the matrix that encapsulates the temperature sensitive waste material. The densified waste form includes a temperature sensitive waste material in a physically densified matrix, the matrix is a compacted metallic powder. The method for forming the densified waste form includes mixing a metallic powder and a temperature sensitive waste material to form a waste form precursor. The waste form precursor is compacted with sufficient pressure to densify the waste precursor and encapsulate the temperature sensitive waste material in a physically densified matrix.

  6. Enterprise Assessments Review, Waste Isolation Pilot Plant -...

    Office of Environmental Management (EM)

    Waste Isolation Pilot Plant - December 2014 Enterprise Assessments Review, Waste Isolation Pilot Plant - December 2014 December, 2014 Review of the Waste Isolation Pilot Plant ...

  7. Enterprise Assessments Operational Awareness Record, Waste Isolation...

    Office of Environmental Management (EM)

    Record, Waste Isolation Pilot Plant - March 2015 Enterprise Assessments Operational Awareness Record, Waste Isolation Pilot Plant - March 2015 March 2015 Review of the Waste ...

  8. Savannah River Site Waste Disposition Project

    Office of Environmental Management (EM)

    Terrel J. Spears Assistant Manager Waste Disposition Project DOE Savannah River Operations Office Savannah River Site Savannah River Site Waste Disposition Project Waste ...

  9. Tank Waste System Integrated Project Team

    Office of Environmental Management (EM)

    Tank Waste System Tank Waste System Integrated Project Team Integrated Project Team Steve Schneider Office of Engineering and Technology Tank Waste Corporate Board July 29, 2009 2 ...

  10. Nuclear Waste Challenge | Department of Energy

    Office of Environmental Management (EM)

    Consent-Based Siting Nuclear Waste Challenge Nuclear Waste Challenge Approximate locations of the current sites where spent nuclear fuel and high-level radioactive waste are ...

  11. EMAB Tank Waste Subcommittee Report Presentation

    Office of Environmental Management (EM)

    EM Environmental Management Tank Waste Subcommittee (EM- -TWS) TWS) Report to the Report ... Low Assess Candidate Low- -Activity Waste Forms Activity Waste Forms Charge 3: ...

  12. Densified waste form and method for forming

    SciTech Connect (OSTI)

    Garino, Terry J.; Nenoff, Tina M.; Sava Gallis, Dorina Florentina

    2015-08-25

    Materials and methods of making densified waste forms for temperature sensitive waste material, such as nuclear waste, formed with low temperature processing using metallic powder that forms the matrix that encapsulates the temperature sensitive waste material. The densified waste form includes a temperature sensitive waste material in a physically densified matrix, the matrix is a compacted metallic powder. The method for forming the densified waste form includes mixing a metallic powder and a temperature sensitive waste material to form a waste form precursor. The waste form precursor is compacted with sufficient pressure to densify the waste precursor and encapsulate the temperature sensitive waste material in a physically densified matrix.

  13. Waste Confidence Discussion | Department of Energy

    Office of Environmental Management (EM)

    Confidence Discussion Waste Confidence Discussion Long-Term Waste Confidence Update. Waste Confidence Discussion (592.19 KB) More Documents & Publications Status Update: Extended ...

  14. Waste Solidification Building Project Lessons Learned Report...

    Office of Environmental Management (EM)

    Waste Solidification Building Project Lessons Learned Report Waste Solidification Building Project Lessons Learned Report This report addresses lessons learned from the Waste ...

  15. Mixed waste characterization reference document

    SciTech Connect (OSTI)

    1997-09-01

    Waste characterization and monitoring are major activities in the management of waste from generation through storage and treatment to disposal. Adequate waste characterization is necessary to ensure safe storage, selection of appropriate and effective treatment, and adherence to disposal standards. For some wastes characterization objectives can be difficult and costly to achieve. The purpose of this document is to evaluate costs of characterizing one such waste type, mixed (hazardous and radioactive) waste. For the purpose of this document, waste characterization includes treatment system monitoring, where monitoring is a supplement or substitute for waste characterization. This document establishes a cost baseline for mixed waste characterization and treatment system monitoring requirements from which to evaluate alternatives. The cost baseline established as part of this work includes costs for a thermal treatment technology (i.e., a rotary kiln incinerator), a nonthermal treatment process (i.e., waste sorting, macronencapsulation, and catalytic wet oxidation), and no treatment (i.e., disposal of waste at the Waste Isolation Pilot Plant (WIPP)). The analysis of improvement over the baseline includes assessment of promising areas for technology development in front-end waste characterization, process equipment, off gas controls, and monitoring. Based on this assessment, an ideal characterization and monitoring configuration is described that minimizes costs and optimizes resources required for waste characterization.

  16. Using wastes as resources

    SciTech Connect (OSTI)

    Prakasam, T.B.S.; Lue-Hing, C. )

    1992-09-01

    The collection, treatment, and disposal of domestic and industrial wastewater, garbage, and other wastes present considerable problems in urban and semiurban areas of developing countries. Major benefits of using integrated treatment and resource recovery systems include waste stabilization, recovering energy as biogas, producing food from algae and fish, irrigation, improved public health, and aquatic weed control and use. Information and research are needed, however, to assesss the appropriateness, benefits, and limitations of such technology on a large scale. System configuration depends on the types and quantities of wastes available for processing. There must be enough collectable waste for the system to be viable. Information should be gathered to asses whether there is a net public health benefit by implementing a waste treatment and resource recovery system. Benefits such as savings in medical expenses and increased worker productivity due to improved health may be difficult to quantify. The potential health risks created by implementing a resource recovery system should be studied. The most difficult issues to contend with are socioeconomic in nature. Often, the poor performance of a proven technology is attributed to a lack of proper understanding of its principles by the operators, lack of community interest, improper operator training, and poor management. Public education to motivate people to accept technologies that are beneficial to them is important.

  17. Recovery process for complexed copper-bearing rinse waters

    SciTech Connect (OSTI)

    Spearot, R.M.; Peck, J.V.

    1984-05-01

    Conventional chemical treatment methods of removing the copper from metal finishing waste streams prior to discharge generate large quantities of hazardous sludge with associate disposal problem. The advantages and disadvantages of currently available technologies are reviewed. Newer technologies provide economical recovery of the copper, which may be used for other purposes, but not for reuse in the bath. The resulting copper-depleted rinse solutions can then be discharged with other treated metal finishing wastes to publicly owned treatment works (POTW) or to receiving surface waters. Of these newer technologies, selective electrochemical displacement appears to be the best approach in terms of operational efficiency and cost.

  18. Meat-, fish-, and poultry-processing wastes. [Industrial wastes

    SciTech Connect (OSTI)

    Litchfield, J.H.

    1982-06-01

    A review of the literature dealing with the effectiveness of various waste processing methods for meat-, fish,-, and poultry-processing wastes is presented. Activated sludge processes, anaerobic digestion, filtration, screening, oxidation ponds, and aerobic digestion are discussed.

  19. Waste-to-Energy: Waste Management and Energy Production Opportunities...

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

    Waste-to-Energy: Waste Management and Energy Production Opportunities July 24, 2014 9:00AM to 3:30PM EDT U.S. Department of Energy Washington, D.C. The tenth in a series of planned ...

  20. Tank Waste and Waste Processing | Department of Energy

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

    waste stored in underground tanks and approximately 4,000 cubic meters of solid waste derived from the liquids stored in bins. The current DOE estimated cost for retrieval,...

  1. Sampling and analysis plan for the Bear Creek Valley Boneyard/Burnyard Accelerated Action Project, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1998-03-01

    In the Bear Creek Valley Watershed Remedial Investigation, the Boneyard/Burnyard was identified as the source of the largest releases of uranium into groundwater and surface water in Bear Creek Valley. The proposed action for remediation of this site is selective excavation and removal of source material and capping of the remainder of the site. The schedule for this action has been accelerated so that this is the first remedial action planned to be implemented in the Bear Creek Valley Record of Decision. Additional data needs to support design of the remedial action were identified at a data quality objectives meeting held for this project. Sampling at the Boneyard/Burnyard will be conducted through the use of a phased approach. Initial or primary samples will be used to make in-the-field decisions about where to locate follow-up or secondary samples. On the basis of the results of surface water, soil, and groundwater analysis, up to six test pits will be dug. The test pits will be used to provide detailed descriptions of source materials and bulk samples. This document sets forth the requirements and procedures to protect the personnel involved in this project. This document also contains the health and safety plan, quality assurance project plan, waste management plan, data management plan, implementation plan, and best management practices plan for this project as appendices.

  2. Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility

    Office of Environmental Management (EM)

    6 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) HLW Waste Vitrification Facility L. Holton D. Alexander C. Babel H. Sutter J. Young August 2007 Prepared by the U.S. Department of Energy Office of River Protection Richland, Washington, 99352 07-DESIGN-046 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) HLW Waste Vitrification Facility L. Holton D. Alexander C. Babel H. Sutter J. Young August 2007 Prepared by the U.S.

  3. Electrostatic stabilizer for a passive magnetic bearing system

    DOE Patents [OSTI]

    Post, Richard F.

    2015-11-24

    Electrostatic stabilizers are provided for passive bearing systems composed of annular magnets having a net positive stiffness against radial displacements and that have a negative stiffness for vertical displacements, resulting in a vertical instability. Further embodiments are shown of a radial electrostatic stabilizer geometry (using circuitry similar to that employed in the vertical stabilizer). This version is suitable for stabilizing radial (lateral) displacements of a rotor that is levitated by annular permanent magnets that are stable against vertical displacements but are unstable against radial displacements.

  4. Electrostatic stabilizer for a passive magnetic bearing system

    DOE Patents [OSTI]

    Post, Richard F.

    2015-12-01

    Electrostatic stabilizers are provided for passive bearing systems composed of annular magnets having a net positive stiffness against radial displacements and that have a negative stiffness for vertical displacements, resulting in a vertical instability. Further embodiments are shown of a radial electrostatic stabilizer geometry (using circuitry similar to that employed in the vertical stabilizer). This version is suitable for stabilizing radial (lateral) displacements of a rotor that is levitated by annular permanent magnets that are stable against vertical displacements but are unstable against radial displacements.

  5. Method for digesting a nitro-bearing explosive compound

    DOE Patents [OSTI]

    Shah, Manish M.

