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1

Feasibility Study for Vitrification of Sodium-Bearing Waste  

SciTech Connect

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.

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

2000-09-01T23:59:59.000Z

2

Sodium-Bearing Waste Treatment Alternatives Implementation Study  

SciTech Connect

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).

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

2004-07-01T23:59:59.000Z

3

Steam Reforming Application for Treatment of DOE Sodium Bearing Tank Wastes at INL for ICP  

SciTech Connect

The patented THOR steam reforming waste treatment technology has been selected as the technology of choice for treatment of Sodium Bearing Waste (SBW) at the Idaho National Laboratory (INL) for the Idaho Cleanup Project (ICP). SBW is an acidic tank waste at the Idaho Nuclear Technology and Engineering Center (INTEC) at INL. It consists primarily of waste from decontamination activities and laboratory wastes. SBW contains high concentrations of nitric acid, alkali and aluminum nitrates, with minor amounts of many inorganic compounds including radionuclides, mainly cesium and strontium. The THOR steam reforming process will convert the SBW tank waste feed into a dry, solid, granular product. The THOR technology was selected to treat SBW, in part, because it can provide flexible disposal options to accommodate the final disposition path selected for SBW. THOR can produce a final end-product that will meet anticipated requirements for disposal as Remote-Handled TRU (RH-TRU) waste; and, with modifications, THOR can also produce a final endproduct that could be qualified for disposal as High Level Waste (HLW). SBW treatment will be take place within the Integrated Waste Treatment Unit (IWTU), a new facility that will be located at the INTEC. This paper provides an overview of the THOR process chemistry and process equipment being designed for the IWTU.

J. Bradley Mason; Kevin Ryan; Scott Roesener; Michael Cowen; Duane Schmoker; Pat Bacala; Bill Landman

2006-03-01T23:59:59.000Z

4

TRUEX partitioning studies applied to ICPP sodium-bearing waste  

SciTech Connect

The Idaho Chemical Processing Plant (ICPP), located in southeast Idaho at the USDOE Idaho National Engineering Laboratory, formerly reprocessed highly enriched spent nuclear fuel to recover fissionable uranium. The HLW raffinates from the combined PUREX/REDOX type uranium recovery process were converted to solid oxides (calcine) in a high temperature fluidized bed. Liquid effluents from the calcination process were combined with liquid sodium bearing waste (SBW) generated primarily in conjunction with decontamination activities. Due to the high sodium content in the SBW, this secondary waste stream is not directly amenable to solidification via calcination. Currently, approximately 1.5 millon gallons of liquid SBW are stored at the ICPP in large tanks. Several treatment options for the SBW are currently being considered, including the TRansUranic EXtraction (TRUEX) process developed by Horwitz and co-workers at Argonne National Laboratory (ANL), in preparation for the final disposition of SBW. Herein described are experimental results of radionuclide tracer studies with simulated SBW using the TRUEX process solvent.

Herbst, R.S.; Brewer, K.N.; Law, J.D.; Tranter, T.J.; Todd, T.A.

1994-05-01T23:59:59.000Z

5

EIS-0287: Notice of Preferred Sodium Bearing Waste Treatment Technology |  

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

Preferred Sodium Bearing Waste Treatment Preferred Sodium Bearing Waste Treatment Technology EIS-0287: Notice of Preferred Sodium Bearing Waste Treatment Technology Idaho High-Level Waste (HLW) and Facilities Disposition In October 2002, the U.S. Department of Energy (DOE or the Department) issued the Final Idaho High-Level Waste (HLW) and Facilities Disposition Environmental Impact Statement (DOE/EIS-0287 (Final EIS)). The Final EIS contains an evaluation of reasonable alternatives for the management of mixed transuranic waste/sodium bearing waste (SBW),1 mixed HLW calcine, and associated low-level waste (LLW), as well as disposition alternatives for HLW facilities when their missions are completed. DOE/EIS-0287, Notice of Preferred Sodium Bearing Waste Treatment Technology, Office of Environmental Management, Idaho, 70 FR 44598 (August

6

Sodium-bearing Waste Treatment Technology Evaluation Report  

SciTech Connect

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). 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.

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

2004-05-01T23:59:59.000Z

7

Independent Oversight Review, Sodium Bearing Waste Treatment...  

Energy Savers (EERE)

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

8

Independent Oversight Review, Sodium Bearing Waste Treatment...  

Energy Savers (EERE)

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

9

Characterization of Tank WM-189 Sodium-bearing Waste at INTEC, Rev. 1  

SciTech Connect

Idaho Nuclear Technology and Engineering Center 300,000-gallon vessel WM-189 was filled in late 2001 with concentrated sodium bearing waste (SBW). Three airlifted liquid samples and a steam jetted slurry sample were obtained for quantitative analysis and characterization of WM-189 liquid phase SBW and tank heel sludge. Estimates were provided for most of the reported data values, based on the greater of (a) analytical uncertainty, and (b) variation of analytical results between nominally similar samples. A consistency check on the data was performed by comparing the total mass of dissolved solids in the liquid, as measured gravimetrically from a dried sample, with the corresponding value obtained by summing the masses of cations and anions in the liquid, based on the reported analytical data. After reasonable adjustments to the nitrate and oxygen concentrations, satisfactory consistency between the two results was obtained. A similar consistency check was performed on the reported compositional data for sludge solids from the steam jetted sample. In addition to the compositional data, various other analyses were performed: particle size distribution was measured for the sludge solids, sludge settling tests were performed, and viscosity measurements were made. WM-189 characterization results were compared with those for WM-180, and other Tank Farm Facility tank characterization data. A 2-liter batch of WM-189 simulant was prepared and a clear, stable solution was obtained, based on a general procedure for mixing SBW simulant that was develop by Dr. Jerry Christian. This WM-189 SBW simulant is considered suitable for laboratory testing for process development.

Batcheller, Thomas Aquinas; Taylor, Dean Dalton

2003-07-01T23:59:59.000Z

10

Baseline Flowsheet Generation for the Treatment and Disposal of Idaho National Engineering and Environmental Laboratory Sodium Bearing Waste  

SciTech Connect

The High-Level Waste (HLW) Program at the Idaho National Engineering and Environmental Laboratory (INEEL) must implement technologies and processes to treat and qualify radioactive wastes located at the Idaho Nuclear Technology and Engineering Center (INTEC) for permanent disposal. This paper describes the approach and accomplishments to date for completing development of a baseline vitrification treatment flowsheet for sodium-bearing waste (SBW), including development of a relational database used to manage the associated process assumptions. A process baseline has been developed that includes process requirements, basis and assumptions, process flow diagrams, a process description, and a mass balance. In the absence of actual process or experimental results, mass and energy balance data for certain process steps are based on assumptions. Identification, documentation, validation, and overall management of the flowsheet assumptions are critical to ensuring an integrated, focused program. The INEEL HLW Program initially used a roadmapping methodology, developed through the INEEL Environmental Management Integration Program, to identify, document, and assess the uncertainty and risk associated with the SBW flowsheet process assumptions. However, the mass balance assumptions, process configuration and requirements should be accessible to all program participants. This need resulted in the creation of a relational database that provides formal documentation and tracking of the programmatic uncertainties related to the SBW flowsheet.

Barnes, Charles Marshall; Lauerhass, Lance; Olson, Arlin Leland; Taylor, Dean Dalton; Valentine, James Henry; Lockie, Keith Andrew

2002-02-01T23:59:59.000Z

11

Baseline Flowsheet Generation for the Treatment and Disposal of Idaho National Engineering and Environmental Laboratory Sodium Bearing Waste  

SciTech Connect

The High-Level Waste (HLW) Program at the Idaho National Engineering and Environmental Laboratory (INEEL) must implement technologies and processes to treat and qualify radioactive wastes located at the Idaho Nuclear Technology and Engineering Center (INTEC) for permanent disposal. This paper describes the approach and accomplishments to date for completing development of a baseline vitrification treatment flowsheet for sodium-bearing waste (SBW), including development of a relational database used to manage the associated process assumptions. A process baseline has been developed that includes process requirements, basis and assumptions, process flow diagrams, a process description, and a mass balance. In the absence of actual process or experimental results, mass and energy balance data for certain process steps are based on assumptions. Identification, documentation, validation, and overall management of the flowsheet assumptions are critical to ensuring an integrated, focused program. The INEEL HLW Program initially used a roadmapping methodology, developed through the INEEL Environmental Management Integration Program, to identify, document, and assess the uncertainty and risk associated with the SBW flowsheet process assumptions. However, the mass balance assumptions, process configuration and requirements should be accessible to all program participants. This need resulted in the creation of a relational database that provides formal documentation and tracking of the programmatic uncertainties related to the SBW flowsheet.

Barnes, C.M.; Lauerhass, L.; Olson, A.L.; Taylor, D.D.; Valentine, J.H.; Lockie, K.A. (DOE- ID)

2002-01-16T23:59:59.000Z

12

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

SciTech Connect

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.

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

2004-01-01T23:59:59.000Z

13

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

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

598 598 Federal Register / Vol. 70, No. 148 / Wednesday, August 3, 2005 / Notices 1 The Final EIS refers to SBW as mixed transuranic waste/SBW. However, a determination that SBW is transuranic waste has not been made. overseas citizens, as well as the individual and combined number of such ballots returned and cast by such voters. (42 U.S.C. 1973ff-1(c)) 5. Individuals entitled to vote otherwise than in person under the Voter Accessibility for the Elderly and Handicapped Act (42 U.S.C. 1973ee- 1(b)(2)(B)(ii)) or any other Federal law. States must identify registrants who are entitled to cast an absentee ballot under such statutes as they are exempt from HAVA's 42 U.S.C. 15483(b)(2) identification requirements. F. What obligations do election officials have concerning the security of the

14

Fluidized Bed Steam Reforming of INEEL SBW Using THORsm Mineralizing Technology  

SciTech Connect

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 process achieved about a 90% turnover of the starting bed. Samples of mineralized solid product materials were analyzed for chemical/physical properties. Results of product performance testing conducted by SRNL will be reported separately by SRNL.

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

2004-12-01T23:59:59.000Z

15

Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container  

E-Print Network (OSTI)

HEPA filtration. On April 11, 2014, in anticipation of investigation of the source of a radiological on the possibility that a container of inadequately remediated nitrate salt bearing waste had caused the release and is the most Page 1 of 17 #12;likely source of the release. Further investigation is underway to determine

Napp, Nils

16

Independent Oversight Review, Sodium Bearing Waste Treatment Project -  

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

Sodium Bearing Waste Treatment Sodium Bearing Waste Treatment Project - Contractor - June 2012 Independent Oversight Review, Sodium Bearing Waste Treatment Project - Contractor - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Contractor Operational Readiness Review This report documents the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), independent review of the Sodium Bearing Waste Treatment Project-Integrated Waste Treatment Unit (SBWTP-IWTU) contractor Operational Readiness Review (C-ORR). The review was conducted at the Idaho Site from February 27 to March 6, 2012. This report discusses the background, scope, results, and conclusions of the review, as well as

17

Independent Oversight Review, Sodium Bearing Waste Treatment Project -  

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

Sodium Bearing Waste Treatment Sodium Bearing Waste Treatment Project - Federal - June 2012 Independent Oversight Review, Sodium Bearing Waste Treatment Project - Federal - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Federal Operational Readiness Review This report documents the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), independent review of the Sodium Bearing Waste Treatment Project-Integrated Waste Treatment Unit (SBWTP-IWTU) DOE (Federal) Operational Readiness Review (D-ORR). The review was performed by the HSS Office of Safety and Emergency Management Evaluations and was intended to assess the effectiveness of the CORR process as implemented for

18

Independent Oversight Review, Sodium Bearing Waste Treatment Project -  

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

Contractor - June 2012 Contractor - June 2012 Independent Oversight Review, Sodium Bearing Waste Treatment Project - Contractor - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Contractor Operational Readiness Review This report documents the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), independent review of the Sodium Bearing Waste Treatment Project-Integrated Waste Treatment Unit (SBWTP-IWTU) contractor Operational Readiness Review (C-ORR). The review was conducted at the Idaho Site from February 27 to March 6, 2012. This report discusses the background, scope, results, and conclusions of the review, as well as opportunities for improvement (OFIs) and items identified for further

19

Independent Oversight Review, Sodium Bearing Waste Treatment Project -  

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

Federal - June 2012 Federal - June 2012 Independent Oversight Review, Sodium Bearing Waste Treatment Project - Federal - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Federal Operational Readiness Review This report documents the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), independent review of the Sodium Bearing Waste Treatment Project-Integrated Waste Treatment Unit (SBWTP-IWTU) DOE (Federal) Operational Readiness Review (D-ORR). The review was performed by the HSS Office of Safety and Emergency Management Evaluations and was intended to assess the effectiveness of the CORR process as implemented for the SBWTP-IWTU. This review also provides additional data regarding

20

Sodium-Bearing Waste Treatment, Applied Technology Plan  

SciTech Connect

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.

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

2003-06-01T23:59:59.000Z

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


21

Overview of Integrated Waste Treatment Unit  

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

Integrated Waste Treatment Unit Overview Integrated Waste Treatment Unit Overview Overview for the DOE High Level Waste Corporate Board March 5, 2009 safety  performance  cleanup  closure M E Environmental Management Environmental Management 2 2 Integrated Waste Treatment Unit Mission * Mission - Project mission is to provide treatment of approximately 900,000 gallons of tank farm waste - referred to as sodium bearing waste (SBW) - stored at the Idaho Tank Farm Facility to a stable waste form suitable for disposition at the Waste Isolation Pilot Plant (WIPP). - Per the Idaho Cleanup Project contract, the resident Integrated Waste Treatment Unit (IWTU) facility, shall have the capability for future packaging and shipping of the existing high level waste (HLW) calcine to the geologic

22

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

Office of Environmental Management (EM)

from INTEC closure activities stored in the Tank Farm, solids in the bottom of the tanks, and trace contamination from first cycle reprocessing extraction waste. SBW contains...

23

An evaluation of neutralization for processing sodium-bearing liquid waste  

SciTech Connect

This report addresses an alternative concept for potentially managing the sodium-bearing liquid waste generated at the Idaho Chemical Processing Plant from the current method of calcining a blend of sodium waste and high-level liquid waste. The concept is based on removing the radioactive components from sodium-bearing waste by neutralization and grouting the resulting low-level waste for on-site near-surface disposal. Solidifying the sodium waste as a remote-handled transuranic waste is not considered to be practical because of excessive costs and inability to dispose of the waste in a timely fashion. Although neutralization can remove most radioactive components to provide feed for a solidified low-level waste, and can reduce liquid inventories four to nine years more rapidly than the current practice of blending sodium-bearing liquid waste with first-cycle raffinite, the alternative will require major new facilities and will generate large volumes of low-level waste. Additional facility and operating costs are estimated to be at least $500 million above the current practice of blending and calcining. On-site, low-level waste disposal may be technically difficult and conflict which national and state policies. Therefore, it is recommended that the current practice of calcining a blend of sodium-bearing liquid waste and high-level liquid waste be continued to minimize overall cost and process complexities. 17 refs., 4 figs., 16 tabs.

Chipman, N.A.; Engelgau, G.O.; Berreth, J.R.

1989-01-01T23:59:59.000Z

24

Iron Phosphate Glasses for Vitrifying DOE High Priority Nuclear Wastes  

SciTech Connect

Iron phosphate glasses have been studied as an alternative glass for vitrifying Department of Energy (DOE) high priority wastes. The high priority wastes were the Low Activity Waste (LAW) and the High Level Waste (HLW) with high chrome content stored at Hanford, WA, and the Sodium Bearing Waste (SBW) stored at the Idaho National Engineering and Environmental Laboratory. These wastes were recommended by Tanks Focus Area since they were expected to require special attention when vitrified in borosilicate glasses. All three of these wastes have been successfully vitrified in iron phosphate glasses at waste loadings ranging from a low of 32 wt% for the high sulfate LAW to 40 wt% for the SBW to a high of 75 wt% for the high chrome HLW. In addition to these desirable high waste loadings, the iron phosphate glasses were easily melted, typically between 950 and 1200 C, in less than 4 hours in commercial refractory oxide containers. It is noteworthy that the chemical durability of both glassy and deliberately crystallized iron phosphate wasteforms not only met, but significantly exceeded, all current DOE chemical durability requirements as measured by the Product Consistency Test (PCT) and Vapor Hydration Test (VHT). The high waste loading, low melting temperature, rapid furnace throughput (short melting time) and their outstanding chemical durability could significantly accelerate the clean up effort and reduce the time and cost of vitrifying these high priority wastes.

Kim, C.W.; Day, D.E.

2004-03-29T23:59:59.000Z

25

Electron Microscopy Characterization of Tc-Bearing Metallic Waste Forms- Final Report FY10  

SciTech Connect

The DOE Fuel Cycle Research & Development (FCR&D) Program is developing aqueous and electrochemical approaches to the processing of used nuclear fuel that will generate technetium-bearing waste streams. This final report presents Pacific Northwest National Laboratory (PNNL) research in FY10 to evaluate an iron-based alloy waste form for Tc that provides high waste loading within waste form processing limitations, meets waste form performance requirements for durability and the long-term retention of radionuclides and can be produced with consistent physical, chemical, and radiological properties that meet regulatory acceptance requirements for disposal.