    2000-01-01

    The present invention is a process wherein superoxide radicals from superoxide salt are used to break down the explosive compounds. The process has an excellent reaction rate for degrading explosives, and operates at ambient temperature and atmospheric pressure in aqueous or non-aqueous conditions. Because the superoxide molecules are small, much smaller than an enzyme molecule for example, they can penetrate the microstructure of plastic explosives faster. The superoxide salt generates reactive hydroxyl radicals, which can destroy other organic contaminants, if necessary, along with digesting the explosive nitro-bearing compound.

  6. Method of fabricating a uranium-bearing foil

    SciTech Connect (OSTI)

    Gooch, Jackie G.; DeMint, Amy L.

    2012-04-24

    Methods of fabricating a uranium-bearing foil are described. The foil may be substantially pure uranium, or may be a uranium alloy such as a uranium-molybdenum alloy. The method typically includes a series of hot rolling operations on a cast plate material to form a thin sheet. These hot rolling operations are typically performed using a process where each pass reduces the thickness of the plate by a substantially constant percentage. The sheet is typically then annealed and then cooled. The process typically concludes with a series of cold rolling passes where each pass reduces the thickness of the plate by a substantially constant thickness amount to form the foil.

  7. RECOVERY OF URANIUM VALUES FROM URANIUM BEARING RAW MATERIALS

    DOE Patents [OSTI]

    Michal, E.J.; Porter, R.R.

    1959-06-16

    Uranium leaching from ground uranium-bearing raw materials using MnO/sub 2/ in H/sub 2/SO/sub 4/ is described. The MnO/sub 2/ oxidizes U to the leachable hexavalent state. The MnO/sub 2/ does not replace Fe normally added, because the Fe complexes P and catalyzes the MnO/sub 2/ reaction. Three examples of continuous processes are given, but batch operation is also possible. The use of MnO/sub 2/ makes possible recovery of very low U values. (T.R.H.)

  8. Silver-bearing, high-temperature, superconducting (HTS) paint

    SciTech Connect (OSTI)

    Ferrando, W.A.

    1990-02-15

    A substantial set of device applications awaits development of a workable, durable, high-temperature superconducting (HTS) paint. Such a paint should be truly superconducting with its critical temperature T sub c>77K. For most of these applications, a high critical current (J sub c) is not required, although probably desirable. A process is described which can be used to produce silver-bearing HTS paint coatings on many engineering materials. Preliminary tests have shown good adherence to several ceramics and the ability to meet the superconducting criteria. Moreover, the coatings withstand multiple thermal cycling and stability under laboratory ambient storage conditions for periods of at least several months.

  9. Stabilization, Packaging, and Storage of Plutonium-Bearing Materials

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

    DOE-STD-3013-2000 September 2000 Superseding DOE-STD-3013-99 November 1999 DOE STANDARD STABILIZATION, PACKAGING, AND STORAGE OF PLUTONIUM-BEARING MATERIALS U.S. Department of Energy AREA PACK Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax:

  10. Stailization, Packaging, and Storage of Plutonium-Bearing Materials

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

    DOE-STD-3013-2012 MARCH 2012 DOE STANDARD STABILIZATION, PACKAGING, AND STORAGE OF PLUTONIUM-BEARING MATERIALS U.S. Department of Energy AREA PACK Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS Available on the Department of Energy Technical Standards Program Web site at http://www.hss.energy.gov/NuclearSafety/ns/techstds/ DOE-STD-3013-2012 iii ABSTRACT This Standard provides guidance for the stabilization, packaging, and safe storage

  11. Criteria for Packaging and Storing Uranium-233-Bearing Materials

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

    3028-2000 July 2000 DOE STANDARD CRITERIA FOR PACKAGING AND STORING URANIUM-233-BEARING MATERIALS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S.

  12. Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant |

    Office of Environmental Management (EM)

    Department of Energy The documents included in this listing are additional references not included in the Phase 2 Radiological Release at the Waste Isolation Pilot Plant, Attachment F: Bibliography and References report. The documents were examined and used to develop the final report. Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant, DOE

  13. Waste Isolation Pilot Plant

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

    4-3542 Site Sustainability Plan Waste Isolation Pilot Plant Fiscal Year 2015 Narrative November 2014 Office of Site Operations Carlsbad Field Office U.S. Department of Energy Approved By: //signature on file// 12/30/14 Jose R. Franco, Date Manager, Carlsbad Field Office Site Sustainability Plan Waste Isolation Pilot Plant, Fiscal Year 2015 Narrative DOE/WIPP-14-3542 Page 2 of 48 TABLE OF CONTENTS I. EXECUTIVE SUMMARY 4 TABLE 1. DOE Goal Summary Table 6 II. PERFORMANCE REVIEW AND PLAN NARRATIVE

  14. Pioneering Nuclear Waste Disposal

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

    30, 1992 President Bush signs into law the WIPP Land Withdrawal Act, designating the EPA as the WIPP's primary regulator. October 21, 1993 DOE moves radioactive waste tests planned for WIPP to national laboratories. December 9, 1993 DOE creates the Carlsbad Area Office to manage the National Transuranic Waste Program and the WIPP. 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 12 study was to analyze long-term per- formance of the underground reposito- ry based on information obtained

  15. 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

  16. Turning nuclear waste into glass

    SciTech Connect (OSTI)

    Pegg, Ian L.

    2015-02-15

    Vitrification has emerged as the treatment option of choice for the most dangerous radioactive waste. But dealing with the nuclear waste legacy of the Cold War will require state-of-the-art facilities and advanced glass formulations.

  17. Low-Level Waste Requirements

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

    1999-07-09

    The guide provides criteria for determining which DOE radioactive wastes are to be managed as low-level waste in accordance with DOE M 435.1-1, Chapter IV.

  18. High-Level Waste Requirements

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

    1999-07-09

    The guide provides the criteria for determining which DOE radioactive wastes are to be managed as high-level waste in accordance with DOE M 435.1-1.

  19. Nevada Waste Leaves Idaho Facility

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

    Nevada Waste Leaves Idaho Facility (Note: This is a reissue of a press release originally ... 15 the afternoon of January 26 actually contained waste from another DOE site in Nevada. ...

  20. Process Waste Assessment - Paint Shop

    SciTech Connect (OSTI)

    Phillips, N.M.

    1993-06-01

    This Process Waste Assessment was conducted to evaluate hazardous wastes generated in the Paint Shop, Building 913, Room 130. Special attention is given to waste streams generated by the spray painting process because it requires a number of steps for preparing, priming, and painting an object. Also, the spray paint booth covers the largest area in R-130. The largest and most costly waste stream to dispose of is {open_quote}Paint Shop waste{close_quotes} -- a combination of paint cans, rags, sticks, filters, and paper containers. These items are compacted in 55-gallon drums and disposed of as solid hazardous waste. Recommendations are made for minimizing waste in the Paint Shop. Paint Shop personnel are very aware of the need to minimize hazardous wastes and are continuously looking for opportunities to do so.

  1. Categorical Exclusion Determinations: Civilian Radioactive Waste...

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

    Civilian Radioactive Waste Management Categorical Exclusion Determinations: Civilian Radioactive Waste Management Categorical Exclusion Determinations issued by Civilian ...

  2. Enterprise Assessments Operational Awareness Record, Waste Treatment...

    Office of Environmental Management (EM)

    Enterprise Assessments Operational Awareness Record, Waste Treatment and Immobilization Plant - March 2015 March 2015 Enterprise Assessments Operational Awareness Record, Waste ...

  3. Waste Heat Recovery Opportunities for Thermoelectric Generators...

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

    Waste Heat Recovery Opportunities for Thermoelectric Generators Waste Heat Recovery Opportunities for Thermoelectric Generators Thermoelectrics have unique advantages for ...

  4. Waste management units - Savannah River Site

    SciTech Connect (OSTI)

    Not Available

    1989-10-01

    This report is a compilation of worksheets from the waste management units of Savannah River Plant. Information is presented on the following: Solid Waste Management Units having received hazardous waste or hazardous constituents with a known release to the environment; Solid Waste Management Units having received hazardous waste or hazardous constituents with no known release to the environment; Solid Waste Management Units having received no hazardous waste or hazardous constituents; Waste Management Units having received source; and special nuclear, or byproduct material only.

  5. 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...

  6. Thermoelectric Generator Development for Automotive Waste Heat...

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

    Generator Development for Automotive Waste Heat Recovery Thermoelectric Generator ... More Documents & Publications Develop Thermoelectric Technology for Automotive Waste Heat ...

  7. Waste Isolation Pilot Plant | Department of Energy

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

    Waste Isolation Pilot Plant Waste Isolation Pilot Plant Operators prepare drums of contact-handled transuranic waste for loading into transportation containers Operators prepare drums of contact-handled transuranic waste for loading into transportation containers A transuranic waste shipment travels on an approved shipping route to the Waste Isolation Pilot Plant A transuranic waste shipment travels on an approved shipping route to the Waste Isolation Pilot Plant Operators prepare drums of

  8. PNNL Supports Hanford Waste Treatment

    SciTech Connect (OSTI)

    2015-06-16

    For more than 40 years, technical assistance from PNNL has supported the operations and processing of Hanford tank waste. Our expertise in tank waste chemistry, fluid dynamics and scaling, waste forms, and safety bases has helped to shape the site’s waste treatment baseline and solve operational challenges. The historical knowledge and unique scientific and technical expertise at PNNL are essential to the success of the Hanford mission.

  9. Tank Waste | Department of Energy

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

    Tank Waste Tank Waste July 28, 2016 Officials mark the completion of construction of the Engineered Scale Test Facility during a ribbon-cutting ceremony July 20. EM Marks Completion of Facility for Low-Activity Waste Pretreatment System RICHLAND, Wash. - The EM Office of River Protection (ORP) completed construction of a new facility designed to validate the technology and systems of the Low-Activity Waste Pretreatment System (LAWPS) on July 17. July 28, 2016 A section of the thermal catalytic

  10. Waste Management | Department of Energy

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

    Management Waste Management Oak Ridge has an onsite CERCLA disposal facility, the Environmental Management Waste Management Facility, that reduces cleanup and transportation costs. Oak Ridge has an onsite CERCLA disposal facility, the Environmental Management Waste Management Facility, that reduces cleanup and transportation costs. Years of diverse research and uranium and isotope production led to numerous forms of waste in Oak Ridge. However, our EM program has worked to identify,

  11. Process for treating fission waste

    DOE Patents [OSTI]

    Rohrmann, Charles A.; Wick, Oswald J.