Buck, Edgar C.; Neiner, Doinita

2010-09-30T23:59:59.000Z

26

EIS-0287: Idaho High-Level Waste and Facilities Disposition Final  

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

Idaho High-Level Waste and Facilities Disposition Final Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) EIS-0287: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) 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 waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, DOE/EIS-0287 (September 2002)

27

EIS-0287: Idaho High-Level Waste & Facilities Disposition | Department of  

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

7: Idaho High-Level Waste & Facilities Disposition 7: Idaho High-Level Waste & Facilities Disposition EIS-0287: Idaho High-Level Waste & Facilities Disposition SUMMARY 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 waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD January 12, 2010 EIS-0287: Amended Record of Decision Idaho High-Level Waste and Facilities Disposition January 4, 2010

28

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

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

U.S. Department of Energy U.S. 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 the Department's Sodium Bearing Waste Treatment Facility Construction Project" BACKGROUND In 2005, the Department of Energy (Department) awarded the Idaho Cleanup Project contract to CH2M ♦ WG Idaho, LLC (CWI) to remediate the Idaho National Laboratory. The Sodium

29

Assessment of Nuclear Safety Culture at the Idaho Cleanup Project Sodium Bearing Waste Treatment Project, November 2012  

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

Idaho Cleanup Project Idaho Cleanup Project Sodium Bearing Waste Treatment Project May 2011 November 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Idaho Cleanup Project Sodium Bearing Waste Treatment Project Table of Contents 1.0 Introduction........................................................................................................................................... 1 2.0 Scope and Methodology ....................................................................................................................... 2

30

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

SciTech Connect

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.

Jantzen, C

2006-01-06T23:59:59.000Z

31

Worst-Case" Simulant for INTEC Soduim-Bearing Waste Vitrification Tests  

SciTech Connect

The Idaho Nuclear Technology and Engineering Center (INTEC) is developing technologies to process the radioactive liquid sodium-bearing waste from the waste tanks at INTEC to solidify the waste into a form suitable for disposition in a National high-level waste repository currently being considered at Yucca Mountain, Nevada. The requirement is for a qualified glass waste form. Therefore, vitrification is being developed using laboratory, research-scale, and pilot scale melters. While some laboratory experiments can be done with actual waste, the larger scale and most laboratory experiments must be done on non-radioactive simulant waste solutions. Some tests have previously been done on simulants of a representative waste that has been concentrated and will remain unchanged in tank WM-180 until it is vitrified. However, there is a need to develop glass compositions that will accommodate all future wastes in the tanks. Estimates of those future waste compositions have been used along with current compositions to develop a worst-case waste composition and a simulant preparation recipe suitable for developing a bracketing glass formulation and for characterizing the flowpath and decontamination factors of pertinent off-gas constituents in the vitrification process. The considerations include development of criteria for a worst-case composition. In developing the criteria, the species that are known to affect vitrification and glass properties were considered. Specific components that may need to be characterized in the off-gas cleanup system were considered in relation to detection limits that would need to be exceeded in order to track those components. Chemical aspects of various constituent interactions that should be taken into account when a component may need to be increased in concentration from that in the actual waste for detection in experiments were evaluated. The worst-case waste simulant composition is comprised of the highest concentration of each species of concern that will be present in current and future wastes from different tanks. Because most of the species of concern are at small concentrations relative to the bulk components that are fairly constant, maximizing them individually into a single waste composition does not substantially affect the general vitrification chemistry. The evaluation and results are reported here. This simulant is suitable for performing laboratory and pilot-scale tests in order to develop the vitrification technology.

Christian, Jerry Dale; Batcheller, Thomas Aquinas

2001-09-01T23:59:59.000Z

32

Phase 2 THOR Steam Reforming Tests for Sodium Bearing Waste Treatment  

SciTech Connect

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.

Nicholas R. Soelberg

2004-01-01T23:59:59.000Z

33

Fabrication and Properties of Technetium-Bearing Pyrochlores and Perovskites as Potential Waste Forms - 13222  

SciTech Connect

Technetium-99 (t{sub 1/2}= 2.13x10{sup 5} years) is important from a nuclear waste perspective and is one of the most abundant, long-lived radioisotopes in used nuclear fuel (UNF). As such, it is targeted in UNF separation strategies such as UREX+, for isolation and encapsulation in solid waste forms for storage in a nuclear repository. We report here results regarding the incorporation of Tc-99 into ternary oxides of different structure types: pyrochlore (Nd{sub 2}Tc{sub 2}O{sub 7}), perovskite (SrTcO{sub 3}), and layered perovskite (Sr{sub 2}TcO{sub 4}). The goal was to determine synthesis conditions of these potential waste forms to immobilize Tc-99 as tetravalent technetium and to harvest crystallographic, thermophysical and hydrodynamic data. The objective of this research is to provide fundamental crystallographic and thermophysical data on advanced ceramic Tc-99 waste forms such as pyrochlore, perovskite, and layered perovskite in support of our current efforts on the corrosion of technetium-bearing waste forms. The ceramic Tc-99-bearing waste forms exhibit good crystallinity. The lattice parameters and crystal structures of the technetium host phases could be refined with high accuracies of 3, 4, and 7 fm (10{sup -15} m), for Nd{sub 2}Tc{sub 2}O{sub 7}, SrTcO{sub 3}, and Sr{sub 2}TcO{sub 4}, respectively. The associated refinement residuals (R{sub Wp}) for the patterns are 4.1 %, 4.7 % and 6.7 %, and the refinement residuals for the individual phases (R{sub Bragg}) are 2.0 %, 2.4 % and 3.9 %, respectively. Thermophysical properties of the oxides SrTcO{sub 3}, Sr{sub 2}TcO{sub 4}, and Nd{sub 2}Tc{sub 2}O{sub 7} were analyzed using AC magnetic susceptibility measurements to further harvest information on the critical temperature (T{sub c}) for superconductivity. In our experiments the strontium technetates, SrTcO{sub 3} and Sr{sub 2}TcO{sub 4}, show superconductivity at rather high critical temperatures of T{sub c} = 7.8 K and 7 K, respectively. On the other hand Nd{sub 2}Tc{sub 2}O{sub 7} did not show any changes in magnetic properties above 3 K. (authors)

Hartmann, Thomas [University of Nevada - Las Vegas, Harry Reid Center, 4505 S. Maryland Parkway, Box 4009, Las Vegas, NV 89154-4009 (United States)] [University of Nevada - Las Vegas, Harry Reid Center, 4505 S. Maryland Parkway, Box 4009, Las Vegas, NV 89154-4009 (United States); Alaniz, Ariana J. [University of Nevada - Las Vegas, Howard R. Hughes College of Engineering, 4505 S. Maryland Parkway, Box 4009, Las Vegas, NV 89154-4009 (United States)] [University of Nevada - Las Vegas, Howard R. Hughes College of Engineering, 4505 S. Maryland Parkway, Box 4009, Las Vegas, NV 89154-4009 (United States); Antonio, Daniel J. [University of Nevada - Las Vegas, Department of Physics and Astronomy, 4505 S. Maryland Parkway, Box 4002, Las Vegas, NV 89154-4002 (United States)] [University of Nevada - Las Vegas, Department of Physics and Astronomy, 4505 S. Maryland Parkway, Box 4002, Las Vegas, NV 89154-4002 (United States)

2013-07-01T23:59:59.000Z

34

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

SciTech Connect

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.

Behrens, R.G. [Los Alamos National Lab., NM (United States); Buck, E.C.; Dietz, N.L.; Bates, J.K.; Van Deventer, E.; Chaiko, D.J. [Argonne National Lab., IL (United States)

1995-09-01T23:59:59.000Z

35

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

SciTech Connect

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.

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

2001-03-01T23:59:59.000Z

36

Cementitious waste option scoping study report  

SciTech Connect

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.

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

1998-02-01T23:59:59.000Z

37

Use of resin-bearing wastes from coke and coal chemicals production at the Novokuznetsk Metallurgical Combine  

SciTech Connect

The coke and coal chemicals plant at the Novokuznetsk Metallurgical Combine is making trial use of a technology that recycles waste products in 'tar ponds.' Specialists from the Ekomash company have installed a recycling unit in one area of the plant's dump, the unit including an inclined conveyor with a steam heater and a receiving hopper The coal preparation shop receives the wastes in a heated bin, where a screw mixes the wastes with pail of the charge for the coking ovens. The mixture subsequently travels along a moving conveyor belt together with the rest of the charge materials. The addition of up to 2% resin-bearing waste materials to the coal charge has not had any significant effect on the strength properties of the coke.

Kul'kova, T.N.; Yablochkin, N.V.; Gal'chenko, A.I.; Karyakina, E.A.; Litvinova, V.A.; Gorbach, D.A.

2007-03-15T23:59:59.000Z

38

Solid-state NMR characterisation of transition-metal bearing nuclear waste glasses.  

E-Print Network (OSTI)

??Alkali borosilicate glass is used to immobilise high-level radioactive waste generated from the reprocessing of spent nuclear fuel. However, poorly soluble waste products such as (more)

Greer, Brandon

2012-01-01T23:59:59.000Z

39

E-Print Network 3.0 - alpha-bearing wastes Sample Search Results  

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

Waste Management Program Approved December 7, 1998 Revised August 26, 2008 Next scheduled review: August... 26, 2011 Rule Statement A hazardous waste management program shall be...

40

Sintered Bentonite Ceramics for the Immobilization of Cesium- and Strontium-Bearing Radioactive Waste  

E-Print Network (OSTI)

minimizing the surface area of these waste forms to counter this issue. Hess found ?? damage to stoichiometric 137Cs doped pollucite structure slightly increased the volume from 0.5 - 1 % [8]. A study performed by Argonne and Pacific Northwest National Labs...

Ortega, Luis H.

2010-07-14T23:59:59.000Z

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


41

Accelerated weathering of high-level and plutonium-bearing lanthanide borosilicate waste glasses under hydraulically unsaturated conditions  

Science Journals Connector (OSTI)

The US Department of Energy (DOE) has proposed that a can-in-canister waste package design be used for disposal of excess weapons-grade Pu at the proposed mined geologic repository at Yucca Mountain, Nevada. This configuration consists of a high-level waste (HLW) canister fitted with a rack that holds mini-canisters containing a Pu-bearing lanthanide borosilicate (LaBS) waste glass and/or titanate-based ceramic (?15% of the total canister volume). The remaining volume of the HLW canister is then filled with HLW glass (?85% of the total canister volume). A 6-a pressurized unsaturated flow (PUF) test was conducted to investigate waste formwaste form interactions that may occur when water penetrates the canisters and contacts the waste forms. The PUF column volumetric water content was observed to increase steadily during the test because of water accumulation associated with alteration phases formed on the surfaces of the glasses. Periodic excursions in effluent pH, electrical conductivity, and solution chemistry were monitored and correlated with the formation of a clay phase(s) during the test. Geochemical modeling, with the EQ3NR code, of select effluent solution samples suggests the dominant secondary reaction product for the surrogate HLW glass, SRL-202, is a smectite di-octahedral clay phase(s), possibly nontronite [Na0.33 Fe2(AlSi)4O10(OH)2n(H2O)] or beidellite [Na0.33Al2.33Si3.67O10(OH)2]. This clay phase was identified in scanning electron microscope (SEM) images as discrete spherical particles growing out of a hydrated gel layer on reacted SRL-202 glass. Alpha energy analysis (AEA) of aliquots of select effluent samples that were filtered through a 1.8nm filter suggest that approximately 80% of the total measurable Pu was in the form of a filterable particulate, in comparison to unfiltered aliquots of the same sample. These results suggest the filterable particles are >1.8nm but smaller than the 0.2?m average diameter openings of the Ti porous plate situated at the base of the column. In this advection-dominated system, Pu appeared to be migrating principally as or in association with colloids after being released from the LaBS glass. Analyses of reacted LaBS glass particles with SEM with energy dispersive X-ray spectroscopy suggest that Pu may have segregated into a discrete disk-like phase, possibly PuO2. Alteration products that contain the neutron absorber Gd have not been positively identified. Separation of the Pu and the neutron absorber Gd during glass dissolution and transport could be a criticality issue for the proposed repository. However, the translation and interpretation of these long-term PUF test results to actual disposed waste packages requires further analysis.

Eric M. Pierce; B.P. McGrail; P.F. Martin; J. Marra; B.W. Arey; K.N. Geiszler

2007-01-01T23:59:59.000Z

42

Assessment of biotechnological strategies for the valorization of metal bearing wastes  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer We examine biological strategies to valorize different metal rich solid waste. Black-Right-Pointing-Pointer Bacteria play a key role in the mobilization of Zn and Y from fluorescent powders. Black-Right-Pointing-Pointer Ferrous iron is crucial for the bioleaching of Ni, V, Mo from spent catalysts. Black-Right-Pointing-Pointer No biological effect is observed for Ni, Zn, As, Cr mobilisation from sediments. - Abstract: The present work deals with the application of biotechnology for the mobilization of metals from different solid wastes: end of life industrial catalysts, heavy metal contaminated marine sediments and fluorescent powders coming from a cathode ray tube glass recycling process. Performed experiments were aimed at assessing the performance of acidophilic chemoautotrophic Fe/S-oxidizing bacteria for such different solid matrices, also focusing on the effect of solid concentration and of different substrata. The achieved results have evidenced that metal solubilization seems to be strongly influenced by the metal speciation and partitioning in the solid matrix. No biological effect was observed for Ni, Zn, As, Cr mobilization from marine sediments (34%, 44%, 15%, 10% yields, respectively) due to metal partitioning. On the other hand, for spent refinery catalysts (Ni, V, Mo extractions of 83%, 90% and 40%, respectively) and fluorescent powders (Zn and Y extraction of 55% and 70%, respectively), the improvement in metal extraction observed in the presence of a microbial activity confirms the key role of Fe/S oxidizing bacteria and ferrous iron. A negative effect of solid concentration was in general observed on bioleaching performances, due to the toxicity of dissolved metals and/or to the solid organic component.

Beolchini, Francesca, E-mail: f.beolchini@univpm.it [Department of Life and Environmental Sciences, Universita Politecnica delle Marche, via Brecce Bianche, 60131 Ancona (Italy); Fonti, Viviana; Dell'Anno, Antonio; Rocchetti, Laura [Department of Life and Environmental Sciences, Universita Politecnica delle Marche, via Brecce Bianche, 60131 Ancona (Italy); Veglio, Francesco [Department of Chemistry, Chemical Engineering and Materials, University of L'Aquila, Monteluco di Roio, 67040 L'Aquila (Italy)

2012-05-15T23:59:59.000Z

43

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

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 sodalites contained in the multiphase ceramic matrix are present as mixed-anion sodalite phases. These results suggest the multiphase FBSR NAS material may be a viable host matrix for long-lived, highly mobilie radionuclides which is a critical aspect in the management of nuclear waste.

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

2013-12-01T23:59:59.000Z

44

INTEC High-Level Waste Studies Universal Solvent Extraction Feasibility Study  

SciTech Connect

This report summarizes a feasibility study that has been conducted on the Universal Solvent Extraction (UNEX) Process for treatment and disposal of 4.3 million liters of INEEL sodium-bearing waste located at the Idaho Nuclear Technology and Engineering Center. This feasibility study covers two scenarios of treatment. The first, the UNEX Process, partitions the Cs/Sr from the SBW and creates remote-handled LLW and contact-handled TRU waste forms. Phase one of this study, covered in the 30% review documents, dealt with defining the processes and defining the major unit operations. The second phase of the project, contained in the 60% review, expanded on the application of the UNEX processes and included facility requirements and definitions. Two facility options were investigated for the UNEX process, resulting in a 2 x 2 matrix of process/facility scenarios as follows: Option A, UNEX at Greenfield Facility, Option B, Modified UNEX at Greenfield Facility, Option C, UNEX at NWCF, th is document, covers life-cycle costs for all options presented along with results and conclusions determined from the study.

J. Banaee; C. M. Barnes; T. Battisti (ANL-W) [ANL-W; S. Herrmann (ANL-W) [ANL-W; S. J. Losinski; S. McBride (ANL-W) [ANL-W

2000-09-01T23:59:59.000Z

45

Bearing system  

DOE Patents (OSTI)

A bearing system includes backup bearings for supporting a rotating shaft upon failure of primary bearings. In the preferred embodiment, the backup bearings are rolling element bearings having their rolling elements disposed out of contact with their associated respective inner races during normal functioning of the primary bearings. Displacement detection sensors are provided for detecting displacement of the shaft upon failure of the primary bearings. Upon detection of the failure of the primary bearings, the rolling elements and inner races of the backup bearings are brought into mutual contact by axial displacement of the shaft.

Kapich, Davorin D. (Carlsbad, CA)

1987-01-01T23:59:59.000Z

46

Apatite- and monazite-bearing glass-crystal composites for the immobilization of low-level nuclear and hazardous wastes  

SciTech Connect

This study demonstrates that glass-crystal composite waste forms can be produced from waste streams containing high proportions of phosphorus, transition metals, and/or halides. The crystalline phases produced in crucible-scale melts include apatite, monazite, spinels, and a Zr-Si-Fe-Ti phase. These phases readily incorporated radionuclide and toxic metals into their crystal structures, while corrosion tests have demonstrated that glass-crystal composites can be up to 300-fold more durable than simulated high-level nuclear waste glasses, such as SRL 202U.

Wronkiewicz, D.J.; Wolf, S.F.; DiSanto, T.S.

1995-12-31T23:59:59.000Z

47

DOE/EIS-0026-SA-03: Supplement Analysis for The Disposal of Certain Rocky Flats Plutonium-Bearing Materials at the Waste Isolation Pilot Plant (11/08/02)  

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

Supplement Analysis For Disposal of Certain Rocky Flats Supplement Analysis For Disposal of Certain Rocky Flats Plutonium-Bearing Materials at the Waste Isolation Pilot Plant PURPOSE The U.S. Department of Energy (DOE) is proposing to revise its approach for managing approximately 0.97 metric tons (MT) of plutonium-bearing materials (containing about 0.18 MT of surplus plutonium) located at the Rocky Flats Environmental Technology Site (RFETS). DOE is proposing to repackage and transport these materials for direct disposal at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Several DOE environmental impact statements (EISs) discuss the potential impacts from different proposed alternatives for the storage and disposition of surplus plutonium and waste containing surplus plutonium. These EISs evaluated and presented the potential impacts for

48

Early containment of high-alkaline solution simulating low-level radioactive waste stream in clay-bearing blended cement  

SciTech Connect

Portland cement blended with fly ash and attapulgite clay was mixed with high-alkaline solution simulating low-level radioactive waste stream at a one-to-one weight ratio. Mixtures were adiabatically and isothermally cured at various temperatures and analyzed for phase composition, total alkalinity, pore solution chemistry, and transport properties as measured by impedance spectroscopy. Total alkalinity is characterized by two main drops. The early one corresponds to a rapid removal of phosphorous, aluminum, sodium, and to a lesser extent potassium solution. The second drop from about 10 h to 3 days is mainly associated with the removal of aluminum, silicon, and sodium. Thereafter, the total alkalinity continues descending, but at a lower rate. All pastes display a rapid flow loss that is attributed to an early precipitation of hydrated products. Hemicarbonate appears as early as one hour after mixing and is probably followed by apatite precipitation. However, the former is unstable and decomposes at a rate that is inversely related to the curing temperature. At high temperatures, zeolite appears at about 10 h after mixing. At 30 days, the stabilized crystalline composition Includes zeolite, apatite and other minor amounts of CaCO{sub 3}, quartz, and monosulfate Impedance spectra conform with the chemical and mineralogical data. The normalized conductivity of the pastes shows an early drop, which is followed by a main decrease from about 12 h to three days. At three days, the permeability of the cement-based waste as calculated by Katz-Thompson equation is over three orders of magnitude lower than that of ordinary portland cement paste. However, a further decrease in the calculated permeability is questionable. Chemical stabilization is favorable through incorporation of waste species into apatite and zeolite.

Kruger, A.A. [Westinghouse Hanford Co., Richland, WA (United States); Olson, R.A.; Tennis, P.D. [Northwestern Univ., Evanston, IL (United States). Center for Advanced Cement-Based Materials] [and others

1995-04-01T23:59:59.000Z

49

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

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.

NONE

1996-09-01T23:59:59.000Z

50

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

SciTech Connect

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.

NONE

1995-02-01T23:59:59.000Z

51

Independent Oversight Assessment, Idaho Cleanup Project Sodium Bearing  

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

Idaho Cleanup Project Sodium Idaho Cleanup Project Sodium Bearing Waste Treatment Project - November 2012 Independent Oversight Assessment, Idaho Cleanup Project Sodium Bearing Waste Treatment Project - November 2012 November 2012 Assessment of Nuclear Safety Culture at the Idaho Cleanup Project Sodium Bearing Waste Treatment Project The U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted an independent assessment of nuclear safety culture at the DOE Sodium Bearing Waste Treatment Project (SBWTP). The primary objective of the evaluation was to provide information regarding the status of the safety culture at SBWTP. The data collection phase of the assessment occurred in April and May 2012. SBWTP is one of DOE's largest nuclear

52

Accelerated Weathering of High-Level and Plutonium-bearing Lanthanide...  

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

This configuration consists of a high-level waste (HLW) canister fitted with a rack that holds mini-canisters containing a Pu-bearing lanthanide borosilicate (LaBS) waste...

53

Molecular dynamics simulation and topological analysis of the network structure of actinide-bearing materials  

E-Print Network (OSTI)

Actinide waste production and storage is a complex problem, and a whole-cycle approach to actinide management is necessary to minimize the total volume of waste. In this dissertation, I examine three actinide-bearing ...

Dewan, Leslie

2013-01-01T23:59:59.000Z

54

Bear Creek Valley Watershed  

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

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

55

DRAFT Bear Safety Plan  

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

Bear Safety Plan June 2010 Bear Safety Plan June 2010 NSA_bsp_Rev9.doc 1 Atmospheric Radiation Measurement Climate Research Facility/ North Slope of Alaska/Adjacent Arctic Ocean (ACRF/NSA/AAO) Bear Safety Plan Background As a major part of DOE's participation in the US Global Change Research Program (USGCRP), the North Slope of Alaska (NSA) and Adjacent Arctic Ocean (AAO) Climate Research Facility (ACRF) exists on the North Slope of Alaska with its Central Facility near the town of Barrow. A secondary facility exists at Atqasuk, a town 100km inland from Barrow. Other instrumentation locations in more remote areas on the North Slope may be established in later stages of the project. Polar bears, and to a lesser extent, brown bears (barren ground grizzly) are significant hazards within the ACRF/NSA/AAO

56

DOE/EIS-0287 Idaho High-Level Waste & Facilities Disposition Draft Environmental Impact Statement (December 1999)  

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

HLW & FD EIS HLW & FD EIS 3-13 DOE/EIS-0287D Calcine storag e i n b i n s ets Calcine storag e i n b i n s et s Cesium ion exchange & grouting Cesium ion exchange & grouting NWCF* NWCF* Calcine Mixed transuranic waste/SBW Mixed transuranic waste/NGLW Low-level waste disposa l*** disposa l*** Tank heels Transuranic waste (from tank heels) * * * * Mixed transuranic waste/ NGLW Mixed transuranic waste/ NGLW M i x e d t r a nsuran ic w a s t e / M i x e d t r a nsuran ic w a s t e / S B W s t o rage in Ta n k F a r m S B W s t o rage in Ta n k F a r m Low-leve l waste Low-leve l waste FIGURE 3-2. Continued Current Operations Alternative. LEGEND * Including high-temperature and maximum achievable control technology upgrades. Mixed transuranic waste/ newly generated liquid waste New Waste Calcining Facility ** Calcine would be transferred from bin set #1 to bin set #6 or #7.

57

Ecological effects of contaminants and remedial actions in Bear Creek  

SciTech Connect

Ecological studies of the Bear Creek watershed, which drains the area surrounding several Oak Ridge Y-12 Plant waste disposal facilities, were initiated in May 1984 and are continuing at present. These studies consisted of an initial, detailed characterization of the benthic invertebrate and fish communities in Bear Creek, and they were followed by a presently ongoing monitoring phase that involves reduced sampling intensities. The characterization phase utilized two approaches: (1) instream sampling of benthic invertebrate and fish communities in Bear Creek to identify spatial and temporal patterns in distribution and abundance and (2) laboratory bioassays on water samples from Bear Creek and selected tributaries to identify potential sources of toxicity to biota. The monitoring phase of the ecological program relates to the long-term goals of identifying and prioritizing contaminant sources and assessing the effectiveness of remedial actions. It continues activities of the characterization phase at less frequent intervals. The Bear Greek Valley is a watershed that drains the area surrounding several closed Oak Ridge Y-12 Plant waste disposal facilities. Past waste disposal practices in Bear Creek Valley resulted in contamination of Bear Creek and consequent ecological damage. Extensive remedial actions have been proposed at waste sites, and some of the have been implemented or are now underway. The proposed study plan consists of an initial, detailed characterization of the benthic invertebrate and fish communities in Bear Creek in the first year followed by a reduction in sampling intensity during the monitoring phase of the plan. The results of sampling conducted from May 1984 through early 1989 are presented in this report.

Southworth, G.R.; Loar, J.M.; Ryon, M.G.; Smith, J.G.; Stewart, A.J. [Oak Ridge National Lab., TN (United States); Burris, J.A. [C. E. Environmental, Inc., Tallahassee, FL (United States)

1992-01-01T23:59:59.000Z

58

The Black Bear  

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

Black Bear Black Bear Nature Bulletin No. 286-A December 9, 1967 Forest Preserve District of Cook County Richard B. Ogilvie, President Roland F. Eisenbeis, Supt. of Conservation THE BLACK BEAR The most amusing and human-like of all our American wild animals is the Black Bear. Slow, clumsy and loose-jointed in appearance, with a shambling gait, he can be very swift and nimble. Like any good clown he is also a good acrobat with a fine sense of balance and timing. He is a great climber in spite of his bulk. Shrewd and droll, he is very popular in menageries and as a performer in circuses and side shows because he learns tricks easily. He can stand on his hind legs to wrestle, box, dance, or beg for food and, occasionally, one becomes a graceful artist on roller skates. They love applause.

59

Woolly Bear Caterpillar  

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

Woolly Bear Caterpillar Woolly Bear Caterpillar Name: Colton Location: N/A Country: N/A Date: N/A Question: We live in N.J. and found a Woolly Bear Caterpillar that was all black. We would like to keep it but are worried that it may "NEED" to hibernate to live. Also: We love to collect bugs (live) and learn about them, but most of the books don't have all the information we need ie. what does it eat, how long does it live, identifying caterpillar stages of insects. Could you please reccomend a good book, that has pictures of all life stages and information that would be of interest to children? Thank you for your time. Replies: Good books on caterpillars are hard to find. Try the Peterson Guide to Butterflies, Audubon Guide to Butterflies, etc. You will probably just have to browse in libraries and see what you can find. Good luck. By the way, the more black on the wooly bear, so the legend goes, the harder the winter will be. One was recently seen around here (NE Illinois) that was almost, but not quite, all black.

60

Radioactive Waste Radioactive Waste  

E-Print Network (OSTI)

#12;Radioactive Waste at UF Bldg 831 392-8400 #12;Radioactive Waste · Program is designed to;Radioactive Waste · Program requires · Generator support · Proper segregation · Packaging · labeling #12;Radioactive Waste · What is radioactive waste? · Anything that · Contains · or is contaminated

Slatton, Clint

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


61

Passive magnetic bearing system  

DOE Patents (OSTI)

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.

Post, Richard F.

2014-09-02T23:59:59.000Z

62

Centrifugally decoupling touchdown bearings  

DOE Patents (OSTI)

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.

Post, Richard F

2014-06-24T23:59:59.000Z

63

Bearing Analytics | Department of Energy  

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

Bearing Analytics Bearing Analytics National Clean Energy Business Plan Competition 2013 355 likes Bearing Analytics Purdue University Avoidable bearing failures cost the US industrial economy $50B in damage and downtime every year. Current bearing health monitoring systems do not adequately detect failure until it is too late. Bearing Analytics offers a patent-pending micro-sensor technology that monitors temperature and vibration directly on the bearing cage helping predict performance degradation and impending failure while improving operating, performance, and energy efficiencies. Our technology does all of that with a better accuracy, faster response time, and increased reliability over any other competing solution today. We intend to target the wind turbine industry as our initial target point

64

Bearing Analytics | Department of Energy  

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

Bearing Analytics Bearing Analytics National Clean Energy Business Plan Competition 2013 355 likes Bearing Analytics Purdue University Avoidable bearing failures cost the US industrial economy $50B in damage and downtime every year. Current bearing health monitoring systems do not adequately detect failure until it is too late. Bearing Analytics offers a patent-pending micro-sensor technology that monitors temperature and vibration directly on the bearing cage helping predict performance degradation and impending failure while improving operating, performance, and energy efficiencies. Our technology does all of that with a better accuracy, faster response time, and increased reliability over any other competing solution today. We intend to target the wind turbine industry as our initial target point

65

Bearing Analytics | Department of Energy  

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

Bearing Analytics Bearing Analytics National Clean Energy Business Plan Competition 2013 355 likes Bearing Analytics Purdue University Avoidable bearing failures cost the US industrial economy $50B in damage and downtime every year. Current bearing health monitoring systems do not adequately detect failure until it is too late. Bearing Analytics offers a patent-pending micro-sensor technology that monitors temperature and vibration directly on the bearing cage helping predict performance degradation and impending failure while improving operating, performance, and energy efficiencies. Our technology does all of that with a better accuracy, faster response time, and increased reliability over any other competing solution today. We intend to target the wind turbine industry as our initial target point

66

Spacesuits optional for 'water bears'  

Science Journals Connector (OSTI)

... a lichen, or maybe a photosynthesizing bacteria." STEVE GSCHMEISSNER / SCIENCE PHOTO LIBRARY The humble water bear has gone where no animal has gone before. STEVE GSCHMEISSNER / SCIENCE ...

Heidi Ledford

2008-09-08T23:59:59.000Z

67

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

EM Makes Significant Progress on Dispositioning Transuranic Waste EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 - 12:00pm Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. Distillation equipment is shown prior to transport to the Idaho site. Distillation equipment is shown prior to transport to the Idaho site. In these 2010 photographs, unexploded ordnance were collected and then detonated onsite at the Mass Detonation Area.

68

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

EM Makes Significant Progress on Dispositioning Transuranic Waste EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 - 12:00pm Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. Distillation equipment is shown prior to transport to the Idaho site. Distillation equipment is shown prior to transport to the Idaho site. In these 2010 photographs, unexploded ordnance were collected and then detonated onsite at the Mass Detonation Area.

69

Mixed-mu superconducting bearings  

DOE Patents (OSTI)

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.

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

1998-03-03T23:59:59.000Z

70

Baseline Change Request  

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

performance cleanup closure performance cleanup closure M E Environmental Management Environmental Management Sodium Bearing Waste Treatment Project Overview U. S. Department of Energy Office of Waste Processing Technical Exchange Denver, Colorado May 20, 2009 Keith Lockie, Deputy Federal Project Director 2 safety performance cleanup closure M E Environmental Management Environmental Management 2 Project Mission/Contract * Mission - The Sodium Bearing Waste Treatment Project (also known as the Integrated Waste Treatment Project) mission is to provide treatment of approximately 900,000 gallons of tank farm waste - referred to as sodium bearing waste (SBW) - stored at the Idaho Tank Farm Facility to a stable waste form suitable for disposition at the Waste Isolation Pilot Plant -

71

AMCRM.PPT  

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

IWTU Project IWTU Project Risk Management Overview Presented at U.S. Department of Energy Risk Management Meeting November 4-6, 2009 Bob Williamson IWTU Risk Manager 2 IWTU (Sodium-Bearing Waste) Project Picture of IWTU Part of the Idaho Cleanup Project (ICP) contract - Contract period May 2005 - September 2012 - Scope reflects EM cleanup mission at the INL - Total Cost ~ $2.9 B ICP contract Sodium Bearing Waste Scope - Provide treatment of approximately 900,000 gallons of Sodium Bearing Waste (SBW) stored at the Idaho Tank Farm Facility to a stable waste form suitable for disposition at the Waste Isolation Pilot Plant (WIPP). Line Item Project 06-D-401 designs, constructs, and commissions a new treatment facility - Total Project Cost - $570.9 M 3 IWTU (Sodium-Bearing Waste) Project Objectives

72

Hydrostatic bearings for a turbine fluid flow metering device  

DOE Patents (OSTI)

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.

Fincke, J.R.

1982-05-04T23:59:59.000Z

73

Superconductor bearings, flywheels and transportation  

Science Journals Connector (OSTI)

This paper describes the present status of high temperature superconductors (HTS) and of bulk superconducting magnet devices, their use in bearings, in flywheel energy storage systems (FESS) and linear transport magnetic levitation (Maglev) systems. We report and review the concepts of multi-seeded REBCO bulk superconductor fabrication. The multi-grain bulks increase the averaged trapped magnetic flux density up to 40% compared to single-grain assembly in large-scale applications. HTS magnetic bearings with permanent magnet (PM) excitation were studied and scaled up to maximum forces of 10kN axially and 4.5kN radially. We examine the technology of the high-gradient magnetic bearing concept and verify it experimentally. A large HTS bearing is tested for stabilizing a 600kg rotor of a 5kWh/250kW flywheel system. The flywheel rotor tests show the requirement for additional damping. Our compact flywheel system is compared with similar HTSFESS projects. A small-scale compact YBCO bearing with insitu Stirling cryocooler is constructed and investigated for mobile applications. Next we show a successfully developed modular linear Maglev system for magnetic train operation. Each module levitates 0.25t at 10mm distance during one-day operation without refilling LN2. More than 30 vacuum cryostats containing multi-seeded YBCO blocks are fabricated and are tested now in Germany, China and Brazil.

F N Werfel; U Floegel-Delor; R Rothfeld; T Riedel; B Goebel; D Wippich; P Schirrmeister

2012-01-01T23:59:59.000Z

74

Low Temperature Waste Immobilization Testing Vol. I  

SciTech Connect

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.

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

2006-09-14T23:59:59.000Z

75

Experiences with treatment of mixed waste  

SciTech Connect

During its many years of research activities involving toxic chemicals and radioactive materials, Los Alamos National Laboratory (Los Alamos) has generated considerable amounts of waste. Much of this waste includes chemically hazardous components and radioisotopes. Los Alamos chose to use an electrochemical process for the treatment of many mixed waste components. The electro-chemical process, which the authors are developing, can treat a great variety of waste using one type of equipment built at a moderate expense. Such a process can extract heavy metals, destroy cyanides, dissolve contamination from surfaces, oxidize toxic organic compounds, separate salts into acids and bases, and reduce the nitrates. All this can be accomplished using the equipment and one crew of trained operating personnel. Results of a treatability study of chosen mixed wastes from Los Alamos Mixed Waste Inventory are presented. Using electrochemical methods cyanide and heavy metals bearing wastes were treated to below disposal limits.

Dziewinski, J.; Marczak, S.; Smith, W.H. [Los Alamos National Lab., NM (United States); Nuttall, E. [Univ. of New Mexico, Albuquerque, NM (United States). Chemical and Nuclear Engineering Dept.