    1983-01-01

    A method is described for the treatment of fission waste. A glass forming agent, a metal oxide, and a reducing agent are mixed with the fission waste and the mixture is heated. After melting, the mixture separates into a glass phase and a metal phase. The glass phase may be used to safely store the fission waste, while the metal phase contains noble metals recovered from the fission waste.

  12. Chapter 19 - Nuclear Waste Fund

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

    Nuclear Waste Fund 19-1 CHAPTER 19 NUCLEAR WASTE FUND 1. INTRODUCTION. a. Purpose. This chapter establishes the financial, accounting, and budget policies and procedures for civilian and defense nuclear waste activities, as authorized in Public Law 97-425, the Nuclear Waste Policy Act, as amended, referred to hereafter as the Act. b. Applicability. This chapter applies to all Departmental elements, including the National Nuclear Security Administration, and activities that are funded by the

  13. Pu-bearing materials - from fundamental science to storage standards.

    SciTech Connect (OSTI)

    Tam, S. W.; Liu, Y.; Decision and Information Sciences; Michigan Technical Univ.

    2008-01-01

    The behavior of plutonium (Pu) oxides in the presence of water/moisture in a confined space and the associated issues of hydrogen and oxygen generation due to radiolysis have important implications for the storage and transportation of Pu-bearing materials. This paper reviews the results of recent studies of gas generation in the Pu-O-H system, including the determination of release rates via engineering-scale measurement. The observations of the significant differences in gas generation behavior between 'pure' Pu-bearing materials and those that contain salt impurities are addressed. In conjunction with the discussion of these empirical observations, the work also addresses recent scientific advances in the investigations of the Pu-O-H system using state-of-the-art ab initio electronic structure calculations, as well as advanced synchrotron techniques to determine the electronic structure of the various Pu-containing phases. The role of oxidizing species such as the hydroxyl radical from the radiolysis of water is examined. Discussed also is the challenge in the predictive ab-initio calculations of the electronic structure of the Pu-H-O system, due to the nature of the 5f valence electrons in Pu. Coupled with the continuing material surveillance program, it is anticipated that this work may help determine the electronic structure of the various Pu-containing phases and the role of impurity salts on gas generation and the long-term stability of oxygen/hydrogen-containing plutonium oxides beyond PuO{sub 2}.

  14. Evaluation of water saturation in oil-bearing shaly sands

    SciTech Connect (OSTI)

    Martinovic, S.; Vojnovic, V. )

    1990-06-01

    The physical properties of shaly formations are difficult to evaluate because the shale component strongly affects geophysical well log and laboratory test data. This is particularly true in the case of water saturation. On the other hand, the accuracy of in-situ hydrocarbon estimates depends directly on the accuracy of water saturation values. The most important interpretation models for water saturation rely on double-layer models. These interpretation models compute highly probably water saturation values of oil-bearing shaly sands using sound mathematical and physical postulates. Certain disadvantages, such as the inability to evaluate some crucial parameters directly from geophysical well logs, simplifications along the system-model line, inherent deficiencies of logging techniques, etc., give rise to errors and other problems which are more or less solved at this stage of development. A simple program for water saturation of oil-bearing shaly sands was designed and tested. The program uses equations based on double layer models. Program listing and test results also are presented.

  15. Combined passive magnetic bearing element and vibration damper

    DOE Patents [OSTI]

    Post, Richard F.

    2001-01-01

    A magnetic bearing system contains magnetic subsystems which act together to support a rotating element in a state of dynamic equilibrium and dampen transversely directed vibrations. Mechanical stabilizers are provided to hold the suspended system in equilibrium until its speed has exceeded a low critical speed where dynamic effects take over, permitting the achievement of a stable equilibrium for the rotating object. A state of stable equilibrium is achieved above a critical speed by use of a collection of passive elements using permanent magnets to provide their magnetomotive excitation. In a improvement over U.S. Pat. No. 5,495,221, a magnetic bearing element is combined with a vibration damping element to provide a single upper stationary dual-function element. The magnetic forces exerted by such an element, enhances levitation of the rotating object in equilibrium against external forces, such as the force of gravity or forces arising from accelerations, and suppresses the effects of unbalance or inhibits the onset of whirl-type rotor-dynamic instabilities. Concurrently, this equilibrium is made stable against displacement-dependent drag forces of the rotating object from its equilibrium position.

  16. Mixed Waste Working Group report

    SciTech Connect (OSTI)

    Not Available

    1993-11-09

    The treatment of mixed waste remains one of this country`s most vexing environmental problems. Mixed waste is the combination of radioactive waste and hazardous waste, as defined by the Resource Conservation and Recovery Act (RCRA). The Department of Energy (DOE), as the country`s largest mixed waste generator, responsible for 95 percent of the Nation`s mixed waste volume, is now required to address a strict set of milestones under the Federal Facility Compliance Act of 1992. DOE`s earlier failure to adequately address the storage and treatment issues associated with mixed waste has led to a significant backlog of temporarily stored waste, significant quantities of buried waste, limited permanent disposal options, and inadequate treatment solutions. Between May and November of 1993, the Mixed Waste Working Group brought together stakeholders from around the Nation. Scientists, citizens, entrepreneurs, and bureaucrats convened in a series of forums to chart a course for accelerated testing of innovative mixed waste technologies. For the first time, a wide range of stakeholders were asked to examine new technologies that, if given the chance to be tested and evaluated, offer the prospect for better, safer, cheaper, and faster solutions to the mixed waste problem. In a matter of months, the Working Group has managed to bridge a gap between science and perception, engineer and citizen, and has developed a shared program for testing new technologies.

  17. Waste-to-Energy: Waste Management and Energy Production Opportunities |

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

    Department of Energy Waste-to-Energy: Waste Management and Energy Production Opportunities Waste-to-Energy: Waste Management and Energy Production Opportunities July 24, 2014 9:00AM to 3:30PM EDT U.S. Department of Energy Washington, D.C. The tenth in a series of planned U.S. Department of Energy (DOE) Office of Indian Energy-sponsored strategic energy development forums, this Tribal Leader Forum focused on waste-to-energy technology and project opportunities for Indian Tribes. The forum

  18. Waste Management Committee | Department of Energy

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

    Waste Management Committee Waste Management Committee Waste Management Committee Waste Management Committee Mission Statement The Northern New Mexico Citizens' Advisory Board (NNMCAB) Waste Management (WM) Committee reviews policies, practices and procedures, existing and proposed to provide recommendations, advice, suggestions and opinions to the US Department of Energy (DOE), regarding the waste management operations of Los Alamos National Laboratory (LANL), including Environmental Management

  19. The Development of Open Water-lubricated Polycrystalline Diamond (PCD) Thrust Bearings for Use in Marine Hydrokinetic (MHK) Energy Machines

    SciTech Connect (OSTI)

    Cooley, Craig, H.; Khonsari, Michael,, M; Lingwall, Brent

    2012-11-28

    Polycrstalline diamond (PCD) bearings were designed, fabricated and tested for marine-hydro-kinetic (MHK) application. Bearing efficiency and life were evaluated using the US Synthetic bearing test facility. Three iterations of design, build and test were conducted to arrive at the best bearing design. In addition life testing that simulated the starting and stopping and the loading of real MHK applications were performed. Results showed polycrystalline diamond bearings are well suited for MHK applications and that diamond bearing technology is TRL4 ready. Based on life tests results bearing life is estimated to be at least 11.5 years. A calculation method for evaluating the performance of diamond bearings of round geometry was also investigated and developed. Finally, as part of this effort test bearings were supplied free of charge to the University of Alaska for further evaluation. The University of Alaska test program will subject the diamond bearings to sediment laden lubricating fluid.

  20. Radioactive Waste Management

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

    1999-07-09

    The objective of this Order is to ensure that all Department of Energy (DOE) radioactive waste is managed in a manner that is protective of worker and public health and safety and the environment. Supersedes DOE O 5820.2A. Chg 1 dated 8-28-01. Certified 1-9-07.

  1. Radioactive Waste Management

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

    1999-07-09

    The objective of this Order is to ensure that all Department of Energy (DOE) radioactive waste is managed in a manner that is protective of worker and public health and safety and the environment. Cancels DOE O 5820.2A

  2. 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.

  3. Effects of extreme pressure additive chemistry on rolling element bearing surface durability

    SciTech Connect (OSTI)

    Evans, Ryan D.; Nixon, H. P.; Darragh, Craig V.; Howe, Jane Y; Coffey, Dorothy W

    2007-01-01

    Lubricant additives have been known to affect rolling element bearing surface durability for many years. Tapered roller bearings were used in fatigue testing of lubricants formulated with gear oil type additive systems. These systems have sulfur- and phosphoruscontaining compounds used for gear protection as well as bearing lubrication. Several variations of a commercially available base additive formulation were tested having modified sulfur components. The variations represent a range of ''active'' extreme pressure (EP) chemistries. The bearing fatigue test results were compared with respect to EP formulation and test conditions. Inner ring near-surface material in selected test bearings was evaluated on two scales: the micrometer scale using optical metallography and the nanometer scale using transmission electron microscopy (TEM). Focused-ion beam (FIB) techniques were used for TEM specimen preparation. Imaging and chemical analysis of the bearing samples revealed near-surface material and tribofilm characteristics. These results are discussed with respect to the relative fatigue lives.

  4. Mounting arrangement for the drive system of an air-bearing spindle on a machine tool

    DOE Patents [OSTI]

    Lunsford, J.S.; Crisp, D.W.; Petrowski, P.L.

    1987-12-07

    The present invention is directed to a mounting arrangement for the drive system of an air-bearing spindle utilized on a machine tool such as a lathe. The mounting arrangement of the present invention comprises a housing which is secured to the casing of the air bearing in such a manner that the housing position can be selectively adjusted to provide alignment of the air-bearing drive shaft supported by the housing and the air-bearing spindle. Once this alignment is achieved the air between spindle and the drive arrangement is maintained in permanent alignment so as to overcome misalignment problems encountered in the operation of the machine tool between the air-bearing spindle and the shaft utilized for driving the air-bearing spindle.