1996-04-10T23:59:59.000Z

76

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...4). Although disposal of HLW remains...for long-term disposal is through deep...successful waste-disposal program has eluded...geologic repository at Yucca Mountain, Nevada. Authorized...Administration withdrew funding for Yucca Mountain...

Eugene A. Rosa; Seth P. Tuler; Baruch Fischhoff; Thomas Webler; Sharon M. Friedman; Richard E. Sclove; Kristin Shrader-Frechette; Mary R. English; Roger E. Kasperson; Robert L. Goble; Thomas M. Leschine; William Freudenburg; Caron Chess; Charles Perrow; Kai Erikson; James F. Short

2010-08-13T23:59:59.000Z

77

Partial List of Laws, Regulations and Guidelines Bearing on the Operation of Biological Research Labs  

E-Print Network (OSTI)

Partial List of Laws, Regulations and Guidelines Bearing on the Operation of Biological Research Chemicals in the Laboratory 40 CFR 260 - 262; RCRA ­ Hazardous Waste Management, Lists and Generator Rule Select Agent Regulations, 49 CFR 171-180-Transportation Additional CFR's not indicated above 21

Oliver, Douglas L.

78

Technology advances for magnetic bearings  

Science Journals Connector (OSTI)

This paper describes the state?of?the?art in magnetic bearing technology and applications and some of advances under development through the joint efforts of Rocketdyne Division of Rockwell International and Auburn University. Advances in the areas of nonlinear control systems design digital controller implementation and power electronics are discussed.

Steve Nolan; John Y. Hung

1996-01-01T23:59:59.000Z

79

Recovery of phosphates from elemental phosphorus bearing wastes  

SciTech Connect

A process for oxidizing aqueous elemental phosphorus containing residues (sludges) to produce orthophosphate containing slurries suitable for subsequent reaction with ammonia to produce nitrogen and phosphate containing fertilizer products is presented. It comprises reacting aqueous elemental phosphorus containing residues with certain special mixtures of concentrated nitric acid and sulfuric acid to effect the conversion of the elemental phosphorus into mostly orthophosphoric acid and very little orthophosphorus acid with the relative ratios of the two acids being dependent upon the mole ratio of H{sub 2}SO{sub 4}:HNO{sub 3} employed in the processing. The resulting aqueous reaction intermediate is neutralized with ammonia during processing to a fluid or solid fertilizer product. Prior to the conversion to products, the aqueous reaction intermediate may be subjected to a solids separation step to remove insoluble salts of certain environmentally undesirable metals, such as Pb, Cd, Ba, and Cr.

Edwards, R.E.; Moore, O.E.; Sullivan, J.M.

1994-10-01T23:59:59.000Z

80

Design of a low cost hydrostatic bearing  

E-Print Network (OSTI)

This thesis presents the design and manufacturing method for a new surface self compensating hydrostatic bearing. A lumped resistance model was used to analyze the performance of the bearing and provide guidance on laying ...

Wong, Anthony Raymond

2012-01-01T23:59:59.000Z

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


81

Low-level waste forum meeting reports  

SciTech Connect

This paper provides highlights from the spring meeting of the Low Level Radioactive Waste Forum. Topics of discussion included: state and compact reports; New York`s challenge to the constitutionality of the Low-Level Radioactive Waste Amendments Act of 1985; DOE technical assistance for 1993; interregional import/export agreements; Department of Transportation requirements; superfund liability; nonfuel bearing components; NRC residual radioactivity criteria.

NONE

1992-12-31T23:59:59.000Z

82

THOR Bench-Scale Steam Reforming Demonstration  

SciTech Connect

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.

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

2003-05-21T23:59:59.000Z

83

THOR Bench-Scale Steam Reforming Demonstration  

SciTech Connect

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.

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

2003-05-01T23:59:59.000Z

84

SMOKEY THE BEAR SUTRA Gary Snyder  

E-Print Network (OSTI)

is threatened by advertising, air pollution, televi­ sion, or the police, they should chant SMOKEY THE BEAR

Alexander, Roger K.

85

THE UNIVERSITY OF EDINBURGH. Hudson Beare Building.  

E-Print Network (OSTI)

. Accessible and standard toilets are also available. Introduction. The Hudson Beare Building housesTHE UNIVERSITY OF EDINBURGH. Hudson Beare Building. (King's Buildings). A GUIDE TO ACCESS AND FACILITIES. Address: Hudson Beare Building, King's Buildings, Edinburgh, E,H,9 3,J,F. Telephone number: 0131

Edinburgh, University of

86

Acceptability of Bettis Laboratories waste shipment to WHC solid waste  

SciTech Connect

The purpose of this document is to evaluate a potential discrepancy between the Solid Waste Management (SWM) Criticality Prevention Specifications and a proposed waste receipt from Bettis Laboratories. This analysis resolves an apparent discrepancy between two different requirements of the Central Waste Complex and 200 Area Low-Level Burial Grounds Criticality Prevention Specifications (CPS-SW-149-00002 and CPS-SW-149-00003 respectively). The analysis is being performed to enable Solid Waste Management to accept a specific package from Bettis Laboratories. This package meets the requirements of section 2.1.1 in that the total fissile content of the drum is less than 200g and the waste occupies greater than 20% of the container volume. The package may not appear, however, to meet the requirements of section 2.1.5 for maximum enrichment of uranium bearing waste, as will be described below. Based on this analysis for this specific package, the waste is shown to be critically safe under all conditions for which the 55-gallon drums (17C, 17H, or UN1A2) specification applies. This package can be accepted under the 55-gallon drum limitations on fissile quantity. No change to the CPS is required.

McDonald, K.M.

1995-04-20T23:59:59.000Z

87

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...

88

Negotiating equity for management of DOE wastes  

SciTech Connect

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.

Carnes, S.A.

1994-09-01T23:59:59.000Z

89

The BEAR Beamline at Elettra  

SciTech Connect

The BEAR (Bending Magnet for Emission Absorption and Reflectivity) beamline is installed at the right exit of the 8.1 bending magnet at ELETTRA. The beamline - in operation since January 2003 - delivers linear and circularly polarized radiation in the 5 - 1600 eV energy range. The experimental station is composed of a UHV chamber for reflectivity, absorption, fluorescence and angle resolved photoemission measurements and a UHV chamber for in-situ sample preparation.

Nannarone, S.; Pasquali, L.; Selvaggi, G. [UdR-INFM Modena, Universita di Modena and Reggio Emilia, Via Vignolese 905, 41100 Modena (Italy); Borgatti, F.; DeLuisa, A.; Doyle, B.P.; Gazzadi, G.C.; Giglia, A.; Finetti, P.; Pedio, M. [TASC-INFM, MM building in Area Science Park, s.s.14 km 163.5, 34012 Basovizza, Trieste (Italy); Mahne, N. [TASC-INFM, Universita di Trieste, Trieste (Italy); Naletto, G.; Pelizzo, M.G.; Tondello, G. [LUXOR-INFM, Universita di Padova, Padua (Italy)

2004-05-12T23:59:59.000Z

90

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...06520, USA. Nuclear power is re-emerging...proclaiming a nuclear renaissance...example, plant safety...liabilities, terrorism at plants and in transport...high-level nuclear wastes (HLW...factor in risk perceptions...supporting nuclear power in the abstract...

Eugene A. Rosa; Seth P. Tuler; Baruch Fischhoff; Thomas Webler; Sharon M. Friedman; Richard E. Sclove; Kristin Shrader-Frechette; Mary R. English; Roger E. Kasperson; Robert L. Goble; Thomas M. Leschine; William Freudenburg; Caron Chess; Charles Perrow; Kai Erikson; James F. Short

2010-08-13T23:59:59.000Z

91

Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste  

E-Print Network (OSTI)

waste (i.e, mixture of biohazardous and chemical or radioactive waste), call Environment, Health2/2009 Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste Description Biohazard symbol Address: UCSD 200 West Arbor Dr. San Diego, CA 92103 (619

Tsien, Roger Y.

92

Analytical and experimental investigations of hybrid air foil bearings  

E-Print Network (OSTI)

Air foil bearings offer several advantages over oil-lubricated bearings in high speed micro-turbomachinery. With no contact between the rotor and bearings, the air foil bearings have higher service life and consequently lesser standstills between...

Kumar, Manish

2009-05-15T23:59:59.000Z

93

Production of iron from metallurgical waste  

DOE Patents (OSTI)

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.

Hendrickson, David W; Iwasaki, Iwao

2013-09-17T23:59:59.000Z

94

Hydrostatic bearings for a turbine fluid flow metering device  

DOE Patents (OSTI)

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.

Fincke, J.R.

1980-05-02T23:59:59.000Z

95

Turbocharger bearing retention and lubrication system  

SciTech Connect

This patent describes exhausts gas driven turbocharger. It comprises a housing, a shaft within the housing having a longitudinal axis of rotation and a pair of ends, a compressor wheel mounted within the housing on one end of the shaft for rotation therewith, a turbine wheel mounted within the housing on the other end of the shaft for rotation therewith, means for communicating air to the compressor wheel, means for communicating exhaust gas to the turbine wheel to cause the latter to rotate the shaft and the compressor wheel mounted thereon to compress the air communicated to the compressor wheel, and bearing means mounting the shaft for rotation relative to the housing, the bearing means including a bearing outer ring, a bearing inner ring, and ball bearing elements supporting the bearing outer ring on the bearing inner ring, a bearing locating aperture in the bearing outer ring, and an elongated bearing location pin having a longitudinal axis of symmetry extending transversely to the longitudinal axis of the shaft.

Gutknecht, D.A.

1991-12-31T23:59:59.000Z

96

Static forces in a superconducting magnet bearing  

SciTech Connect

Static levitation forces and stiffnesses in a superconducting bearing consisting of concentric ring magnets and a superconducting YBaCuO ring are investigated. In the field-cooled mode a levitation force of 20 N has been achieved. The axial and radial stiffnesses have values of 15 N/mm and 10 N/mm, respectively. An arrangement with two bearings supporting a high speed shaft is now under development. A possible application of superconducting magnetic bearings is flywheels for energy storage.

Stoye, P.; Fuchs, G. [Institut fuer Festkoerper- und Werkstofforschung, Dresden (Germany)] [Institut fuer Festkoerper- und Werkstofforschung, Dresden (Germany); Gawalek, W.; Goernert, P. [Institut fuer Physikalische Hochtechnologie, Jena (Germany)] [Institut fuer Physikalische Hochtechnologie, Jena (Germany); Gladun, A. [Technische Univ., Dresden (Germany)] [Technische Univ., Dresden (Germany)

1995-11-01T23:59:59.000Z

97

Synthesis and characterization of silicon phthalocyanines bearing...  

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

Synthesis and characterization of silicon phthalocyanines bearing axial phenoxyl groups for attachment to semiconducting metal oxides Authors: Bergkamp, J. J., Sherman, B. D.,...

98

Glass Development for Treatment of LANL Evaporator Bottoms Waste  

SciTech Connect

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).

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

1998-11-20T23:59:59.000Z

99

Precision instrumentation for rolling element bearing characterization  

SciTech Connect

This article describes an instrument to measure the error motion of rolling element bearings. This challenge is met by simultaneously satisfying four requirements. First, an axial preload must be applied to seat the rolling elements in the bearing races. Second, one of the races must spin under the influence of an applied torque. Third, rotation of the remaining race must be prevented in a way that leaves the radial, axial/face, and tilt displacements free to move. Finally, the bearing must be fixtured and measured without introducing off-axis loading or other distorting influences. In the design presented here, an air bearing reference spindle with error motion of less than 10 nm rotates the inner race of the bearing under test. Noninfluencing couplings are used to prevent rotation of the bearing outer race and apply an axial preload without distorting the bearing or influencing the measurement. Capacitive displacement sensors with 2 nm resolution target the nonrotating outer race. The error motion measurement repeatability is shown to be less than 25 nm. The article closes with a discussion of how the instrument may be used to gather data with sufficient resolution to accurately estimate the contact angle of deep groove ball bearings.

Marsh, Eric R.; Vigliano, Vincent C.; Weiss, Jeffrey R.; Moerlein, Alex W.; Vallance, R. Ryan [Machine Dynamics Research Laboratory, Pennsylvania State University, 331 Reber Building University Park, Pennsylvania 16802 (United States); Precision Systems Laboratory, George Washington University, 738 Phillips Hall 801 22nd Street, N.W. Washington, D.C., 20052 (United States)

2007-03-15T23:59:59.000Z

100

Self-adjusting magnetic bearing systems  

DOE Patents (OSTI)

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.

Post, Richard F. (Walnut Creek, CA)

1998-01-01T23:59:59.000Z

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


101

Marine bearing for a downhole drilling apparatus  

SciTech Connect

A bearing supports a rotatable shaft in a fluid environment. The bearing can be utilized to support a drive shaft connected to a drill bit in a downhole drilling apparatus. The drive shaft extends through a housing in which drilling fluid is flowing. Preferably, the bearing includes an inner elastomeric sleeve and an outer rigid sleeve attached to the interior side wall of the housing. The drive shaft has a wear sleeve attached for rotation therewith. The wear sleeve is rotatably received in the bearing inner sleeve. The inner sleeve is relatively short as compared with the drive shaft and absorbs radial loads imposed on the drive shaft. The bearing is lubricated by a portion of the drilling fluid in the housing which flows between the exterior side wall of the wear sleeve and the interior side wall of the inner sleeve.

Beimgraben, H.W.

1984-07-31T23:59:59.000Z

102

Turbocharger with improved roller bearing shaft support  

SciTech Connect

This paper describes an exhaust gas driven turbocharger. It comprises: a housing, a shaft within the housing having a pair of ends, a compressor wheel mounted within the housing on one end of the shaft for rotation therewith, a turbine wheel mounted within the housing on the other end of the shaft for rotation therewith, means for communicating air through the compressor wheel, means for communicating exhaust gas through the turbine wheel to cause the latter to rotate the shaft and the compressor wheel mounted thereon to compress the air communicated through the compressor wheel, and bearing means mounting the shaft for rotation relative to the housing, the bearing means including a bearing outer ring, a bearing inner ring, and ball bearing elements supporting the bearing outer ring on the bearing inner ring, the ball bearing elements includes a first set of the elements and a second set of the elements spaced axially from the first set, the bearing outer ring being a rigid, uninterrupted member providing an uninterrupted structural link between the first and second sets to establish the axial spacing between the sets, a pair of axially spaced faying surfaces on the inner ring engaging corresponding faying surfaces on the shaft to support the inner ring on the shaft, the shaft defining a circumferentially extending surface between the faying surfaces on the inner ring cooperating with the shaft to define an air gap therebetween, one of the faying surfaces on the inner ring having a diameter greater than the diameter of the other of the faying surfaces on the inner ring.

Gutknecht, D.A.

1991-10-08T23:59:59.000Z

103

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

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

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 ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 2 4.0 Results ................................................................................................................................................... 2

104

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

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

105

Compressor ported shroud for foil bearing cooling  

SciTech Connect

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.

Elpern, David G. (Los Angeles, CA); McCabe, Niall (Torrance, CA); Gee, Mark (South Pasadena, CA)

2011-08-02T23:59:59.000Z

106

Notes 04. Static load performance of plain journal bearings  

E-Print Network (OSTI)

The long and short bearing models. Pressure field and fluid film forces on short length journal bearings. Equilibrium condition, load capacity and the Sommerfeld number....

San Andres, Luis

2010-01-01T23:59:59.000Z

107

Bearing Analytics | Department of Energy  

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

Pyro-E Pyro-E University of California-Berkeley 190 likes Pyro-E, LLC is developing a solid-state device for waste heat harvesting at the distributed energy scale. The device is designed based on the pyroelectric effect and can be used to improve the fuel-use efficiency of 300 million vehicles and generators in the United States. Learn More SiNode Systems Northwestern University 31 likes SiNode Systems is a battery materials venture developing silicon-graphene anodes for the next generation of lithium-ion batteries. SiNode anodes offer higher battery capacity and faster charging rates, all while being produced via a low cost solution chemistry-based manufacturing process. Learn More Picasolar University of Arkansas 16 likes Picasolar wholly owns the hydrogen selective emitter (HSE) technology. HSE

108

Bearing Analytics | Department of Energy  

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

Picasolar Picasolar University of Arkansas 16 likes Picasolar wholly owns the hydrogen selective emitter (HSE) technology. HSE can increase the efficiency of solar cells by up to 15 percent and remove up to 33 percent of the silver grid lines in a conventional silicon solar cell. Learn More SiNode Systems Northwestern University 31 likes SiNode Systems is a battery materials venture developing silicon-graphene anodes for the next generation of lithium-ion batteries. SiNode anodes offer higher battery capacity and faster charging rates, all while being produced via a low cost solution chemistry-based manufacturing process. Learn More Pyro-E University of California-Berkeley 190 likes Pyro-E, LLC is developing a solid-state device for waste heat harvesting at the distributed energy scale. The device is designed based on the

109

Bearing Analytics | Department of Energy  

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

Picasolar Picasolar University of Arkansas 16 likes Picasolar wholly owns the hydrogen selective emitter (HSE) technology. HSE can increase the efficiency of solar cells by up to 15 percent and remove up to 33 percent of the silver grid lines in a conventional silicon solar cell. Learn More Pyro-E University of California-Berkeley 190 likes Pyro-E, LLC is developing a solid-state device for waste heat harvesting at the distributed energy scale. The device is designed based on the pyroelectric effect and can be used to improve the fuel-use efficiency of 300 million vehicles and generators in the United States. Learn More SiNode Systems Northwestern University 31 likes SiNode Systems is a battery materials venture developing silicon-graphene anodes for the next generation of lithium-ion batteries. SiNode anodes

110

Bear Creek Wind Farm | Open Energy Information  

Open Energy Info (EERE)

Bear Creek Wind Farm Bear Creek Wind Farm Facility Bear Creek Sector Wind 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 Creek Village PA Coordinates 41.1801°, -75.7216° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":41.1801,"lon":-75.7216,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

111

Sun Bear Solar Ltd | Open Energy Information  

Open Energy Info (EERE)

Sun Bear Solar Ltd Place: Hong Kong Sector: Solar Product: Hong Kong-based firm that manufactures solar product equipment, such as PV glass, coatings and mirrors. References: Sun...