  5. Hanford Tank Waste - Near Source Treatment of Low Activity Waste

    SciTech Connect (OSTI)

    Ramsey, William Gene

    2013-08-15

    Abstract only. Treatment and disposition of Hanford Site waste as currently planned consists of 100+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory of this waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most of the leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper

  6. Tank waste concentration mechanism study

    SciTech Connect (OSTI)

    Pan, L.C.; Johnson, L.J.

    1994-09-01

    This study determines whether the existing 242-A Evaporator should continue to be used to concentrate the Hanford Site radioactive liquid tank wastes or be replaced by an alternative waste concentration process. Using the same philosophy, the study also determines what the waste concentration mechanism should be for the future TWRS program. Excess water from liquid DST waste should be removed to reduce the volume of waste feed for pretreatment, immobilization, and to free up storage capacity in existing tanks to support interim stabilization of SSTS, terminal cleanout of excess facilities, and other site remediation activities.

  7. LANL reaches waste shipment milestone

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

    LANL reaches waste shipment milestone LANL reaches waste shipment milestone The Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total. May 31, 2011 A shipment of transuranic waste on its way to the WIPP repository A shipment of transuranic waste on its way to the WIPP repository. Contact Fred deSousa Communications Office (505) 665-3430 Email LOS ALAMOS, New Mexico, May 31, 2011 - Los Alamos National Laboratory has reached an important

  8. Development of a container for the transportation and storage of plutonium bearing materials

    SciTech Connect (OSTI)

    Ammerman, D.; Geinitz, R.; Thorp, D.; Rivera, M.

    1998-03-01

    There is a large backlog of plutonium contaminated materials at the Rocky Flats Environmental Technology Site near Denver, Colorado, USA. The clean-up of this site requires this material to be packaged in such a way as to allow for efficient transportation to other sites or to a permanent geologic repository. Prior to off-site shipment of the material, it may be stored on-site for a period of time. For this reason, it is desirable to have a container capable of meeting the requirements for storage as well as the requirements for transportation. Most of the off-site transportation is envisioned to take place using the TRUPACT-II Type B package, with the Waste Isolation Pilot Plant (WIPP) as the destination. Prior to the development of this new container, the TRUPACT-II had a limit of 325 FGE (fissile gram equivalents) of plutonium due to criticality control concerns. Because of the relatively high plutonium content in the material to be transported, transporting 325 FGE per TRUPACT-II is uneconomical. Thus, the purpose of the new containers is to provide criticality control to increase the allowed TRUPACT-II payload and to provide a safe method for on-site storage prior to transport. This paper will describe the analysis and testing used to demonstrate that the Pipe Overpack Container provides safe on-site storage of plutonium bearing materials in unhardened buildings and provides criticality control during transportation within the TRUPACT-II. Analyses included worst-case criticality analyses, analyses of fork-lift time impacts, and analyses of roof structure collapse onto the container. Testing included dynamic crush tests, bare pipe impact tests, a 30-minute totally engulfing pool-fire test, and multiple package impact tests in end-on and side-on orientations.

  9. Y-12 donates DVDs, teddy bears to Children's Hospital | Y-12 National

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

    Security Complex Y-12 donates DVDs, teddy ... Y-12 donates DVDs, teddy bears to Children's Hospital Posted: January 24, 2014 - 3:33pm Pictured from left to right: Y-12ers Karen Dixon, Linda Cantrell and John Buck decorate the Christmas tree in the lobby of Y-12's Jack Case Center with donated teddy bears. Some 360 bears and other animals were collected for patients at the East Tennessee Children's Hospital. More than 350 DVDs and some 360 teddy bears were collected by Y-12 employees for

  10. Categorical Excluslon DeterminatIon 11'orn1 Project Title: Bear...

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

    DeterminatIon 11'orn1 ...... Project Title: Bear Creek Road Deferred Maintenance Reduction Project (4550) Program or Program Office: Y-12 Site Office Oak Ridge Tennessee Project...

  11. Potassium chloride-bearing ice VII and ice planet dynamics (Journal...

    Office of Scientific and Technical Information (OSTI)

    Title: Potassium chloride-bearing ice VII and ice planet dynamics Authors: Frank, Mark R. ; Scott, Henry P. ; Aarestad, Elizabeth ; Prakapenka, Vitali B. 1 ; UC) 2 ; NIU) 2 + ...

  12. Hanford tank waste pretreatment overview

    SciTech Connect (OSTI)

    Gasper, K.A.

    1994-12-31

    The U.S. Department of Energy (DOE) has established the Tank Waste Remediation System (TWRS) to safely manage and dispose of the Hanford Site tank waste. Pretreatment is one of the major program elements of the TWRS. The scope of the TWRS Tank Waste Pretreatment Program is to treat tank waste to separate it into high- and low-level waste fractions and to provide additional treatment as required to feed low-level and high-level waste immobilization processes. The Pretreatment Program activities include technology development, design, fabrication, construction, and operation of facilities to support the pretreatment of radioactive mixed waste retrieved from 28 large underground double-shell tanks and 149 single-shell tanks.

  13. Treatment of halogen-containing waste and other waste materials

    DOE Patents [OSTI]

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

    1997-03-18

    A process is described for treating a halogen-containing waste material. The process provides a bath of molten glass containing a sacrificial metal oxide capable of reacting with a halogen in the waste material. The sacrificial metal oxide is present in the molten glass in at least a stoichiometric amount with respect to the halogen in the waste material. The waste material is introduced into the bath of molten glass to cause a reaction between the halogen in the waste material and the sacrificial metal oxide to yield a metal halide. The metal halide is a gas at the temperature of the molten glass. The gaseous metal halide is separated from the molten glass and contacted with an aqueous scrubber solution of an alkali metal hydroxide to yield a metal hydroxide or metal oxide-containing precipitate and a soluble alkali metal halide. The precipitate is then separated from the aqueous scrubber solution. The molten glass containing the treated waste material is removed from the bath as a waste glass. The process of the invention can be used to treat all types of waste material including radioactive wastes. The process is particularly suited for separating halogens from halogen-containing wastes. 3 figs.

  14. Treatment of halogen-containing waste and other waste materials

    DOE Patents [OSTI]

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

    1997-01-01

    A process for treating a halogen-containing waste material. The process provides a bath of molten glass containing a sacrificial metal oxide capable of reacting with a halogen in the waste material. The sacrificial metal oxide is present in the molten glass in at least a stoichiometric amount with respect to the halogen in the waste material. The waste material is introduced into the bath of molten glass to cause a reaction between the halogen in the waste material and the sacrificial metal oxide to yield a metal halide. The metal halide is a gas at the temperature of the molten glass. The gaseous metal halide is separated from the molten glass and contacted with an aqueous scrubber solution of an alkali metal hydroxide to yield a metal hydroxide or metal oxide-containing precipitate and a soluble alkali metal halide. The precipitate is then separated from the aqueous scrubber solution. The molten glass containing the treated waste material is removed from the bath as a waste glass. The process of the invention can be used to treat all types of waste material including radioactive wastes. The process is particularly suited for separating halogens from halogen-containing wastes.

  15. Exploring the structure of high temperature, iron-bearing liquids

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

    Wilding, Martin; Benmore, Chris; Weber, Rick; Parise, John; Lazareva, Lena; Skinner, Lawrie; Alderman, Oliver; Tamalonis, Antony

    2015-06-25

    This paper describes the direct measurements of the structure of iron-bearing liquids using a combination of containerless techniques and in–situ high energy x-ray diffraction. These capabilities provide data that is important to help model and optimize processes such as smelting, steel making, and controlling slag chemistry. A successful programme of liquid studies has been undertaken and the Advanced Photon Source using these combined techniques which include the provision of gas mixing and the control of pO₂ and the changing influence of mixed valance elements. It is possible to combine rapid image acquisition with quenching of liquids to obtain the fullmore » diffraction patterns of deeply supercooled liquids and the metastable supercooled liquid regime, where the liquid structures and viscosity change most dramatically, can also be explored.« less

  16. Preliminary relative permeability estimates of methanehydrate-bearing sand

    SciTech Connect (OSTI)

    Seol, Yongkoo; Kneafsey, Timothy J.; Tomutsa, Liviu; Moridis,George J.

    2006-05-08

    The relative permeability to fluids in hydrate-bearingsediments is an important parameter for predicting natural gas productionfrom gas hydrate reservoirs. We estimated the relative permeabilityparameters (van Genuchten alpha and m) in a hydrate-bearing sand by meansof inverse modeling, which involved matching water saturation predictionswith observations from a controlled waterflood experiment. We used x-raycomputed tomography (CT) scanning to determine both the porosity and thehydrate and aqueous phase saturation distributions in the samples. X-rayCT images showed that hydrate and aqueous phase saturations arenon-uniform, and that water flow focuses in regions of lower hydratesaturation. The relative permeability parameters were estimated at twolocations in each sample. Differences between the estimated parametersets at the two locations were attributed to heterogeneity in the hydratesaturation. Better estimates of the relative permeability parametersrequire further refinement of the experimental design, and betterdescription of heterogeneity in the numerical inversions.

  17. Exploring the structure of high temperature, iron-bearing liquids

    SciTech Connect (OSTI)

    Wilding, Martin; Benmore, Chris; Weber, Rick; Parise, John; Lazareva, Lena; Skinner, Lawrie; Alderman, Oliver; Tamalonis, Antony

    2015-06-25

    This paper describes the direct measurements of the structure of iron-bearing liquids using a combination of containerless techniques and in–situ high energy x-ray diffraction. These capabilities provide data that is important to help model and optimize processes such as smelting, steel making, and controlling slag chemistry. A successful programme of liquid studies has been undertaken and the Advanced Photon Source using these combined techniques which include the provision of gas mixing and the control of pO₂ and the changing influence of mixed valance elements. It is possible to combine rapid image acquisition with quenching of liquids to obtain the full diffraction patterns of deeply supercooled liquids and the metastable supercooled liquid regime, where the liquid structures and viscosity change most dramatically, can also be explored.

  18. Sealed rotary hearth furnace with central bearing support

    DOE Patents [OSTI]

    Docherty, James P. (Carnegie, PA); Johnson, Beverly E. (Pittsburgh, PA); Beri, Joseph (Morgan, PA)

    1989-01-01

    The furnace has a hearth which rotates inside a stationary closed chamber and is supported therein on vertical cylindrical conduit which extends through the furnace floor and is supported by a single center bearing. The charge is deposited through the furnace roof on the rim of the hearth as it rotates and is moved toward the center of the hearth by rabbles. Externally generated hot gases are introduced into the furnace chamber below the hearth and rise through perforations in the hearth and up through the charge. Exhaust gases are withdrawn through the furnace roof. Treated charge drops from a center outlet on the hearth into the vertical cylindrical conduit which extends downwardly through the furnace floor to which it is also sealed.

  19. Response of oceanic hydrate-bearing sediments to thermalstresses

    SciTech Connect (OSTI)

    Moridis, G.J.; Kowalsky, M.B.

    2006-05-01

    In this study, we evaluate the response of oceanicsubsurface systems to thermal stresses caused by the flow of warm fluidsthrough noninsulated well systems crossing hydrate-bearing sediments.Heat transport from warm fluids, originating from deeper reservoirs underproduction, into the geologic media can cause dissociation of the gashydrates. The objective of this study is to determine whether gasevolution from hydrate dissociation can lead to excessive pressurebuildup, and possibly to fracturing of hydrate-bearing formations andtheir confining layers, with potentially adverse consequences on thestability of the suboceanic subsurface. This study also aims to determinewhether the loss of the hydrate--known to have a strong cementing effecton the porous media--in the vicinity of the well, coupled with thesignificant pressure increases, can undermine the structural stability ofthe well assembly.Scoping 1D simulations indicated that the formationintrinsic permeability, the pore compressibility, the temperature of theproduced fluids andthe initial hydrate saturation are the most importantfactors affecting the system response, while the thermal conductivity andporosity (above a certain level) appear to have a secondary effect.Large-scale simulations of realistic systems were also conducted,involving complex well designs and multilayered geologic media withnonuniform distribution of properties and initial hydrate saturationsthat are typical of those expected in natural oceanic systems. Theresults of the 2D study indicate that although the dissociation radiusremains rather limited even after long-term production, low intrinsicpermeability and/or high hydrate saturation can lead to the evolution ofhigh pressures that can threaten the formation and its boundaries withfracturing. Although lower maximum pressures are observed in the absenceof bottom confining layers and in deeper (and thus warmer and morepressurized) systems, the reduction is limited. Wellbore designs withgravel

  20. Tritium waste package

    DOE Patents [OSTI]

    Rossmassler, R.; Ciebiera, L.; Tulipano, F.J.; Vinson, S.; Walters, R.T.

    1995-11-07

    A containment and waste package system for processing and shipping tritium oxide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within the outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen and oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB. 1 fig.

  1. Tritium waste package

    DOE Patents [OSTI]

    Rossmassler, Rich; Ciebiera, Lloyd; Tulipano, Francis J.; Vinson, Sylvester; Walters, R. Thomas

    1995-01-01

    A containment and waste package system for processing and shipping tritium xide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen add oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

  2. Waste Isolation Pilot Plant

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

    15/16 WIPP Home Page About WIPP Contact Us Search Recovery Facts WIPP Progress Since 2014 Events February 2016 - Year in Review Recovery Posters and Factsheets Ionizing Radiation Dose Ranges Doses from Radiation Sources Comparison Bioassay Chart Radiation and WIPP Employees WIPP Facts Fire and Radiological Event Locations Emplaced Waste WIPP Aerial Photo WIPP Ventilation System WIPP Layout Recovery Plan Factsheet Deep Geologic Disposal In Salt Radiation Radiation and Radioactive Materials

  3. Waste Isolation Pilot Plant

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

    News Releases December 29, 2015 Emergency Operations Center Level 1 Activation August 4, 2015 Event News Release #4 Event News Release #3 Event News Release #2 Event News Release #1 Joint Information Center Activated at WIPP Emergency Operations Center Activated at WIPP June 02, 2015 Nitrate Waste Stream Isolated at WIPP December 22, 2014 CBFO Manager Letter #14 November 04, 2014 CBFO Manager Letter #13 September 30, 2014 Department of Energy Releases WIPP Recovery Plan June 18, 2014 CBFO

  4. Municipal Solid Waste:

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

    Methodology for Allocating Municipal Solid Waste to Biogenic and Non-Biogenic Energy May 2007 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the U.S. Department of Energy. The information contained herein should be attributed to the Energy Information Administration and should not be

  5. PROCESSING OF RADIOACTIVE WASTE

    DOE Patents [OSTI]

    Johnson, B.M. Jr.; Barton, G.B.

    1961-11-14

    A process for treating radioactive waste solutions prior to disposal is described. A water-soluble phosphate, borate, and/or silicate is added. The solution is sprayed with steam into a space heated from 325 to 400 deg C whereby a powder is formed. The powder is melted and calcined at from 800 to 1000 deg C. Water vapor and gaseous products are separated from the glass formed. (AEC)

  6. Transuranic (TRU) Waste | Department of Energy

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

    Transuranic (TRU) Waste Transuranic (TRU) Waste Transuranic (TRU) Waste Defined by the WIPP Land Withdrawal Act as "waste containing more than 100 nanocuries of alpha-emitting transuranic isotopes per gram of waste with half-lives greater than 20 years, except for (A) high-level radioactive waste, (B) waste that the Secretary of Energy has determined, with concurrence of the Administrator of the Environmental Protection Agency, does not need the degree of isolation required by the disposal

  7. Waste Receipt Quality Assurance Program - Hanford Site

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

    Receipt Quality Assurance Program About Us Hanford Site Solid Waste Acceptance Program What's New Acceptance Criteria Acceptance Process Becoming a new Hanford Customer Annual Waste Forecast and Funding Arrangements Waste Stream Approval Waste Shipment Approval Waste Receipt Quality Assurance Program Waste Specification Records Tools Points of Contact Waste Receipt Quality Assurance Program Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size The Hanford Site has a

  8. Lab sets new record for waste shipments

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

    New record for waste shipments Lab sets new record for waste shipments LANL completing its 132nd transuranic (TRU) waste shipment of fiscal year 2010 to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. August 20, 2010 LANL's shipment of transuranic waste leaves Los Alamos. LANL's shipment of transuranic waste leaves Los Alamos. Contact Fred deSousa Communications Office (505) 500-5672 Email "Removing this waste from Los Alamos is crucial to our plans for overall

  9. WIPP Documents - Hazardous Waste Facility Permit (RCRA)

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

    Hazardous Waste Facility Permit The WIPP Hazardous Waste Facility Permit (HWFP) effective April 15, 2011 WIPP Hazardous Waste Facility Permit Authorizes the U.S. Department of Energy to manage, store, and dispose of contact-handled and remote-handled transuranic mixed waste at the Waste Isolation Pilot Plant. Mixed waste contains radioactive and chemically hazardous components. Information Repository Documents related to the Hazardous Waste Facility Permit

  10. Evaluation of Used Fuel Disposition in Clay-Bearing Rock

    SciTech Connect (OSTI)

    Jové Colón, Carlos F.; Weck, Philippe F.; Sassani, David H.; Zheng, Liange; Rutqvist, Jonny; Steefel, Carl I.; Kim, Kunhwi; Nakagawa, Seiji; Houseworth, James; Birkholzer, Jens; Caporuscio, Florie A.; Cheshire, Michael; Rearick, Michael S.; McCarney, Mary K.; Zavarin, Mavrik; Benedicto, Ana; Kersting, Annie B.; Sutton, Mark; Jerden, James; Frey, Kurt E.; Copple, Jacqueline M.; Ebert, William

    2014-08-01

    Radioactive waste disposal in shale/argillite rock formations has been widely considered given its desirable isolation properties (low permeability), geochemically reduced conditions, anomalous groundwater pressures, and widespread geologic occurrence. Clay/shale rock formations are characterized by their high content of clay minerals such as smectites and illites where diffusive transport and chemisorption phenomena predominate. These, in addition to low permeability, are key attributes of shale to impede radionuclide mobility. Shale host-media has been comprehensively studied in international nuclear waste repository programs as part of underground research laboratories (URLs) programs in Switzerland, France, Belgium, and Japan. These investigations, in some cases a decade or more long, have produced a large but fundamental body of information spanning from site characterization data (geological, hydrogeological, geochemical, geomechanical) to controlled experiments on the engineered barrier system (EBS) (barrier clay and seals materials). Evaluation of nuclear waste disposal in shale formations in the USA was conducted in the late 70’s and mid 80’s. Most of these studies evaluated the potential for shale to host a nuclear waste repository but not at the programmatic level of URLs in international repository programs. This report covers various R&D work and capabilities relevant to disposal of heat-generating nuclear waste in shale/argillite media. Integration and cross-fertilization of these capabilities will be utilized in the development and implementation of the shale/argillite reference case planned for FY15. Disposal R&D activities under the UFDC in the past few years have produced state-of-the-art modeling capabilities for coupled Thermal-Hydrological-Mechanical-Chemical (THMC), used fuel degradation (source term), and thermodynamic modeling and database development to evaluate generic disposal concepts. The THMC models have been developed for shale

  11. he Hanford Story Tank Waste Cleanup | Department of Energy

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

    he Hanford Story Tank Waste Cleanup he Hanford Story Tank Waste Cleanup Addthis Description The Hanford Story Tank Waste Cleanup

  12. Waste water filtration enhancement

    SciTech Connect (OSTI)

    Martin, H.L.

    1989-01-01

    Removal of submicron particles from process solutions and waste water is now economically achievable using a new Tyvek{reg sign} media in conventional filtration equipment. This new product greatly enhances filtration and allows use of the much improved filter aids and polymers which were recently developed. It has reduced operating costs and ensures a clean effluent discharge to the environment. This significant technical development is especially important to those who discharge to a small stream with low 7Q10 flow and must soon routinely pass the Toxicity tests that are being required by many States for NPDES permit renewal. The Savannah River Plant produces special nuclear materials for the US Government. Aluminum forming and metal finishing operations in M-Area, that manufacture fuel and target assemblies for the nuclear reactors, discharge to a waste water treatment facility using BAT hydroxide precipitation and filtration. The new Tyvek{reg sign} media and filter aids have achieved 55% less solids in the filtrate discharged to Tims Branch Creek, 15% less hazardous waste (dry filter cake), 150%-370% more filtration capacity, 74% lower materials purchase cost, 10% lower total M-Area manufacturing cost, and have improved safety. Performance with the improved polymers is now being evaluated.