112

Carbon nanotube bearings in theory and practice  

E-Print Network (OSTI)

Carbon Nanotubes (CNTs) are attractive elements for bearings in Micro-Electro-Mechanical Systems (MEMS), because their structure comprises nested shells with no bonding and sub-nanometer spacing between them, enabling ...

Cook, Eugene Hightower

2011-01-01T23:59:59.000Z

113

A carbon nanotube bearing and Stodola rotor  

E-Print Network (OSTI)

A nano-scale rotor supported on a cantilevered multi-wall carbon nanotube (MWNT) shaft (Stodola configuration) is proposed. The nanotube is also expected to function as the bearing, since individual walls of a MWNT are not ...

Cook, Eugene Hightower

2008-01-01T23:59:59.000Z

114

RUBBER BEARINGS FOR DOWN-HOLE PUMPS  

SciTech Connect

Synopsis of project activity: 1998--Awarded cost share grant from DOE. 1st Qtr 1999--Developed fail safe lubricating system. 2nd Qtr 1999--Performed first large scale test with nitrile based bearings. It failed due to material swelling. Failure was blamed on improper tolerance. 3rd Qtr 1999--Material tests were performed with autoclaves and exposure tests to Casa Diablo fluids. Testing of Viton materials began. Alternate bearing designs were developed to limit risk of improper tolerances. 4th Qtr 1999--Site testing indicated a chemical attack on the bearing material caused the test failure and not improper bearing tolerance. 1st Qtr 2000--The assistance of Brookhaven National Laboratory was obtained in evaluating the chemical attack. The National Laboratory also began more elaborate laboratory testing on bearing materials. 2nd Qtr 2000--Testing indicated Viton was an inappropriate material due to degradation in Casa Diablo fluid. Testing of EPDM began. 3rd Qtr 2001--EPDM bearings were installed for another large scale test. Bearings failed again due to swelling. Further testing indicated that larger then expected oil concentrations existed in lubricating water geothermal fluid causing bearing failure. 2002-2003--Searched for and tested several materials that would survive in hot salt and oil solutions. Kalrez{reg_sign}, Viton{reg_sign}ETP 500 and Viton{reg_sign}GF were identified as possible candidates. 2003-2005--Kalrez{reg_sign}has shown superior resistance to downhole conditions at Casa Diablo from among the various materials tested. Viton ETP-500 indicated a life expectancy of 13 years and because it is significantly less expensive then Kalrez{reg_sign}, it was selected as the bearing material for future testing. Unfortunately during the laboratory testing period Dupont Chemical chose to stop manufacturing this specific formulation and replaced it with Viton ETP 600S. The material is available with six different fillers; three based on zinc oxide and three based on silicon oxide. Samples of all six materials have been obtained and are being tested at the National Laboratory in Brookhaven, New York. This new material's properties as a bearing material and its ability to adhere to a bearings shell must be reviewed, but cost information deemed the material to be too expensive to be economical.

Bob Sullivan Mammoth Pacific, L.P.

2005-09-07T23:59:59.000Z

115

Elastohydrodynamic behavior of compliant slider bearings  

E-Print Network (OSTI)

ELASTOHYDRODYNAMIC BEHAVIOR OF COMPLIANT SLIDER BEARINGS A Thesis by RODNEY EMERSON HERRINGTON Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE December... 1973 Major Subject: Mechanical Engineering ELASTOHYDRODYNAMIC BEHAVIOR OF COMPLIANT SLIDER BEARINGS A Thesis by RODNEY EMERSON HERRINGTON Approved as to style and content by: (Chairma of Committee) (Head of Department) (Member) (Member...

Herrington, Rodney Emerson

2012-06-07T23:59:59.000Z

116

Waste Hoist  

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

117

Nuclear Waste  

Science Journals Connector (OSTI)

Nuclear waste is radioactive material no longer considered valuable...238U, 235U, and 226Ra (where the latter decays to 222Rn gas by emitting an alpha particle) or formed through fission of fissile radioisotopes ...

Rob P. Rechard

2014-01-01T23:59:59.000Z

118

Hot isostatic press waste option study report  

SciTech Connect

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.

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

1998-02-01T23:59:59.000Z

119

WASTE TO WATTS Waste is a Resource!  

E-Print Network (OSTI)

WASTE TO WATTS Waste is a Resource! energy forum Case Studies from Estonia, Switzerland, Germany Bossart,· ABB Waste-to-Energy Plants Edmund Fleck,· ESWET Marcel van Berlo,· Afval Energie Bedrijf From Waste to Energy To Energy from Waste #12;9.00-9.30: Registration 9.30-9.40: Chairman Ella Stengler opens

Columbia University

120

White-etching matter in bearing steel Part 2: Distinguishing cause and eect in bearing steel  

E-Print Network (OSTI)

White-etching matter in bearing steel Part 2: Distinguishing cause and eect in bearing steel through a mechanism called "white-structure flaking", has triggered many studies of microstructural damage associated with "white-etching ar- eas" created during rolling contact fatigue, although whether

Cambridge, University of

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


121

Remedial investigation work plan for Bear Creek Valley Operable Unit 4 (shallow groundwater in Bear Creek Valley) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee  

SciTech Connect

The enactment of the Resource Conservation and Recovery Act (RCRA) in 1976 and the Hazardous and Solid Waste Amendments (HSWA) to RCRA in 1984 created management requirements for hazardous waste fadities. The facilities within the Oak Ridge Reservation (ORR) were in the process of meeting the RCRA requirements when ORR was placed on the Comprehensive Environmental Response, Compensation, and Liability Act (CERCIA) National Priorities List (NPL) on November 21, 1989. Under RCRA, the actions typically follow the RCRA Facility Assessment (RIFA)/RCRA Facility Investigation (RFI)/Coffective Measures Study (CMS)/Corrective Measures Implementation process. Under CERCLA, the actions follow the Pre@ary Assessment/Site Investigation (PA/Sl) Remedial Investigation Feasibility Study (RI/FS)/Remedial Design/Remedial Action process. The development of this document will incorporate requirements under both RCRA and CERCIA into an RI Work Plan for the lint phase of characterization of Bear Creek Valley (BCV) Operable Unit (OU) 4.

Not Available

1992-12-01T23:59:59.000Z

122

EIS-0287-SA-01: Supplement Analysis | Department of Energy  

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

-SA-01: Supplement Analysis -SA-01: Supplement Analysis EIS-0287-SA-01: Supplement Analysis Idaho High-Level Waste and Facilities Disposition DOE/EIS-0287-SA-01: Supplement Analysis for the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement (June 2005). In October 2002, DOE issued the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement that provided an analysis of the potential environmental consequences of alternatives/options for the management and disposition of Sodium Bearing Waste (SBW), High-Level Waste (HLW) calcine, and HLW facilities at the Idaho Nuclear Technology and Engineering Center. DOE/EIS-0287-SA-01: Supplement Analysis for the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement (June 2005)

123

Page not found | Department of Energy  

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

21 - 9430 of 9,640 results. 21 - 9430 of 9,640 results. Download EIS-0287: Final Environmental Impact Statement Idaho High-Level Waste and Facilities Disposition http://energy.gov/nepa/downloads/eis-0287-final-environmental-impact-statement Download EIS-0287: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) 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... http://energy.gov/nepa/downloads/eis-0287-idaho-high-level-waste-and-facilities-disposition-final-environmental-impa-1 Download EIS-0250-S2: Final Supplemental Environmental Impact Statement Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level

124

Bear Canyon Geothermal Facility | Open Energy Information  

Open Energy Info (EERE)

Canyon Geothermal Facility Canyon Geothermal Facility Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Bear Canyon Geothermal Facility General Information Name Bear Canyon Geothermal Facility Facility Bear Canyon Sector Geothermal energy Location Information Location Clear Lake, California, Coordinates 38.762851116528°, -122.69217967987° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":38.762851116528,"lon":-122.69217967987,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

125

Wear Analysis of Wind Turbine Gearbox Bearings  

SciTech Connect

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.

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

2010-04-01T23:59:59.000Z

126

Waste Disposal (Illinois)  

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

This article lays an outline of waste disposal regulations, permits and fees, hazardous waste management and underground storage tank requirements.

127

Sleeping Bear Wind Farm | Open Energy Information  

Open Energy Info (EERE)

Sleeping Bear Wind Farm Sleeping Bear Wind Farm Jump to: navigation, search Name Sleeping Bear Wind Farm Facility Sleeping Bear Wind Farm Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner Edison Mission Group Developer Chermac Energy Corp./Edison Mission Group Energy Purchaser AEP - Public Service of Oklahoma Location Harper County OK Coordinates 36.63°, -99.5° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":36.63,"lon":-99.5,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

128

The Grizzly and the Big Brown Bears  

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

Grizzly and the Big Brown Bears Grizzly and the Big Brown Bears Nature Bulletin No. 655-A November 12, 1977 Forest Preserve District of Cook County George W. Dunne, President Roland F. Eisenbeis, Supt. of Conservation THE GRIZZLY AND THE BIG BROWN BEARS In the early days, more tall tales were told about "Old Ephraim, " the grizzly bear, than any other animal. It had the reputation of being a bloodthirsty enemy of man and was given the scientific name Ursus horribilis by a taxonomist who had never seen a live one but had heard and read some of those yarns about its terrible ferocity and prodigious strength. The Grizzly is very intelligent and shrewd but, actually, has a rather phlegmatic disposition. It avoids people and will not attack unless provoked. Then, a female with cubs is unpredictable, and big game hunters say that a wounded grizzly is the most dangerous animal on earth. But ordinarily, as Earnest Thompson Seton observed, Ephraim is a peaceful giant who is perfectly satisfied to let you alone if you leave him alone.

129

Cu-Bearing Tourmaline from Paraiba, Brazil  

Science Journals Connector (OSTI)

In Cu-bearing tourmaline, the octahedrally coordinated Z site is completely occupied by Al, the octahedrally coordinated Y site is occupied primarily by Li and Al, and the nine-coordinate X site is approximately half-occupied by Na.

MacDonald, D.J.

1995-04-15T23:59:59.000Z

130

Experimental verification of bifurcation in fluid bearings  

E-Print Network (OSTI)

The thesis presents the results of the experiments that were conducted on short and long fluid film bearings with a simple single disk rotor. The behavior of the journal was analyzed as function of the rotor system parameters such as the load, speed...

Deepak, James Christopher

1997-01-01T23:59:59.000Z

131

High Temperature, Permanent Magnet Biased Magnetic Bearings  

E-Print Network (OSTI)

performance, high speed and high temperature applications like space vehicles, jet engines and deep sea equipment. The bearing system had a target design to carry a load equal to 500 lb-f (2225N). Another objective was to design and build a test rig fixture...

Gandhi, Varun R.

2010-07-14T23:59:59.000Z

132

Turbine bearings and rotor dynamics workshop: proceedings  

SciTech Connect

An EPRI workshop to address turbine bearing reliability improvement and rotor dynamics was co-hosted by Detroit Edison in Dearborn, Michigan on September 8-10, 1982. The 136 attendees represented a broad spectrum of US utilities, equipment manufacturers, and consultants, as well as representatives from England, Japan, and Switzerland. These proceedings contain the text of the formal presentations as well as summaries of the working group sessions which were devoted to topics of particular interest to the workshop participants. Formal presentations were organized under the following general session titles: utility experience and advancements in turbine bearing and lubrication systems; recent advancements in turbine bearing and lubrication systems; utility experience and advancements in turbine-generator rotor dynamics; and recent advancements in turbine-generator rotor dynamics. In addition to the technical presentations, working group sessions were held on selected topics relevant to turbine bearing reliability improvement and rotor dynamics. These groups provided a forum for engineers to exchange ideas and information in a less formal environment. The discussions provided attendees with an opportunity to discuss key issues in more detail and address subjects not covered in the formal presentations. The subjects of these working groups were: rotor dynamic analysis and problem solving; vibration signature analysis and field balancing; oil contamination monitoring and control; and operation and maintenance practices. Individual papers have been entered individually into EDB and ERA.

Brown, R.G.; Quilliam, J.F. (eds.)

1985-06-01T23:59:59.000Z

133

Significance of chloritoid-bearing and staurolite-bearing rocks in the Picuris Range, New Mexico  

Science Journals Connector (OSTI)

...in the Picuris Mountains if endugh sillimanite- bearing rocks were examined. ACKNOWLEDGMENTS I thank Harold Dailey and John Futch for assistance in the field and in p trographie work. Elaine Padovani, James Toni, and James Carter were helpful with microprobe...

134

Waste Treatment and Immobilation Plant HLW Waste Vitrification...  

Office of Environmental Management (EM)

Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility Full Document and Summary Versions...

135

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE  

E-Print Network (OSTI)

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE January 2010 Prepared for the Interagency left intentionally blank.] #12;Prepared for the U.S. Department of Energy PNNL-SA-69994 under Contract DE-AC05-76RL01830 Waste Disposal Workshops: Anthrax-Contaminated Waste AM Lesperance JF Upton SL

136

Page not found | Department of Energy  

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

11 - 5720 of 28,560 results. 11 - 5720 of 28,560 results. Download EIS-0287: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) 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... http://energy.gov/nepa/downloads/eis-0287-idaho-high-level-waste-and-facilities-disposition-final-environmental-impa-1 Download Audit Report: OAS-L-03-16 Department of Energy's Nuclear Weapons Incident Response Program http://energy.gov/ig/downloads/audit-report-oas-l-03-16 Download DOE-TSPP-8, Approving and Issuing DOE Technical Standards- July 1, 2009 This document is the TSPP for Approving and Issuing DOE Technical

137

Page not found | Department of Energy  

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

31 - 8440 of 26,764 results. 31 - 8440 of 26,764 results. Download EIS-0287: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) 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... http://energy.gov/nepa/downloads/eis-0287-idaho-high-level-waste-and-facilities-disposition-final-environmental-impa-1 Download EA-1819: Final Environmental Assessment Kilowatts for Kenston Wind Energy Project, Chagrin Falls, Geauga County http://energy.gov/nepa/downloads/ea-1819-final-environmental-assessment Download LNG Annual Report- 2005 LNG Annual Report - 2005 http://energy.gov/fe/downloads/lng-annual-report-2005

138

EIS-0287: Final Environmental Impact Statement | Department of Energy  

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

Final Environmental Impact Statement Final Environmental Impact Statement EIS-0287: Final Environmental Impact Statement Idaho High-Level Waste and Facilities Disposition 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 liq- uid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. After considering comments on the Draft EIS (DOE/EIS- 0287D), as well as information on available treatment technologies, DOE and the State of Idaho have iden- tified separate preferred alternatives for

139

Building Technologies Office: HVAC Radial Air Bearing Heat Exchanger  

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

Radial Air Bearing Radial Air Bearing Heat Exchanger Research Project to someone by E-mail Share Building Technologies Office: HVAC Radial Air Bearing Heat Exchanger Research Project on Facebook Tweet about Building Technologies Office: HVAC Radial Air Bearing Heat Exchanger Research Project on Twitter Bookmark Building Technologies Office: HVAC Radial Air Bearing Heat Exchanger Research Project on Google Bookmark Building Technologies Office: HVAC Radial Air Bearing Heat Exchanger Research Project on Delicious Rank Building Technologies Office: HVAC Radial Air Bearing Heat Exchanger Research Project on Digg Find More places to share Building Technologies Office: HVAC Radial Air Bearing Heat Exchanger Research Project on AddThis.com... About Take Action to Save Energy Partner with DOE

140

A bulk-flow model of angled injection Lomakin bearings  

E-Print Network (OSTI)

A bulk-flow model for determination of the leakage and dynamic force characteristics of angled injection Lomakin bearings is presented. Zeroth- and first-order equations describe the equilibrium flow for a centered bearing and the perturbed flow...

Soulas, Thomas Antoine Theo

2001-01-01T23:59:59.000Z

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


141

Waste Processing | Department of Energy  

Office of Environmental Management (EM)

Processing Waste Processing Workers process and repackage waste at the Transuranic Waste Processing Centers Cask Processing Enclosure. Workers process and repackage waste at...

142

Recommendation 195: Mitigation of Contamination in Bear Creek Burial Grounds  

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

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

143

Waste Hoist  

NLE Websites -- All DOE Office Websites (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 is limited by a high-bay door at 4.14m high Nominal configuration is 2-cage (over/under), with bottom (equipment) cage interior height of 4.52m The photo, at left, shows the 4.14m high-bay doors at the top collar of the waste hoist shaft. The perpendicular cross section of the opening is 3.5m x 4.14m, but the bottom cage cross section is 2.87m x 4.5m (and 4.67m into the plane of the photo).