  13. Radioactive waste processing apparatus

    DOE Patents [OSTI]

    Nelson, Robert E.; Ziegler, Anton A.; Serino, David F.; Basnar, Paul J.

    1987-01-01

    Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container.

  14. Coolside waste management research

    SciTech Connect (OSTI)

    Not Available

    1992-10-01

    Sample collection - soils, base sand, and conventional fly ash for loading the field lysimeter calls were selected and either obtained or in process of being delivered. Chemical and Mineralogical Characterization of the Waste - This activity is proceeding with proximate and ultimate analysis of the materials being completed. In addition the major and minor element analysis was performed by several analytical techniques. The protocol for rapid, thick-target proton induced x-ray emission (PIXE) and proton induced gamma emission (PIGE) spectroscopy were developed. Analysis of 97 Coolside waste samples from Run 3 and 77 samples from Run 1 showed a wide range of concentration values were observed for most of the values. In Run 3 calcium content increased with time and titanium content decreased. Likewise, a change in sodium content occurred with average concentrations being 1.26 [plus minus] 0.03 wt% during the first half of the run while it dropped to 1.18 [plus minus] 0.03 wt% in the latter part of the run. Vanadium and bromine directly correlate with the calcium content indicating these elements are either introduced in the hydrated lime or their capture efficiency depends on the calcium concentration in the waste. The other elements whose concentrations increase with time are zinc, germanium, arsenic, gallium and lead but do not appear to be introduced with the lime or have capture efficiencies that are affected by the calcium content in the ash.

  15. Method for processing aqueous wastes

    DOE Patents [OSTI]

    Pickett, J.B.; Martin, H.L.; Langton, C.A.; Harley, W.W.

    1993-12-28

    A method is presented for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply. 4 figures.

  16. Method for processing aqueous wastes

    SciTech Connect (OSTI)

    Pickett, John B.; Martin, Hollis L.; Langton, Christine A.; Harley, Willie W.

    1993-01-01

    A method for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply.

  17. Method for processing aqueous wastes

    SciTech Connect (OSTI)

    Pickett, J.B.; Martin, H.L.; Langton, C.A.; Harley, W.W.

    1992-12-31

    This invention is comprised of a method for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply.

  18. Naval Waste Package Design Report

    SciTech Connect (OSTI)

    M.M. Lewis

    2004-03-15

    A design methodology for the waste packages and ancillary components, viz., the emplacement pallets and drip shields, has been developed to provide designs that satisfy the safety and operational requirements of the Yucca Mountain Project. This methodology is described in the ''Waste Package Design Methodology Report'' Mecham 2004 [DIRS 166168]. To demonstrate the practicability of this design methodology, four waste package design configurations have been selected to illustrate the application of the methodology. These four design configurations are the 21-pressurized water reactor (PWR) Absorber Plate waste package, the 44-boiling water reactor (BWR) waste package, the 5-defense high-level waste (DHLW)/United States (U.S.) Department of Energy (DOE) spent nuclear fuel (SNF) Co-disposal Short waste package, and the Naval Canistered SNF Long waste package. Also included in this demonstration is the emplacement pallet and continuous drip shield. The purpose of this report is to document how that design methodology has been applied to the waste package design configurations intended to accommodate naval canistered SNF. This demonstrates that the design methodology can be applied successfully to this waste package design configuration and support the License Application for construction of the repository.

  19. Waste Characterization, Reduction, and Repackaging Facility (WCRRF) Waste

    Office of Environmental Management (EM)

    Characterization Glovebox Operations, EP-WCRR-WO-DOP-0233 | Department of Energy Operations, EP-WCRR-WO-DOP-0233 Waste Characterization, Reduction, and Repackaging Facility (WCRRF) Waste Characterization Glovebox Operations, EP-WCRR-WO-DOP-0233 The documents included in this listing are additional references not included in the Phase 2 Radiological Release at the Waste Isolation Pilot Plant, Attachment F: Bibliography and References report. The documents were examined and used to develop the

  20. The First Recovery Act Funded Waste Shipment depart from the...

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

    The First Recovery Act Funded Waste Shipment departs from the Advanced Mixed Waste Treatment Facility A shipment of mixed low-level waste left DOEs Advanced Mixed Waste ...

  1. Transuranic Waste Processing Center Oak Ridge Site Specific...

    Office of Environmental Management (EM)

    Transuranic Waste Processing Update Oak Ridge Site Specific Advisory Board May 14, 2014 ...EM 3 Oak Ridge Transuranic (TRU) Waste Inventory * TRU waste is waste ...

  2. Scalable, Efficient Solid Waste Burner System - Energy Innovation...

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

    A system that effectively burns solid human waste where traditional waste management ... is a semi-gasifier, burner device to process solid waste, particularly solid human waste. ...

  3. Tank waste chemistry: A new understanding of waste aging

    SciTech Connect (OSTI)

    Babad, H.; Camaioni, D.M.; Lilga, M.A.; Samuels, W.D.; Strachan, D.M.

    1993-02-01

    There is concern about the risk of uncontrolled exothermic reaction(s) in Hanford Site waste tanks containing NO{sub 3}{sup {minus}}/NO{sub 2} based salts and/or metal hydroxide sludges in combination with organics or ferrocyanides. However, gradual oxidation of the waste in the tanks to less reactive species appears to have reduced the risk. In addition, wastes sampled to date contain sufficiently large quantities of water so that propagation reactions are highly unlikely. This paper investigates various aspects of the aging of Hanford tank wastes.

  4. Methane generation from animal wastes

    SciTech Connect (OSTI)

    Fulton, E.L.

    1980-06-01

    The conversion of manure to biogas via anaerobic digestion is described. The effluent resulting from the conversion retains fertilizer value and is environmentally acceptable. Discussion is presented under the headings: methane formation in the digester; the Tarleton State Poultry Waste to Methane production system; operating experience at Tarleton State; economics of biogas production from poultry waste; construction cost and biogas value; energy uses; feed and waste processing; and advantages of anaerobic digestion. (DMC)

  5. Waste management units - Savannah River Site. Volume 1, Waste management unit worksheets

    SciTech Connect (OSTI)

    Not Available

    1989-10-01

    This report is a compilation of worksheets from the waste management units of Savannah River Plant. Information is presented on the following: Solid Waste Management Units having received hazardous waste or hazardous constituents with a known release to the environment; Solid Waste Management Units having received hazardous waste or hazardous constituents with no known release to the environment; Solid Waste Management Units having received no hazardous waste or hazardous constituents; Waste Management Units having received source; and special nuclear, or byproduct material only.

  6. Tritium Waste Treatment System component failure data analysis from June 18, 1984--December 31, 1989

    SciTech Connect (OSTI)

    Cadwallader, L.C. ); Stolpe Gavett, M.A. )

    1990-09-01

    This document gives the failure rates for the major tritium-bearing components in the Tritium Waste Treatment System at the Tritium Systems Test Assembly, which is a fusion research and technology facility at the Los Alamos National Laboratory. The failure reports, component populations, and operating demands/hours are given in this report, and sample calculations for binomial demand failure rates and poisson hourly failure rates are given in the appendices. The failure rates for tritium-bearing components were on the order of the screening failure rate values suggested for fusion reliability and risk analyses. More effort should be directed toward collecting and analyzing fusion component failure data, since accurate failure rates are necessary to refine reliability and risk analyses. 15 refs., 4 figs., 4 tabs.

  7. SECONDARY WASTE MANAGEMENT FOR HANFORD EARLY LOW ACTIVITY WASTE VITRIFICATION

    SciTech Connect (OSTI)

    UNTERREINER BJ

    2008-07-18

    More than 200 million liters (53 million gallons) of highly radioactive and hazardous waste is stored at the U.S. Department of Energy's Hanford Site in southeastern Washington State. The DOE's Hanford Site River Protection Project (RPP) mission includes tank waste retrieval, waste treatment, waste disposal, and tank farms closure activities. This mission will largely be accomplished by the construction and operation of three large treatment facilities at the Waste Treatment and Immobilization Plant (WTP): (1) a Pretreatment (PT) facility intended to separate the tank waste into High Level Waste (HLW) and Low Activity Waste (LAW); (2) a HLW vitrification facility intended to immobilize the HLW for disposal at a geologic repository in Yucca Mountain; and (3) a LAW vitrification facility intended to immobilize the LAW for shallow land burial at Hanford's Integrated Disposal Facility (IDF). The LAW facility is on target to be completed in 2014, five years prior to the completion of the rest of the WTP. In order to gain experience in the operation of the LAW vitrification facility, accelerate retrieval from single-shell tank (SST) farms, and hasten the completion of the LAW immobilization, it has been proposed to begin treatment of the low-activity waste five years before the conclusion of the WTP's construction. A challenge with this strategy is that the stream containing the LAW vitrification facility off-gas treatment condensates will not have the option of recycling back to pretreatment, and will instead be treated by the Hanford Effluent Treatment Facility (ETF). Here the off-gas condensates will be immobilized into a secondary waste form; ETF solid waste.

  8. Process for preparing liquid wastes

    DOE Patents [OSTI]

    Oden, Laurance L.; Turner, Paul C.; O'Connor, William K.; Hansen, Jeffrey S.

    1997-01-01

    A process for preparing radioactive and other hazardous liquid wastes for treatment by the method of vitrification or melting is provided for.

  9. Reporting Fraud, Waste, and Abuse

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

    2004-09-15

    This Notice reminds all DOE employees of their duty to report allegations of fraud, waste, and abuse to the Office of Inspector General. No cancellation.

  10. Treatment of mercury containing waste

    DOE Patents [OSTI]

    Kalb, Paul D.; Melamed, Dan; Patel, Bhavesh R; Fuhrmann, Mark

    2002-01-01

    A process is provided for the treatment of mercury containing waste in a single reaction vessel which includes a) stabilizing the waste with sulfur polymer cement under an inert atmosphere to form a resulting mixture and b) encapsulating the resulting mixture by heating the mixture to form a molten product and casting the molten product as a monolithic final waste form. Additional sulfur polymer cement can be added in the encapsulation step if needed, and a stabilizing additive can be added in the process to improve the leaching properties of the waste form.

  11. Anaerobic treatment of food wastes

    SciTech Connect (OSTI)

    Criner, G. )

    1991-04-01

    This article describes a research project at the University of Maine in which food wastes from the University cafeteria salad bar are processed in the anaerobic facility which normally treats only animal wastes. The project has benefited the University in several ways: avoidance of waste disposal fees; increased electricity co-generated from the biogas process; and use of the residual as fertilizer. An economic analysis indicated that the estimated cost of anaerobic treatment of the salad bar wastes was $4520/yr and benefits were $4793/yr. Since the digester was already in use, this cost was not factored into the analysis. Further studies are being planned.

  12. Nuclear Waste Partnership Contract Modifications

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

    Waste Partnership Contract DE-EM0001971 Modifications NWP Modification Index Description Modification 001 Modification 002 Modification 003 Modification 004 Modification 005...

  13. Progress Update: TRU Waste Shipping

    ScienceCinema (OSTI)

    Cody, Tom

    2012-06-14

    A progress update at the Savannah River Site. A continued effort on shipping TRU waste to WIPP in Carlsbad, New Mexico.

  14. Hydrothermal Processing of Wet Wastes

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

    Processing of Wet Wastes James Oyler July 2014 Slide 1 Slide 2 Q: What is possible with Waste-to-Energy (WTE)? A: Up to 25% of US Liquid Fuel Supply. 25% Sounds High-Is That Possible? * Available technology and wet wastes can start toward this goal now * 285,000 barrels of oil per day by 2025 - 3.3 million bbl/d by 2045 (17% of US demand); also produces more than 6 million MCF/d of methane - Continue growing to 25% of US demand by adding more feedstocks (chart shown later) * Using wastes solves

  15. Geomechanical Performance of Hydrate-Bearing Sediment in Offshore Environments

    SciTech Connect (OSTI)

    Stephen Holditch; Tad Patzek; Jonny Rutqvist; George Moridis; Richard Plumb

    2008-03-31

    The objective of this multi-year, multi-institutional research project was to develop the knowledge base and quantitative predictive capability for the description of geomechanical performance of hydrate-bearing sediments (hereafter referred to as HBS) in oceanic environments. The focus was on the determination of the envelope of hydrate stability under conditions typical of those related to the construction and operation of offshore platforms. We have developed a robust numerical simulator of hydrate behavior in geologic media by coupling a reservoir model with a commercial geomechanical code. We also investigated the geomechanical behavior of oceanic HBS using pore-scale models (conceptual and mathematical) of fluid flow, stress analysis, and damage propagation. The objective of the UC Berkeley work was to develop a grain-scale model of hydrate-bearing sediments. Hydrate dissociation alters the strength of HBS. In particular, transformation of hydrate clusters into gas and liquid water weakens the skeleton and, simultaneously, reduces the effective stress by increasing the pore pressure. The large-scale objective of the study is evaluation of geomechanical stability of offshore oil and gas production infrastructure. At Lawrence Berkeley National Laboratory (LBNL), we have developed the numerical model TOUGH + Hydrate + FLAC3D to evaluate how the formation and disassociation of hydrates in seafloor sediments affects seafloor stability. Several technical papers were published using results from this model. LBNL also developed laboratory equipment and methods to produce realistic laboratory samples of sediments containing gas hydrates so that mechanical properties could be measured in the laboratory. These properties are required to run TOUGH + Hydrate + FLAC3D to evaluate seafloor stability issues. At Texas A&M University we performed a detailed literature review to determine what gas hydrate formation properties had been measured and reported in the literature. We

  16. Development programs in the United States of America for the application of cement-based grouts in radioactive waste management

    SciTech Connect (OSTI)

    Dole, L.R.; Row, T.H.

    1984-01-01

    This paper briefly reviews seven cement-based waste form development programs at six of the US Department of Energy (DOE) sites. These sites have developed a variety of processes that range from producing 25 mm (1 in.) diameter pellets in a glove box to producing 240 m (800 ft.) diameter grout sheets within the bedding planes of a deep shale formation. These successful applications of cement-based waste forms to the many radioactive waste streams from nuclear facilities bear witness to the flexibility and reliability of this class of materials. This paper also discusses the major issues regarding the application of cement-based waste forms to radioactive waste management problems. These issues are (1) leachability, (2) radiation stability, (3) thermal stability, (4) phase complexity of the matrix, and (5) effects of the waste stream composition. A cursory review of current research in each of these areas is given This paper also discusses future trends in cement-based waste form development and applications. 31 references, 11 figures.

  17. Radioactive waste processing apparatus

    DOE Patents [OSTI]

    Nelson, R.E.; Ziegler, A.A.; Serino, D.F.; Basnar, P.J.

    1985-08-30

    Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container. The chamber may be formed by placing a removable extension over the top of the container. The extension communicates with the apparatus so that such vapors are contained within the container, extension and solution feed apparatus. A portion of the chamber includes coolant which condenses the vapors. The resulting condensate is returned to the container by the force of gravity.

  18. Tank Waste Committee

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

    3/15 Tank Waste Committee Priorities for advice on FY17 budget Not in priority order, numbering refers to last year's related advice points, per DOE response  (#1) The Board strongly urges DOE-Headquarters (HQ) to request full funding from Congress to meet all legal requirements of the ongoing cleanup work in FY 2016 and 2017 in addition to the following specific requests.  (#2) The Board advises DOE-ORP continue to request funding to proceed to empty leaking tanks (particularly AY-102 and

  19. Waste Isolation Pilot Plant

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

    What happened at WIPP in February 2014 Burned Truck Salt hauling truck after the fire Two isolated events took place at the Waste Isolation Pilot Plant (WIPP) in February. On February 5, a salt haul truck caught fire. Workers were evacuated, and the underground portion of WIPP was shut down. Six workers were treated for smoke inhalation. Nine days later, late in the evening of February 14, a second, unrelated event occurred when a continuous air monitor (CAM) alarmed during the night shift. Only

  20. Hanford Dangerous Waste Permit

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

    Single-Shell Tank System Closing Unit #4 The tanks and surrounding contaminated soil are one of Hanford's greatest challenges. We don't really know the full extent of the risks yet. Removing wastes from the tanks will greatly reduce the risks. An ongoing risk assessment for the SST closures will ensure the risks are below acceptable levels. How does this part of the permit differ from the usual? SSTs do not comply with regulations, so the permit requires SSTs to be closed as soon as possible.

  1. Municipal waste processing apparatus

    DOE Patents [OSTI]

    Mayberry, John L.

    1988-01-01

    Municipal waste materials are processed by crushing the materials so that pieces of noncombustible material are smaller than a selected size and pieces of combustible material are larger than the selected size. The crushed materials are placed on a vibrating mesh screen conveyor belt having openings which pass the smaller, noncombustible pieces of material, but do not pass the larger, combustible pieces of material. Pieces of material which become lodged in the openings of the conveyor belt may be removed by cylindrical deraggers or pressurized air. The crushed materials may be fed onto the conveyor belt by a vibrating feed plate which shakes the materials so that they tend to lie flat.

  2. Municipal waste processing apparatus

    DOE Patents [OSTI]

    Mayberry, John L.

    1989-01-01

    Municipal waste materials are processed by crushing the materials so that pieces of noncombustible material are smaller than a selected size and pieces of combustible material are larger than the selected size. The crushed materials are placed on a vibrating mesh screen conveyor belt having openings which pass the smaller, noncombustible pieces of material, but do not pass the larger, combustible pieces of material. Consecutive conveyors may be connected by an intermediate vibratory plate. An air knife can be used to further separate materials based on weight.

  3. Tank Waste Remediation System Tank Waste Analysis Plan. FY 1995

    SciTech Connect (OSTI)

    Haller, C.S.; Dove, T.H.

    1994-11-01

    This documents lays the groundwork for preparing the implementing the TWRS tank waste analysis planning and reporting for Fiscal Year 1995. This Tank Waste Characterization Plan meets the requirements specified in the Hanford Federal Facility Agreement and Consent Order, better known as the Tri-Party Agreement.

  4. Waste acceptance criteria for the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    NONE

    1996-04-01

    The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies.

  5. Waste Isolation Pilot Plant (WIPP) Waste Information System (Public Access)

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

    The Waste Isolation Pilot Plant (WIPP) is a DOE facility located in the desert outside Carlsbad, New Mexico. Its mission is to safely dispose of defense-related transuranic radioactive waste. Disposal ôroomsö are carved out of the Permian Salt Formation deep below the desertÆs surface. The WIPP Waste Information Service (WWIS) was established in accordance with an Agreement between the United States Department of Energy and the New Mexico Environment Department, dated February 11, 2005, Docket Number HWB 04-07 (CO). The service provides information the containers emplaced at WIPP and the waste products they hold. The public may query by shipment number, location of waste stream or location of the container after it is placed at WIPP, date placed, and Haz Codes or other information about the waste stream profiles. For example, choosing the waste stream identified as ID-SDA-SLUDGE reveals that it may contain more than 20 chemical waste products, including arsenic, spent halogenated solvents, potassium cyanide, and chloroform. The system then tells you each numbered container that has this kind of sludge. Container data is available within 14 days after the containerÆs emplacement in the WIPP Repository.

  6. Waste to energy – key element for sustainable waste management

    SciTech Connect (OSTI)

    Brunner, Paul H. Rechberger, Helmut

    2015-03-15

    Highlights: • First paper on the importance of incineration from a urban metabolism point of view. • Proves that incineration is necessary for sustainable waste management. • Historical and technical overview of 100 years development of MSW incineration. - Abstract: Human activities inevitably result in wastes. The higher the material turnover, and the more complex and divers the materials produced, the more challenging it is for waste management to reach the goals of “protection of men and environment” and “resource conservation”. Waste incineration, introduced originally for volume reduction and hygienic reasons, went through a long and intense development. Together with prevention and recycling measures, waste to energy (WTE) facilities contribute significantly to reaching the goals of waste management. Sophisticated air pollution control (APC) devices ensure that emissions are environmentally safe. Incinerators are crucial and unique for the complete destruction of hazardous organic materials, to reduce risks due to pathogenic microorganisms and viruses, and for concentrating valuable as well as toxic metals in certain fractions. Bottom ash and APC residues have become new sources of secondary metals, hence incineration has become a materials recycling facility, too. WTE plants are supporting decisions about waste and environmental management: They can routinely and cost effectively supply information about chemical waste composition as well as about the ratio of biogenic to fossil carbon in MSW and off-gas.