144

UCR Recreation Department Big Bear Lake House Policies  

E-Print Network (OSTI)

UCR Recreation Department Big Bear Lake House Policies The UCR Recreation Department strives of service animals. 15. The UCR Recreation Department Big Bear Lake House is a non-smoking facility. 16 Agreement with them while staying at the facility. 18. The UCR Recreation Department big Bear Lake House

Mills, Allen P.

145

Organic Tank Safety Project: development of a method to measure the equilibrium water content of Hanford organic tank wastes and demonstration of method on actual waste  

SciTech Connect

Some of Hanford`s underground waste storage tanks contain Organic- bearing high level wastes that are high priority safety issues because of potentially hazardous chemical reactions of organics with inorganic oxidants in these wastes such as nitrates and nitrites. To ensure continued safe storage of these wastes, Westinghouse Hanford Company has placed affected tanks on the Organic Watch List and manages them under special rules. Because water content has been identified as the most efficient agent for preventing a propagating reaction and is an integral part of the criteria developed to ensure continued safe storage of Hanford`s organic-bearing radioactive tank wastes, as part of the Organic Tank Safety Program the Pacific Northwest National Laboratory developed and demonstrated a simple and easily implemented procedure to determine the equilibrium water content of these potentially reactive wastes exposed to the range of water vapor pressures that might be experienced during the wastes` future storage. This work focused on the equilibrium water content and did not investigate the various factors such as @ ventilation, tank surface area, and waste porosity that control the rate that the waste would come into equilibrium, with either the average Hanford water partial pressure 5.5 torr or other possible water partial pressures.

Scheele, R.D.; Bredt, P.R.; Sell, R.L.

1996-09-01T23:59:59.000Z

146

Bear, Delaware: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

Bear, Delaware: Energy Resources Bear, Delaware: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 39.6292788°, -75.6582628° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":39.6292788,"lon":-75.6582628,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

147

Buffalo Bear Wind Farm | Open Energy Information  

Open Energy Info (EERE)

Wind Farm Wind Farm Jump to: navigation, search Name Buffalo Bear Wind Farm Facility Buffalo Bear Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner Edison Mission Group Developer Edison Mission Group Energy Purchaser Western Farmers Electric Coop Location OK Coordinates 36.573681°, -99.573275° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":36.573681,"lon":-99.573275,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

148

Organic tank safety project: Preliminary results of energetics and thermal behavior studies of model organic nitrate and/or nitrite mixtures and a simulated organic waste  

SciTech Connect

As a result of years of production and recovery of nuclear defense materials and subsequent waste management at the Hanford Site, organic-bearing radioactive high-level wastes (HLW) are currently stored in large (up to 3. ML) single-shell storage tanks (SSTs). Because these wastes contain both fuels (organics) and the oxidants nitrate and nitrite, rapid energetic reactions at certain conditions could occur. In support of Westinghouse Hanford Company`s (WHC) efforts to ensure continued safe storage of these organic- and oxidant-bearing wastes and to define the conditions necessary for reactions to occur, we measured the thermal sensitivities and thermochemical and thermokinetic properties of mixtures of selected organics and sodium nitrate and/or nitrite and a simulated Hanford organic-bearing waste using thermoanalytical technologies. These thermoanalytical technologies are used by chemical reactivity hazards evaluation organizations within the chemical industry to assess chemical reaction hazards.

Scheele, R.D.; Sell, R.L.; Sobolik, J.L.; Burger, L.L.

1995-08-01T23:59:59.000Z

149

Prediction and measurement of the rotordynamic response of an automotive turbocharger with floating ring bearings  

E-Print Network (OSTI)

of lubricant heating and bearing clearance changes due to bearing power consumption. The floating ring bearing analysis provides both floating ring speeds and bearing force coefficients for use in a linear rotordynamic model. The linear rotordynamic...

Kerth, Jason Michael

2012-06-07T23:59:59.000Z

150

Central Waste Complex (CWC) Waste Analysis Plan  

SciTech Connect

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

ELLEFSON, M.D.

1999-12-01T23:59:59.000Z

151

MANAGING THE RETRIEVAL RISK OF BURIED TRANSURANIC (TRU) WASTE WITH UNIQUE CHARACTERISTICS  

SciTech Connect

United States-Department of Energy (DOE) sites that store transuranic (TRU) waste are almost certain to encounter waste packages with characteristics that are so unique as to warrant special precautions for retrieval. At the Hanford Site, a subgroup of stored TRU waste (12 drums) had special considerations due to the radioactive source content of plutonium oxide (PuO{sub 2}), and the potential for high heat generation, pressurization, criticality, and high radiation. These characteristics bear on the approach to safely retrieve, overpack, vent, store, and transport the waste package. Because of the potential risk to personnel, contingency planning for unexpected conditions played an effective role in work planning and in preparing workers for the field inspection activity. As a result, the integrity inspections successfully confirmed waste package configuration and waste confinement without experiencing any perturbations due to unanticipated packaging conditions. This paper discusses the engineering and field approach to managing the risk of retrieving TRU waste with unique characteristics.

WOJTASEK, R.D.; GADD, R.R.; GREENWELL, R.D.

2006-01-19T23:59:59.000Z

152

Radioactive Waste Management (Minnesota)  

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

This section regulates the transportation and disposal of high-level radioactive waste in Minnesota, and establishes a Nuclear Waste Council to monitor the federal high-level radioactive waste...

153

Radioactive Waste Management  

Directives, Delegations, and Requirements

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

1984-02-06T23:59:59.000Z

154

Transuranic Waste Requirements  

Directives, Delegations, and Requirements

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.

1999-07-09T23:59:59.000Z

155

Waste?to?Energy  

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

Waste?to?Energy Roadmapping Workshop Waste?to?Energy Presentation by Jonathan Male, Director of the Bioenery Technolgies Office, Department of Energy

156

Nuclear Waste Disposal: Amounts of Waste  

Science Journals Connector (OSTI)

The term nuclear waste...embraces all residues from the use of radioactive materials, including uses in medicine and industry. The most highly radioactive of these are the spent fuel or reprocessed wastes from co...

2005-01-01T23:59:59.000Z

157

WasteTraining Booklet Waste & Recycling Impacts  

E-Print Network (OSTI)

WasteTraining Booklet #12;Waste & Recycling Impacts Environment: The majority of our municipal jobs while recycling 10,000 tons of waste creates 36 jobs. Environment: Recycling conserves resources. It takes 95% less energy to make aluminum from recycled aluminum than from virgin materials, 60% less

Saldin, Dilano

158

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

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.

NONE

1996-09-01T23:59:59.000Z

159

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

SciTech Connect

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.

NONE

1996-09-01T23:59:59.000Z

160

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

SciTech Connect

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.

NONE

1994-12-31T23:59:59.000Z

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


161

SPHERICAL RESORCINOL-FORMALDEHYDE PERFORMANCE TESTING WITH HANFORD TANK WASTE  

SciTech Connect

The efficacy of a new spherically engineered form of resorcinol-formaldehyde (RF) resin was tested for cesium removal on two actual Hanford tank wastes. Small-scale processing was conducted according to the River Protection Project-Waste Treatment and Immobilization Plant flowsheet in a lead-lag column format. The RF resin processed 95 bed volumes (BVs) of high potassium-bearing waste (AP-101) and >200 BVs of a high complexant-bearing waste (AN-102) before reaching 50% cesium breakthrough. Elution with 0.5 M nitric acid was effective and complete after processing 16 BVs. Cesium and other analyte fractionations to the process stream effluent and eluate were evaluated. The RF resin resulted in very little metal and radionuclide fractionation, other than cesium, to the eluate. The spent resins were measured for most analytes relevant to land-disposal requirements. The actinide concentrations on the spent resins were <3% of the transuranic waste limit; the residual cesium concentrations were <4 mCi/kg; chromium was the only metal, regulated by the Resource Conservation Recovery Act, that was measured in quantities significant to land-disposal regulations.

Fiskum, Sandra K.; Arm, Stuart T.; Steele, Marilyn J.; Thorson, Murray R.

2008-07-16T23:59:59.000Z

162

Recycling of sodium waste  

Science Journals Connector (OSTI)

Recycling of sodium waste ... Methods for handling and recycling a dangerous and costly chemical. ...

Bettina Hubler-Blank; Michael Witt; Herbert W. Roesky

1993-01-01T23:59:59.000Z

163

HVAC Radial Air Bearing Heat Exchangers Research Project | Department of  

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

Radial Air Bearing Heat Exchangers Radial Air Bearing Heat Exchangers Research Project HVAC Radial Air Bearing Heat Exchangers Research Project The U.S. Department of Energy is currently conducting research into heating, ventilation, and air conditioning (HVAC) radial air bearing heat exchangers. Rotary air bearing heat exchanger technology simultaneously solves four long standing problems of conventional "fan-plus-finned-heat-sink" heat exchangers. Project Description This project seeks to design, fabricate, and test successive generations of prototype radial air bearing heat exchanger devices based on lessons learned and further insights into device optimization, computational fluid dynamic studies for parametric optimization and determination of scaling laws, and laboratory measurement of flow field and heat transfer

164

Positive contact, self retaining bearing seals  

DOE Patents (OSTI)

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.

Johnson, Bruce H. (Kansas City, MO); Larsen, Lawrence E. (Kansas City, MO); Welch, Edmund F. (Kansas City, MO)

1992-05-05T23:59:59.000Z

165

Central Waste Complex (CWC) Waste Analysis Plan  

SciTech Connect

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source special nuclear and by-product material components of mixed waste, radionuclides are not within the scope of this document. The information on radionuclides is provided only for general knowledge. This document has been revised to meet the interim status waste analysis plan requirements of Washington Administrative Code (WAC) 173 303-300(5). When the final status permit is issued, permit conditions will be incorporated and this document will be revised accordingly.

ELLEFSON, M.D.

2000-01-06T23:59:59.000Z

166

Infectious waste feed system  

DOE Patents (OSTI)

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.

Coulthard, E. James (York, PA)

1994-01-01T23:59:59.000Z

167

White Bear Lake Conservation District (Minnesota) | Department of Energy  

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

White Bear Lake Conservation District (Minnesota) White Bear Lake Conservation District (Minnesota) White Bear Lake Conservation District (Minnesota) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Minnesota Program Type Siting and Permitting This statute establishes the White Bear Lake Conservation District, which

168

Notes 09. Fluid inertia and turbulence in fluid film bearings  

E-Print Network (OSTI)

When fluid inertia effects are important. Bulk-flow model for inertial flows. Turbulence and inertia in short length journal bearings and open end dampers....

San Andres, Luis

2009-01-01T23:59:59.000Z

169

Notes 03. Kinematics of motion in cylindrical journal bearings  

E-Print Network (OSTI)

Reynolds equation for cylindrical journal bearings. Kinematics of motion and film thickness. Distinction between fixed and rotating coordinates. The pure squeeze velocity vector. Examples of journal motion....

San Andres, Luis

2009-01-01T23:59:59.000Z

170

Axial bearing with gas lubrication for marine turbines  

Science Journals Connector (OSTI)

The possibility of enhancing the carrying capacity of the lubricant layer in bearings with gas lubrication is considered, for marine turbines. The basic design features of the hybrid...

M. V. Gribinichenko; A. V. Kurenskii; N. V. Sinenko

2013-10-01T23:59:59.000Z

171

Computer-aided design (CAD) of full hydrodynamic journal bearings  

Science Journals Connector (OSTI)

Since the equations involved in solving bearing problems are tedious to work with, calculations are most easily made by the use of bearing performance charts. However, the design of journal bearings is still a relatively cumbersome iterative process that involves the use of various data charts and tables, thus leading to time consuming and less accurate results. Therefore, a complete computer-aided design (CAD) procedure covering the basic methods for designing a full hydrodynamic journal bearing of finite length is developed and presented. The theoretical data and relevant empirical charts are collected and presented in appropriate formats. Also, the design variables of load per unit of projected bearing area, and bearing clearance in industrial applications, needed in the bearing design, are derived and incorporated in the design process. However, when designing a bearing for a given application, an infinite number of solutions is possible. Thus, certain limitations are imposed on the values of the bearing performance variables including stability, based on empirical guidelines. Consequently, one may select the solution for optimum conditions, say of maximum load capacity, or the minimum power loss (i.e. minimum friction). Finally, the CAD programme developed and constructed is general, fully automated, flexible, extendable, interactive and friendly to use.

M.H. Es-Saheb; Y.A. Al-Kalifa

2003-01-01T23:59:59.000Z

172

Investigations of Bearing Failures Associated with White Etching...  

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

Investigations of Bearing Failures Associated with White Etching Areas (irWEAs) in Wind Turbine Gearboxes Presented by Bob Errichello of GEARTECH at the Wind Turbine Tribology...

173

Contestation of Place: Bear Butte and the Sturgis Motorcycle Rally.  

E-Print Network (OSTI)

??The sacred American Indian mountain of Bear Butte, South Dakota is a contested place under threat from the biker themed campgrounds that facilitate the Sturgis (more)

Stasiuk, Davie D.

2012-01-01T23:59:59.000Z

174

Radioactive Waste Management Manual  

Directives, Delegations, and Requirements

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.

1999-07-09T23:59:59.000Z

175

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

SciTech Connect

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.

NONE

1997-04-01T23:59:59.000Z

176

Bear Valley Electric Service | Open Energy Information  

Open Energy Info (EERE)

Service Service Jump to: navigation, search Name Bear Valley Electric Service Place California Utility Id 17612 Utility Location Yes Ownership I NERC Location WECC NERC WECC Yes Operates Generating Plant Yes Activity Generation Yes Activity Buying Transmission Yes Activity Distribution Yes Activity Wholesale Marketing Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png A-1 General Service, less than 20 kW A-1 General Service, less than 20 kW - Direct Access Commercial A-2 General Service, 20 to 50 kW A-2 General Service, 20 to 50 kW - Direct Access A-3 General Service, more than 50 kW Commercial

177

Hybrid air foil bearing with external pressurization  

E-Print Network (OSTI)

) becomes smooth. 20 Figure 3.7 Non-dimensional film thickness for operating parameters in Table 3.1 with S f =1 21 m ? m ? (a) S f = 0.8 m ? (b) S f = 0.5 (c) S f = 0.2 m ? Figure 3... and NASA [18] experimental minimum film thickness; L/D=1, C=31.8 m? , and bump stiffness = 4.7 GN/m 3 Figure 3.11 describes a non-dimensional pressure (P=p/p a ), film thickness (H=h/C), and bump deflection (W=w B /C) for the bearing in Table 3.1 at 45...

Park, Soongook

2009-05-15T23:59:59.000Z

178

Resonant frequency method for bearing ball inspection  

DOE Patents (OSTI)

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.

Khuri-Yakub, B. T. (Palo Alto, CA); Hsieh, Chung-Kao (Stanford, CA)

1993-01-01T23:59:59.000Z

179

Resonant frequency method for bearing ball inspection  

DOE Patents (OSTI)

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.

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

1993-11-02T23:59:59.000Z

180

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....

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


181

Bioelectrochemical Integration of Waste Heat Recovery, Waste...  

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

and Waste-to-Chemical Conversion with Industrial Gas and Chemical Manufacturing Processes Air Products and Chemicals, Inc. - Allentown, PA A microbial reverse electrodialysis...

182

Bioelectrochemical Integration of Waste Heat Recovery, Waste...  

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

(ex: organic Rankine cycle) High installed KW capital Low temperature waste heat (<100C) is not practicable Further efficiency loss in electrolytic conversion to...

183

Permanent magnet design for high-speed superconducting bearings  

DOE Patents (OSTI)

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.

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

1996-09-10T23:59:59.000Z

184

Thermal Effects on the Bearing Behavior of Composite Joints  

Science Journals Connector (OSTI)

Thermal effects on the pin-bearing behavior of an IM7/PETI5 composite laminate are studied comprehensively within this paper. Pin-bearing tests of several lay-ups at the operating temperatures of -200 degrees F, 70 degrees F, and 350 degrees F are conducted ...

Walker Sandra Polesky

2001-05-01T23:59:59.000Z

185

Diesel engine crankshaft journal bearings failures: Case study  

Science Journals Connector (OSTI)

Abstract Wear as a tribological process has major influence on the reliability and life of engine crankshaft bearings. The importance of field examinations of bearing failures due to wear is very well known. They point to the possible causes of wear and to the necessary treatment for its reduction or elimination. The paper presents the results obtained by examining 616 crankshaft bearings, damaged by different mechanisms. The bearings were installed in high-speed diesel engines, and were gathered for two years, during general repairs of the engines (overhaul), i.e. after 30005000 working hours. After the examination of the bearings, the fault tree analysis (FTA) was performed to determine the root causes for engine bearing failures. Each type of damage that was identified was illustrated with an appropriate high-resolution photograph. The investigations show that the basic and most conspicuous types of damage which cause bearing failures are abrasive, adhesive and surface fatigue wear. The paper also considers the effects of the place of installation and type of bearing material in respect to each type of wear.

Aleksandar Vencl; Aleksandar Rac

2014-01-01T23:59:59.000Z

186

Vibration Control of Multi-Mode Rotor-Bearing Systems  

Science Journals Connector (OSTI)

8 March 1983 research-article Vibration Control of Multi-Mode Rotor-Bearing...least-squares method to minimize the vibration of any general rotor-bearing system...to implement the open-loop adaptive vibration control strategies outlined in the paper...

1983-01-01T23:59:59.000Z

187

High temperature, permanent magnet biased, homopolar magnetic bearing actuator  

E-Print Network (OSTI)

current resistance and improves the system efficiency because the magnetic field of the HTPM can suspend the major portion of the static load on bearing. A high temperature radial magnetic bearing was designed via an iterative search employing 3D finite...

Hossain, Mohammad Ahsan

2006-10-30T23:59:59.000Z

188

Radioactive Waste Management Manual  

Directives, Delegations, and Requirements

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.

1999-07-09T23:59:59.000Z

189

Radioactive Waste: 1. Radioactive waste from your lab is  

E-Print Network (OSTI)

Radioactive Waste: 1. Radioactive waste from your lab is collected by the RSO. 2. Dry radioactive waste must be segregated by isotope. 3. Liquid radioactive waste must be separated by isotope. 4. Liquid frequently and change them if contaminated. 5. Use radioactive waste container to collect the waste. 6. Check

Jia, Songtao

190

Hanford Dangerous Waste Permit  

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

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...

191

Hanford Dangerous Waste Permit  

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

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...

192

Hazardous Waste Management (Oklahoma)  

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

This article states regulations for the disposal of hazardous waste. It also provides information about permit requirements for the transport, treatment and storage of such waste. It also mentions...

193

Nuclear waste solids  

Science Journals Connector (OSTI)

Glass and polycrystalline materials for high-level radioactive waste immobilization are discussed. Borosilicate glass has been selected as the waste form for defence high-level radwaste in the US. Since releas...

L. L. Hench; D. E. Clark; A. B. Harker

1986-05-01T23:59:59.000Z

194

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

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

Contractor 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 ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 2 4.0 Results ................................................................................................................................................... 2

195

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

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

Contractor 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 ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 2 4.0 Results ................................................................................................................................................... 2

196

Waste disposal package  

DOE Patents (OSTI)

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.

Smith, M.J.

1985-06-19T23:59:59.000Z

197

Flywheel energy storage using superconducting magnetic bearings  

SciTech Connect

Storage of electrical energy on a utility scale is currently not practicable for most utilities, preventing the full utilization of existing base-load capacity. A potential solution to this problem is Flywheel Energy Storage (FES), made possible by technological developments in high-temperature superconducting materials. Commonwealth Research Corporation (CRC), the research arm of Commonwealth Edison Company, and Argonne National Laboratory are implementing a demonstration project to advance the state of the art in high temperature superconductor (HTS) bearing performance and the overall demonstration of efficient Flywheel Energy Storage. Currently, electricity must be used simultaneously with its generation as electrical energy storage is not available for most utilities. Existing storage methods either are dependent on special geography, are too expensive, or are too inefficient. Without energy storage, electric utilities, such as Commonwealth Edison Company, are forced to cycle base load power plants to meet load swings in hourly customer demand. Demand can change by as much as 30% over a 12-hour period and result in significant costs to utilities as power plant output is adjusted to meet these changes. HTS FES systems can reduce demand-based power plant cycling by storing unused nighttime capacity until it is needed to meet daytime demand.

Abboud, R.G. [Commonwealth Research Corp., Chicago, IL (United States); Uherka, K.; Hull, J.; Mulcahy, T. [Argonne National Lab., IL (United States)

1994-04-01T23:59:59.000Z

198

Vibration diagnosis of main journal bearings for diesel engines  

Science Journals Connector (OSTI)

A comprehensive summary of the vibration diagnosis techniques used to detect the wear of the main journal bearings in a diesel engine is presented. The load of the main journal bearing, the minimum thickness of the oil film, the oil film pressure and the locus of the crankshaft centre have been calculated based on the measured thermal parameters. Simulated wear experiments for the main journal bearing have been carried out in laboratory conditions. The strain and vibration on the main journal pedestals in the vertical direction were measured under various working conditions. The strain signals on the main journal bearing pedestal are related to the oil film forces, damped by the lubricant oil. The excitation sources and the vibration characteristics of the main journal bearing pedestal system were analysed by measuring the vibration signals. The relationships between the feature parameters of the vibration signals and the wear conditions of the main journal bearing have been obtained. It is promising, therefore, to develop and apply the vibration diagnosis technique further to detect the wear conditions of the main journal bearings online.

Yonghua Yu; Jianguo Yang

2005-01-01T23:59:59.000Z

199

Dynamic gas bearing turbine technology in hydrogen plants  

Science Journals Connector (OSTI)

Dynamic Gas Bearing Turbines - although applied for helium refrigerators and liquefiers for decades - experienced limitations for hydrogen applications due to restrictions in axial bearing capacity. With a new design concept for gas bearing turbines developed in 2004 axial bearing capacity was significantly improved enabling the transfer of this technology to hydrogen liquefiers. Prior to roll-out of the technology to industrial plants the turbine bearing technology passed numerous tests in R&D test benches and subsequently proved industrial scale demonstration at Linde Gas' hydrogen liquefier in Leuna Germany. Since its installation this turbine has gathered more than 16 000 successful operating hours and has outperformed its oil bearing brother in terms of performance maintainability as well as reliability. The present paper is based on Linde Kryotechnik AG's paper published in the proceedings of the CEC 2009 concerning the application of Dynamic Gas Bearing Turbines in hydrogen applications. In contrast to the former paper this publication focuses on the steps towards final market launch and more specifically on the financial benefits of this turbine technology both in terms of capital investment as well as operating expenses.

Klaus Ohlig; Stefan Bischoff

2012-01-01T23:59:59.000Z

200

Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 3: Appendix D -- Nature and extent of contamination report  

SciTech Connect

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 D describes the nature and extent of contamination in environmental media and wastes.

NONE

1996-09-01T23:59:59.000Z

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


201

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both radioactive materials  

E-Print Network (OSTI)

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both as noted on the list, you do not have a mixed waste and it may be managed as a normal radioactive waste radioactive waste after initially dating the container, the hold for decay time is extended, but you cannot

Straight, Aaron

202

Sequence stratigraphy, paleoclimate, and tectonics of coal-bearing strata  

SciTech Connect

The origin of coal-bearing strata has been debated vigorously for more than a century, and with the emergence of coalbed methane as a major energy resource and the possibility of sequestering greenhouse gas in coal, this debate has never been more relevant. This volume contains 10 chapters on coal-bearing strata of Carboniferous through Tertiary age and is based on a special session that was held at an AAPG Annual Meeting in New Orleans. Contributors have employed a multitude of approaches ranging from basin analysis to plant taphonomy to support a variety of views on the sequence stratigraphy, paleoclimate, and tectonics of coal-bearing strata.

Jack C. Pashin; Robert A. Gastaldo (eds.)

2004-07-15T23:59:59.000Z

203

E-Print Network 3.0 - alternate bearing indices Sample Search...  

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

Summary: .124313506501JET477 Abstract: Offset' journal bearings provide an alternate design approach for problematic... suggests that offset bearings might provide a good...

204

Modernization of the guide bearings of turbines of the cascade of Chirchik hydroelectric stations  

Science Journals Connector (OSTI)

The favorable experience of reconstruction and subsequent operation of the guide bearings of turbines of the cascade of Chirchik hydrostations confirms the possibility of modernizing bearings under conditions ...

V. V. Balagurov; Yu. P. Maizel'; M. A. Tsvetkova

1981-08-01T23:59:59.000Z

205

Radioactive Waste Management Manual  

Directives, Delegations, and Requirements

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, cancels DOE M 435.1-1 Chg 1.

1999-07-09T23:59:59.000Z

206

Transuranic Waste Transportation Working Group Agenda | Department...  

Office of Environmental Management (EM)

Transuranic Waste Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda More Documents &...

207

Waste Isolation Pilot Plant Transportation Security | Department...  

Office of Environmental Management (EM)

Waste Isolation Pilot Plant Transportation Security Waste Isolation Pilot Plant Transportation Security Waste Isolation Pilot Plant Transportation Security More Documents &...

208

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

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

Bearing Corp - IN 09 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 Radioactive Materials Handled: Uranium IN.09-1 Radiological Survey(s): None Indicated Site Status: Eliminated from further consideration under FUSRAP - Referred to NRC IN.09-4 Also see Documents Related to American Bearing Corp. IN.09-1 - National Lead Company of Ohio Memorandum; Ciborski to

209

Timken XEMC Hunan Bearings Co Ltd | Open Energy Information  

Open Energy Info (EERE)

Timken XEMC Hunan Bearings Co Ltd Timken XEMC Hunan Bearings Co Ltd Jump to: navigation, search Name Timken XEMC (Hunan) Bearings Co Ltd Place Xiangtan, Hunan Province, China Sector Wind energy Product Manufacturer of ultra-large-bore bearings for large scale wind turbines. Coordinates 27.859819°, 112.892067° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":27.859819,"lon":112.892067,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

210

Circular sensor array and nonlinear analysis of homopolar magnetic bearings  

E-Print Network (OSTI)

an adjustment factor for single failures. A prototype 8-sensor array shows substantial runout reduction and bandwidth and sensitivity comparable to commercial systems. Nonlinear behavior in homopolar magnetic bearings is caused primarily by the quadratic...

Wiesenborn, Robert Kyle

2007-04-25T23:59:59.000Z

211

Three dimensional thermohydrodynamic analysis of multi-lobed bearings  

E-Print Network (OSTI)

An approach for three dimensional Therinohydrodyiiamic analysis of multi-lobed journal bearings is presented. The generalized Reynolds equation solution yields the Dressure distribution in the axial and circumferential directions. The energy...

Mulchandani, Rajesh R.

1997-01-01T23:59:59.000Z

212

Preliminary relative permeability estimates of methane hydrate-bearing sand  

E-Print Network (OSTI)

sand, the gas permeability of the sand with hydrate, and thefor gas and water through methane hydrate-bearing sand. X-hydrate dissociation and making a single-phase (gas or water) permeability measurement of the sand

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

2006-01-01T23:59:59.000Z

213

Cooling system for a bearing of a turbine rotor  

DOE Patents (OSTI)

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.

Schmidt, Mark Christopher (Niskayuna, NY)

2002-01-01T23:59:59.000Z

214

Modeling of virtual standards of vibration of defective bearing units  

Science Journals Connector (OSTI)

Results of studies designed to model vibration signals are presented below. A sample of time signals obtained as a result of cranking defective and defect-free bearings of railway freight cars on a test bench ser...

V. Yu. Tetter; E. N. Sidorov; E. A. Sidorova

2013-06-01T23:59:59.000Z

215

Cryocooler Applications for High-Temperature Superconductor Magnetic Bearings  

Science Journals Connector (OSTI)

The efficiency and stability of rotational magnetic suspension systems are enhanced by the use of high-temperature superconductor (HTS) magnetic bearings. Fundamental aspects of ... aspects to be considered are i...

R. C. Niemann; J. R. Hull

2002-01-01T23:59:59.000Z

216

Field Examples of Axial Cracked Bearings in Wind Turbine Gearboxes...  

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

Field Examples of Axial Cracked Bearings in Wind Turbine Gearboxes Presented by Paul John Baker of FrontierPro Services at the Wind Turbine Tribology Seminar 2014. 141030 Axial...

217

Force measurements in magnetic bearings using fiber optic strain gauges  

E-Print Network (OSTI)

Turbomachinery Laboratory. Two FOSGs were placed approximately 90? apart on two separate poles of one of the bearings, and the strain levels for different load magnitudes and directions were measured. The raw signal has several undesirable attributes...

Raymer, Stephen Geoffrey

2000-01-01T23:59:59.000Z

218

Gas Foil Bearing Technology Advancements for Closed Brayton Cycle Turbines  

Science Journals Connector (OSTI)

Closed Brayton Cycle (CBC) turbine systems are under consideration for future space electric power generation. CBC turbines convert thermal energy from a nuclear reactor or other heat source to electrical power using a closed?loop cycle. The operating fluid in the closed?loop is commonly a high pressure inert gas mixture that cannot tolerate contamination. One source of potential contamination in a system such as this is the lubricant used in the turbomachine bearings. Gas Foil Bearings (GFB) represent a bearing technology that eliminates the possibility of contamination by using the working fluid as the lubricant. Thus foil bearings are well suited to application in space power CBC turbine systems. NASA Glenn Research Center is actively researching GFB technology for use in these CBC power turbines. A power loss model has been developed and the effects of very high ambient pressure start?up torque and misalignment have been observed and are reported here.

Samuel A. Howard; Robert J. Bruckner; Christopher DellaCorte; Kevin C. Radil

2007-01-01T23:59:59.000Z

219

High performance magnetic bearing systems using high temperature superconductors  

DOE Patents (OSTI)

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.

Abboud, R.G.

1998-05-05T23:59:59.000Z

220

High performance magnetic bearing systems using high temperature superconductors  

DOE Patents (OSTI)

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.

Abboud, Robert G. (Barrington Hills, IL)

1998-01-01T23:59:59.000Z

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


221

Tank Waste and Waste Processing | Department of Energy  

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

Tank Waste and Waste Processing 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 with glassified waste in a year. New bubbler technology and other enhancements will increase canister production in the future. The Defense Waste Processing Facility set a record by producing 267 canisters filled with glassified waste in a year. New bubbler technology and other enhancements will increase canister production in the future. A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility where the melter is pouring molten glass inside a canister. A Savannah River Remediation employee uses a manipulator located inside a

222

Bioelectrochemical Integration of Waste Heat Recovery, Waste...  

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

electrolytic cell, designed to integrate waste heat recovery (i.e a microbial heat recovery cell or MHRC), can operate as a fuel cell and convert effluent streams into...

223

New Waste Calcining Facility (NWCF) Waste Streams  

SciTech Connect

This report addresses the issues of conducting debris treatment in the New Waste Calcine Facility (NWCF) decontamination area and the methods currently being used to decontaminate material at the NWCF.

K. E. Archibald

1999-08-01T23:59:59.000Z

224

Solid Waste Management Plan. Revision 4  

SciTech Connect

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.

NONE

1995-04-26T23:59:59.000Z

225

Waste Confidence Discussion | Department of Energy  

Office of Environmental Management (EM)

Waste Confidence Discussion Waste Confidence Discussion Long-Term Waste Confidence Update. Waste Confidence Discussion More Documents & Publications Status Update: Extended Storage...

226

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

Office of Environmental Management (EM)

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

227

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...

228

Ferrocyanide tank waste stability  

SciTech Connect

Ferrocyanide wastes were generated at the Hanford Site during the mid to late 1950s as a result of efforts to create more tank space for the storage of high-level nuclear waste. The ferrocyanide process was developed to remove [sup 137]CS from existing waste and newly generated waste that resulted from the recovery of valuable uranium in Hanford Site waste tanks. During the course of research associated with the ferrocyanide process, it was recognized that ferrocyanide materials, when mixed with sodium nitrate and/or sodium nitrite, were capable of violent exothermic reaction. This chemical reactivity became an issue in the 1980s, when safety issues associated with the storage of ferrocyanide wastes in Hanford Site tanks became prominent. These safety issues heightened in the late 1980s and led to the current scrutiny of the safety issues associated with these wastes, as well as current research and waste management programs. Testing to provide information on the nature of possible tank reactions is ongoing. This document supplements the information presented in Summary of Single-Shell Tank Waste Stability, WHC-EP-0347, March 1991 (Borsheim and Kirch 1991), which evaluated several issues. This supplement only considers information particular to ferrocyanide wastes.

Fowler, K.D.

1993-01-01T23:59:59.000Z

229

6 - Nuclear Waste Regulations  

Science Journals Connector (OSTI)

The most influential national and international bodies providing recommendations on radiation protection are described, including the International Commission on Radiological Protection (ICRP) and the International Atomic Energy Agency (IAEA). Protection philosophies and the ICRP general principles of radiation protection are discussed. Radioactive material regulations and sources of radiation are explained. Criteria of exemption from regulatory control are discussed with examples of exemption levels for naturally occurring and radioactive waste radionuclides. Clearance of both moderate and bulk amounts of materials from regulatory control is also explained, including examples of EU and the UK regulations. Dose limits recommended by the ICRP are given, as well as the main principles of control of radiation hazards. Nuclear waste classification schemes are outlined, including the IAEA classification scheme. A brief explanation of nuclear waste classes including exempt waste, very short-lived waste, very low-level waste, low-level waste, intermediate-level waste and high-level waste is given. Examples of waste classification schemes are given, including that of the UK.

M.I. Ojovan; W.E. Lee

2014-01-01T23:59:59.000Z

230

Hanford Tank Waste Information Enclosure 1 Hanford Tank Waste Information  

E-Print Network (OSTI)

Hanford Tank Waste Information Enclosure 1 1 Hanford Tank Waste Information 1.0 Summary This information demonstrates the wastes in the twelve Hanford Site tanks meet the definition of transuranic (TRU. The wastes in these twelve (12) tanks are not high-level waste (HLW), and contain more than 100 nanocuries

231

Energy from Waste UK Joint Statement on Energy from Waste  

E-Print Network (OSTI)

Energy from Waste UK Joint Statement on Energy from Waste Read more overleaf Introduction Energy from waste provides us with an opportunity for a waste solution and a local source of energy rolled,itcan onlyaddressaportionofthewastestream andisnotsufficientonitsown. Energy obtained from the combustion of residual waste (Energy from

232

Stabilization of compactible waste  

SciTech Connect

This report summarizes the results of series of experiments performed to determine the feasibility of stabilizing compacted or compactible waste with polymers. The need for this work arose from problems encountered at disposal sites attributed to the instability of this waste in disposal. These studies are part of an experimental program conducted at Brookhaven National Laboratory (BNL) investigating methods for the improved solidification/stabilization of DOE low-level wastes. The approach taken in this study was to perform a series of survey type experiments using various polymerization systems to find the most economical and practical method for further in-depth studies. Compactible dry bulk waste was stabilized with two different monomer systems: styrene-trimethylolpropane trimethacrylate (TMPTMA) and polyester-styrene, in laboratory-scale experiments. Stabilization was accomplished by wetting or soaking compactible waste (before or after compaction) with monomers, which were subsequently polymerized. Three stabilization methods are described. One involves the in-situ treatment of compacted waste with monomers in which a vacuum technique is used to introduce the binder into the waste. The second method involves the alternate placement and compaction of waste and binder into a disposal container. In the third method, the waste is treated before compaction by wetting the waste with the binder using a spraying technique. A series of samples stabilized at various binder-to-waste ratios were evaluated through water immersion and compression testing. Full-scale studies were conducted by stabilizing two 55-gallon drums of real compacted waste. The results of this preliminary study indicate that the integrity of compacted waste forms can be readily improved to ensure their long-term durability in disposal environments. 9 refs., 10 figs., 2 tabs.