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

    SciTech Connect (OSTI)

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

    2015-09-30

    decrease the need for expensive engineered barriers.Our current work aims are 1) quantifying and understanding the processes associated with glass alteration in contact with Fe-bearing materials; 2) quantifying and understanding the processes associated with glass alteration in presence of MgO (example of engineered barrier used in WIPP); 3) identifying glass alteration suppressants and the processes involved to reach glass alteration suppression; 4) quantifying and understanding the processes associated with Saltstone and Cast Stone (SRS and Hanford cementitious waste forms) in various representative groundwaters; 5) investigating positron annihilation as a new tool for the study of glass alteration; and 6) quantifying and understanding the processes associated with glass alteration under gamma irradiation.

  8. Lesson 7 - Waste from Nuclear Power Plants | Department of Energy

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

    7 - Waste from Nuclear Power Plants Lesson 7 - Waste from Nuclear Power Plants This lesson takes a look at the waste from electricity production at nuclear power plants. It considers the different types of waste generated, as well as how we deal with each type of waste. Specific topics covered include: Nuclear Waste Some radioactive Types of radioactive waste Low-level waste High-level waste Disposal and storage Low-level waste disposal Spent fuel storage Waste isolation Reprocessing

  9. ALUMINUM REMOVAL FROM HANFORD WASTE BY LITHIUM HYDROTALCITE PRECIPITATION - LABORATORY SCALE VALIDATION ON WASTE SIMULANTS TEST REPORT

    SciTech Connect (OSTI)

    SAMS T; HAGERTY K

    2011-01-27

    To reduce the additional sodium hydroxide and ease processing of aluminum bearing sludge, the lithium hydrotalcite (LiHT) process has been invented by AREV A and demonstrated on a laboratory scale to remove alumina and regenerate/recycle sodium hydroxide prior to processing in the WTP. The method uses lithium hydroxide (LiOH) to precipitate sodium aluminate (NaAI(OH){sub 4}) as lithium hydrotalcite (Li{sub 2}CO{sub 3}.4Al(OH){sub 3}.3H{sub 2}O) while generating sodium hydroxide (NaOH). In addition, phosphate substitutes in the reaction to a high degree, also as a filterable solid. The sodium hydroxide enriched leachate is depleted in aluminum and phosphate, and is recycled to double-shell tanks (DSTs) to leach aluminum bearing sludges. This method eliminates importing sodium hydroxide to leach alumina sludge and eliminates a large fraction of the total sludge mass to be treated by the WTP. Plugging of process equipment is reduced by removal of both aluminum and phosphate in the tank wastes. Laboratory tests were conducted to verify the efficacy of the process and confirm the results of previous tests. These tests used both single-shell tank (SST) and DST simulants.

  10. Development of Erbia-bearing Super High Burnup Fuel

    SciTech Connect (OSTI)

    Akio, Yamamoto; Toshikazu, Takeda; Hironobu, Unesaki; Masaaki, Mori; Masatoshi Yamasaki

    2006-07-01

    In this paper, concept and development plan of the Erbia (Er{sub 2}O{sub 3})-bearing super high burnup (Er-SHB) fuel for LWRs are described. In order to reduce the number of spent fuel assemblies, utilization of high burnup fuels with higher uranium enrichment is effective. However, the upper limitation of enrichment for LWR fuels is 5 wt% and current advanced fuel assemblies for LWRs are already reaching this limit. Though various efforts to overcome the 5 wt% enrichment limit have been undergoing, it will require considerable cost that may offset the economic benefit of high burnup fuels. We are proposing another pathway. By adding low content ({>=}0.2 wt%) of Erbia in all UO{sub 2} powder, reactivity of high enrichment (>5 wt%) fuel is suppressed under that of current fuel assemblies, i.e. we leverage the negative reactivity credit of Erbia. Since Erbia is mixed into UO{sub 2} powder just after the re-conversion, we can avoid most of the criticality safety issues appearing in the front-end stream. Namely, major improvements and re-licensing for equipments in transportation, storage and fabrication process will not be necessary. Therefore, the Er-SHB fuel will significantly contribute to reduction of fuel cycle cost. (authors)

  11. Prediction of hydrocarbon-bearing structures based on remote sensing

    SciTech Connect (OSTI)

    Smirnova, I.; Gololobov, Yu.; Rusanova, A. )

    1993-09-01

    The technology we developed is based on the use of remotely sensed data and has proved to be effective for identification of structures that appear promising for oil and gas, in particular, reefs in the hydrocarbon-bearing basin of central Asia (Turkmenistan and Uzbekistan). It implements the [open quotes]geoindication[close quotes] concept, the main idea being that landscape components (geoindicators) and subsurface geological features are correlated and depend on each other. Subsurface features (uplifts, depressions, faults, reefs, and other lithological and structural heterogeneities) cause physical and chemical alterations in overlying rocks up to the land surface; thus, they are reflected in distribution of landscape components and observed on airborne and satellite images as specific patterns. The following identified geoindicators are related to different subsurface geological features: definite formations, anticlines, and reefs (barrier, atoll, and bioherm). The geoindicators are extracted from images either visually or by using computer systems. Specially developed software is applied to analyze geoindicator distribution and calculate their characteristics. In the course of processing, it is possible to distinguish folds from reefs. Distribution of geoindicator characteristics is examined on the well studied reefs, and from the regularities, established promising areas with reefs are revealed. When applying the technology in central Asia, the results were successfully verified by field works, seismic methods, and drilling.

  12. The Integrated Waste Tracking System - A Flexible Waste Management Tool

    SciTech Connect (OSTI)

    Anderson, Robert Stephen

    2001-02-01

    The US Department of Energy (DOE) Idaho National Engineering and Environmental Laboratory (INEEL) has fully embraced a flexible, computer-based tool to help increase waste management efficiency and integrate multiple operational functions from waste generation through waste disposition while reducing cost. The Integrated Waste Tracking System (IWTS)provides comprehensive information management for containerized waste during generation,storage, treatment, transport, and disposal. The IWTS provides all information necessary for facilities to properly manage and demonstrate regulatory compliance. As a platformindependent, client-server and Web-based inventory and compliance system, the IWTS has proven to be a successful tracking, characterization, compliance, and reporting tool that meets the needs of both operations and management while providing a high level of management flexibility.

  13. Nuclear Waste Policy Act | Department of Energy

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

    Nuclear Waste Policy Act Nuclear Waste Policy Act Document on the Nuclear Waste Policy Act of 1982 An Act to provide for the development of repositories for the disposal of ...

  14. 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 ...

  15. Nuclear waste storage container with metal matrix

    DOE Patents [OSTI]

    Sump, Kenneth R.

    1978-01-01

    The invention relates to a storage container for high-level waste having a metal matrix for the high-level waste, thereby providing greater impact strength for the waste container and increasing heat transfer properties.

  16. Apparatus for the processing of solid mixed waste containing radioactive and hazardous materials

    DOE Patents [OSTI]

    Gotovchikov, Vitaly T.; Ivanov, Alexander V.; Filippov, Eugene A.

    1999-03-16

    Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination oaf plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

  17. Apparatus for the processing of solid mixed waste containing radioactive and hazardous materials

    DOE Patents [OSTI]

    Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

    1999-03-16

    Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter. 6 figs.

  18. Environmental sustainability comparison of a hypothetical pneumatic waste collection system and a door-to-door system

    SciTech Connect (OSTI)

    Punkkinen, Henna; Merta, Elina; Teerioja, Nea; Moliis, Katja; Kuvaja, Eveliina

    2012-10-15

    Highlights: Black-Right-Pointing-Pointer We compare the environmental sustainability of two MSW collection systems. Black-Right-Pointing-Pointer We evaluate pneumatic and door-to-door collection systems. Black-Right-Pointing-Pointer The greenhouse gas emissions of pneumatic collection are around three times higher. Black-Right-Pointing-Pointer System components are decisive but assumptions on electricity use are also important. Black-Right-Pointing-Pointer Pneumatic collection could provide other benefits over door-to-door system. - Abstract: Waste collection is one of the life cycle phases that influence the environmental sustainability of waste management. Pneumatic waste collection systems represent a new way of arranging waste collection in densely populated urban areas. However, limited information is available on the environmental impacts of this system. In this study, we compare the environmental sustainability of conventional door-to-door waste collection with its hypothetical pneumatic alternative. Furthermore, we analyse whether the size of the hypothetical pneumatic system, or the number of waste fractions included, have an impact on the results. Environmental loads are calculated for a hypothetical pneumatic waste collection system modelled on an existing dense urban area in Helsinki, Finland, and the results are compared to those of the prevailing, container-based, door-to-door waste collection system. The evaluation method used is the life-cycle inventory (LCI). In this study, we report the atmospheric emissions of greenhouse gases (GHG), SO{sub 2} and NO{sub x}. The results indicate that replacing the prevailing system with stationary pneumatic waste collection in an existing urban infrastructure would increase total air emissions. Locally, in the waste collection area, emissions would nonetheless diminish, as collection traffic decreases. While the electricity consumption of the hypothetical pneumatic system and the origin of electricity have a

  19. Vitrification of hazardous and radioactive wastes

    SciTech Connect (OSTI)

    Bickford, D.F.; Schumacher, R.

    1995-12-31

    Vitrification offers many attractive waste stabilization options. Versatility of waste compositions, as well as the inherent durability of a glass waste form, have made vitrification the treatment of choice for high-level radioactive wastes. Adapting the technology to other hazardous and radioactive waste streams will provide an environmentally acceptable solution to many of the waste challenges that face the public today. This document reviews various types and technologies involved in vitrification.

  20. LANL sets TRU waste hauling record

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

    sets TRU waste hauling record LANL sets TRU waste hauling record TRU waste consists of clothing, tools, rags, debris, soil, and other items contaminated with radioactive elements, mostly plutonium. October 4, 2011 TRU waste from LANL to WIPP TRU waste from LANL to WIPP Contact Colleen Curran Communications Office (505) 664-0344 Email LOS ALAMOS, New Mexico, October 4, 2011-Los Alamos National Laboratory has set a new LANL record for the amount of transuranic (TRU) waste from past