Franz, E.M.; Heiser, J.H. III; Colombo, P.

1990-09-01T23:59:59.000Z

233

Waste Inspection Tomography (WIT)  

SciTech Connect

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. The mobile feature of WIT allows inspection technologies to be brought to the nuclear waste drum storage site without the need to relocate drums for safe, rapid, and cost-effective characterization of regulated nuclear waste. The combination of these WIT characterization modalities provides the inspector with an unprecedented ability to non-invasively characterize the regulated contents of waste drums as large as 110 gallons, weighing up to 1,600 pounds. Any objects that fit within these size and weight restrictions can also be inspected on WIT, such as smaller waste bags and drums that are five and thirty-five gallons.

Bernardi, R.T.

1995-12-01T23:59:59.000Z

234

White-Etching Matter in Bearing Steel. Part II: Distinguishing Cause and Effect in Bearing Steel Failure  

E-Print Network (OSTI)

The premature failure of large bearings of the type used in wind turbines, possibly through a mechanism called white-structure flaking, has triggered many studies of microstructural damage associated with white-etching areas created during...

Solano-Alvarez, W.; Bhadeshia, H. K. D. H.

2014-07-11T23:59:59.000Z

235

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)

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.

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

1994-11-22T23:59:59.000Z

236

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)

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.

Vijayan, Sivaraman (Deep River, CA); Wong, Chi F. (Pembroke, CA); Buckley, Leo P. (Deep River, CA)

1994-01-01T23:59:59.000Z

237

Pioneering Nuclear Waste Disposal  

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

18 18 19 T he WIPP's first waste receipt, 11 years later than originally planned, was a monumental step forward in the safe management of nuclear waste. Far from ending, however, the WIPP story has really just begun. For the next 35 years, the DOE will face many challenges as it manages a complex shipment schedule from transuranic waste sites across the United States and continues to ensure that the repository complies with all regulatory requirements. The DOE will work to maintain the highest level of safety in waste handling and trans- portation. Coordination with sites Disposal operations require coordination with sites that will ship transuranic waste to the WIPP and include periodic certification of waste characterization and handling practices at those facilities. During the WIPP's

238

SRS - Programs - Waste Solidification  

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

Waste Solidification Waste Solidification The two primary facilities operated within the Waste Solidification program are Saltstone and the Defense Waste Processing Facility (DWPF). Each DWPF canister is 10 feet tall and 2 feet in diameter, and typically takes a little over a day to fill. Each DWPF canister is 10 feet tall and 2 feet in diameter, and typically takes a little over a day to fill. The largest radioactive waste glassification plant in the world, DWPF converts the high-level liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for immobilizing high-level radioactive liquids into a more stable, manageable form until a federal

239

High level nuclear waste  

SciTech Connect

The DOE Division of Waste Products through a lead office at Savannah River is developing a program to immobilize all US high-level nuclear waste for terminal disposal. DOE high-level wastes include those at the Hanford Plant, the Idaho Chemical Processing Plant, and the Savannah River Plant. Commercial high-level wastes, for which DOE is also developing immobilization technology, include those at the Nuclear Fuel Services Plant and any future commercial fuels reprocessing plants. The first immobilization plant is to be the Defense Waste Processing Facility at Savannah River, scheduled for 1983 project submission to Congress and 1989 operation. Waste forms are still being selected for this plant. Borosilicate glass is currently the reference form, but alternate candidates include concretes, calcines, other glasses, ceramics, and matrix forms.

Crandall, J L

1980-01-01T23:59:59.000Z

240

Underground waste barrier structure  

DOE Patents (OSTI)

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.

Saha, Anuj J. (Hamburg, NY); Grant, David C. (Gibsonia, PA)

1988-01-01T23:59:59.000Z

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


241

Fasteners -- Preloading test for the detection of hydrogen embrittlement -- Parallel bearing surface method  

E-Print Network (OSTI)

Fasteners -- Preloading test for the detection of hydrogen embrittlement -- Parallel bearing surface method

International Organization for Standardization. Geneva

1999-01-01T23:59:59.000Z

242

ANALYSIS OF DAMAGE TO WASTE PACKAGES CAUSED BY SEISMIC EVENTS DURING POST-CLOSURE  

SciTech Connect

This paper presents methodology and results of an analysis of damage due to seismic ground motion for waste packages emplaced in a nuclear waste repository at Yucca Mountain, Nevada. A series of three-dimensional rigid body kinematic simulations of waste packages, pallets, and drip shields subjected to seismic ground motions was performed. The simulations included strings of several waste packages and were used to characterize the number, location, and velocity of impacts that occur during seismic ground motion. Impacts were categorized as either waste package-to-waste package (WP-WP) or waste package-to-pallet (WP-P). In addition, a series of simulations was performed for WP-WP and WP-P impacts using a detailed representation of a single waste package. The detailed simulations were used to determine the amount of damage from individual impacts, and to form a damage catalog, indexed according to the type, angle, location and force/velocity of the impact. Finally, the results from the two analyses were combined to estimate the total damage to a waste package that may occur during an episode of seismic ground motion. This study addressed two waste package types, four levels of peak ground velocity (PGV), and 17 ground motions at each PGV. Selected aspects of waste package degradation, such as effective wall thickness and condition of the internals, were also considered. As expected, increasing the PGV level of the vibratory ground motion increases the damage to the waste packages. Results show that most of the damage is caused by WP-P impacts. TAD-bearing waste packages with intact internals are highly resistant to damage, even at a PGV of 4.07 m/s, which is the highest level analyzed.

Alves, S W; Blair, S C; Carlson, S R; Gerhard, M; Buscheck, T A

2008-05-27T23:59:59.000Z

243

Synthesizing Optimal Waste Blends  

Science Journals Connector (OSTI)

Vitrification of tank wastes to form glass is a technique that will be used for the disposal of high-level waste at Hanford. ... Durability restrictions ensure that the resultant glass meets the quantitative criteria for disposal/long-term storage in a repository. ... If glasses are formulated to minimize the volume of glass that would be produced, then the cost of processing the waste and storing the resultant glass would be greatly reduced. ...

Venkatesh Narayan; Urmila M. Diwekar; Mark Hoza

1996-10-08T23:59:59.000Z

244

Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 4: Appendix E -- Valley-wide fate and transport report  

SciTech Connect

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 E addresses contaminant releases and migration pathways from a valley-wide perspective and provides estimates of changes in contaminant fluxes in BCV.

NONE

1996-09-01T23:59:59.000Z

245

Waste Confidence Discussion  

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

Long-Term Long-Term Waste Confidence Update Christine Pineda Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission National Transportation Stakeholders Forum May 2012 ♦ Knoxville, Tennessee Long-Term Update Draft Report, "Background and Preliminary Assumptions for an Environmental Impact Statement- Long-Term Waste Confidence Update" Elements of the Long-Term Update - Draft environmental impact statement - Draft Waste Confidence Decision - Proposed Waste Confidence Rule based on the EIS and Decision, if applicable 2 Overview of Draft Report Background and assumptions report is first step in process. Basic topics in the report are:

246

Norcal Waste Systems, Inc.  

SciTech Connect

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

Not Available

2002-12-01T23:59:59.000Z

247

Section 24: Waste Characterization  

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

Energy (DOE). 1995b. Transuranic Waste Baseline Inventory Report (Revision 2, December). DOECAO-95-1121. ERMS 531643. Carlsbad Area Office, Carlsbad, NM. PDF Author U.S....

248

Hanford Dangerous Waste Permit  

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

training, security) * Closure plan Tank-Related Permit Units New * 149 single-shell tanks (SSTs) * 28 double-shell tanks (DSTs) Existing * 242-A Evaporator * Waste Treatment...

249

Waste Heat Recovery  

Office of Environmental Management (EM)

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

250

Electronic Waste Transformation  

Science Journals Connector (OSTI)

Electronic Waste Transformation ... Instead, entrepreneurial individuals and small businesses recover valuable metals such as copper from obsolete equipment through activities such as burning. ...

CHERYL HOGUE

2012-04-01T23:59:59.000Z

251

Waste minimization assessment procedure  

SciTech Connect

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.

Kellythorne, L.L. (Centerior Energy, Cleveland, OH (United States))

1993-01-01T23:59:59.000Z

252

Vitrification of waste  

DOE Patents (OSTI)

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.

Wicks, G.G.

1999-04-06T23:59:59.000Z

253

Avoidable waste management costs  

SciTech Connect

This report describes the activity based costing method used to acquire variable (volume dependent or avoidable) waste management cost data for routine operations at Department of Energy (DOE) facilities. Waste volumes from environmental restoration, facility stabilization activities, and legacy waste were specifically excluded from this effort. A core team consisting of Idaho National Engineering Laboratory, Los Alamos National Laboratory, Rocky Flats Environmental Technology Site, and Oak Ridge Reservation developed and piloted the methodology, which can be used to determine avoidable waste management costs. The method developed to gather information was based on activity based costing, which is a common industrial engineering technique. Sites submitted separate flow diagrams that showed the progression of work from activity to activity for each waste type or treatability group. Each activity on a flow diagram was described in a narrative, which detailed the scope of the activity. Labor and material costs based on a unit quantity of waste being processed were then summed to generate a total cost for that flow diagram. Cross-complex values were calculated by determining a weighted average for each waste type or treatability group based on the volume generated. This study will provide DOE and contractors with a better understanding of waste management processes and their associated costs. Other potential benefits include providing cost data for sites to perform consistent cost/benefit analysis of waste minimization and pollution prevention (WMIN/PP) options identified during pollution prevention opportunity assessments and providing a means for prioritizing and allocating limited resources for WMIN/PP.

Hsu, K.; Burns, M.; Priebe, S.; Robinson, P.

1995-01-01T23:59:59.000Z

254

Waste Isolation Pilot Plant  

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

September 19, 2014 - No second release at WIPP September 12, 2014 - Waste hoist transformer replacement September 09, 2014 - Additional areas cleared in WIPP underground...

255

Vitrification of waste  

DOE Patents (OSTI)

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.

Wicks, George G. (Aiken, SC)

1999-01-01T23:59:59.000Z

256

Comparative test on two kinds of new compliant foil bearing for small cryogenic turbo-expander  

Science Journals Connector (OSTI)

Two kinds of new compliant foil journal bearing for a small cryogenic turbo-expander used in the Brayton cycle cryocooler are presented in this paper. The foil of bearings is supported with copper wires and elastic material respectively, so the bearings are much simpler in structure than previous compliant foil bearing. The performances of the bearings are studied under the same experiment conditions. The results indicate that both bearings have better damp performance and the foil bearing supported with elastic material has preferable stability to the one supported with copper wires.

Y Hou; Z.H Zhu; C.Z Chen

2004-01-01T23:59:59.000Z

257

The experimental determination of the dynamic radial stiffness of an angular contact ball bearing  

E-Print Network (OSTI)

Objectives 1 II LITERATURE REVIEW 3 Analytical Models 3 Experimental Investigations 4 III TEST BEARING 6 RL10 Angular Contact Ball Bearing 6 IV TEST RIG 7 V EXPERIMENTAL SETUP AND PROCEDURES 10 Static Pedestal Pull Tests 10 Static Bearing Pull Tests... components created a natural frequency that was primarily dependent on the test bearing stiffness. 4 5 1 Driver (air turbine) 2 Driver support 3 Coupling 4 Pocket damper seal 5 Rotor wheel 6 RL10 test bearing 7 Shaft 8 Slave bearing 9 Bearing...

Schmidt, Brent Lee

2012-06-07T23:59:59.000Z

258

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

SciTech Connect

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 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 group B (or A) tank identifies the potential for an induced flammable gas release hazard, the hazard only exists for specific operations that can release the retained gas in the tank at a rate and quantity that results in reaching 100% of the lower flammability limit in the tank headspace. The identification and evaluation of tank farm operations that could cause an induced flammable gas release hazard in a waste group B (or A) tank are included in other documents. The third criterion is the buoyancy ratio. This criterion addresses tanks that are not waste group C double-shell tanks and have an energy ratio {ge} 3.0. For these double-shell tanks, the buoyancy ratio considers whether the saturated solids can retain sufficient gas to exceed neutral buoyancy relative to the supernatant layer and therefore have buoyant displacement gas release events. If the buoyancy ratio is {ge} 1.0, that double-shell tank is assigned to waste group A. These tanks are considered to have a potential spontaneous buoyant displacement flammable gas release hazard in addition to a potential induced flammable gas release hazard.

FOWLER KD

2007-12-27T23:59:59.000Z

259

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

SciTech Connect

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 group B (or A) tank identifies the potential for an induced flammable gas release hazard, the hazard only exists for specific operations that can release the retained gas in the tank at a rate and quantity that results in reaching 100% of the lower flammability limit in the tank headspace. The identification and evaluation of tank farm operations that could cause an induced flammable gas release hazard in a waste group B (or A) tank are included in other documents. The third criterion is the buoyancy ratio. This criterion addresses tanks that are not waste group C double-shell tanks and have an energy ratio {ge} 3.0. For these double-shell tanks, the buoyancy ratio considers whether the saturated solids can retain sufficient gas to exceed neutral buoyancy relative to the supernatant layer and therefore have buoyant displacement gas release events. If the buoyancy ratio is {ge} 1.0, that double-shell tank is assigned to waste group A. These tanks are considered to have a potential spontaneous buoyant displacement flammable gas release hazard in addition to a potential induced flammable gas release hazard. 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 8 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs.

WEBER RA

2009-01-16T23:59:59.000Z

260

Processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents (OSTI)

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.

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

1998-05-12T23:59:59.000Z

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


261

Waste Loading Enhancements for Hanford Low-Activity Waste Glasses  

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

WASTE LOADING ENHANCEMENTS FOR HANFORD LOW-ACTIVITY WASTE GLASSES Albert A. Kruger, Glass Scientist DOE-WTP Project Office Engineering Division US Department of Energy Richland,...

262

Tank Waste Committee Page 1  

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

of a PA is to examine the final waste disposition at Hanford, such as waste in the tanks at C-Farm. Vince said the quest is to model waste movement over 10,000 years,...

263

EVALUATION OF A LOW FRICTION - HIGH EFFICIENCY ROLLER BEARING ENGINE  

SciTech Connect

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 machining and heat treatment. Timken designed and manufactured all of the roller bearing related components such as the thrust bearing package. The production connecting rods and camshafts could not be used for the roller bearing engine, so new ones were produced according to the teams designs using Timken steel. The remaining miscellaneous components were designed and procured by FEV. Timken prepared a display version of the crankshaft portion of the production engine without connecting rods which could be driven by a motor through a cogged-belt and electrically actuated clutch arrangement. A modified version was also made in which the engine was outfitted with roller bearings on the main bearing positions. Preliminary tests showed that the rollerized engine was running with 1/3 less friction than the standard display engine. Additional friction testing and noise characterization was cut short because of shipping damage to the rollerized engine display and because of other project priorities. The team did successfully demonstrate the ability to package roller bearings satisfactorily in numerous locations in a typical automotive engine. The scope of this project did not include durability demonstration and that subject would have to be addressed in any follow-on work. In the actual test phase, the rollerized engine did show significantly less friction in motored dynamometer tests compared to its production equivalent. The 5-10% improvement measured in this study was about half that seen in other studies. However, the fired test results did not show a reduction in friction which did not match prior experience or expectations. Subsequent teardown and inspection of the rollerized engine revealed potential sources of excessive friction in the experimental application. These features would be eliminated in a design not based on modification of production parts. The team is confident (based on experience) that friction reduction would be realized with proper modifications.

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

2009-06-30T23:59:59.000Z

264

Evaluation Of Used Fuel Disposition In Clay-Bearing Rock  

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

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...

265

WASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED,  

E-Print Network (OSTI)

DESCRIPTION DETAILS * Radioactive Waste Source Reduction 1,500 Radioactive Waste $6,000 $2,500 $6,000 Waste Yard Sorting Table surveying to sort clean waste from radioactive waste Radioactive Emissions Emission lives. Radioactive Waste generated through wet chemistry Waste Minimization 30 Mixed waste / Liquid

266

Chapter 19 - Nuclear Waste Fund  

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

Nuclear Waste Fund 19-1 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 Nuclear Waste Fund (NWF) or the Defense Nuclear Waste Disposal appropriation. c. Background. The Act established the Office of Civilian Radioactive Waste Management (OCRWM) and assigned it responsibility for the management

267

Solid Waste Rules (New Hampshire)  

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

The solid waste statute applies to construction and demolition debris, appliances, recyclables, and the facilities that collect, process, and dispose of solid waste. DES oversees the management of...

268

Solid Waste Management (North Carolina)  

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

The Solid Waste Program regulates safe management of solid waste through guidance, technical assistance, regulations, permitting, environmental monitoring, compliance evaluation and enforcement....

269

Waste Management | Department of Energy  

Energy Savers (EERE)

Management Waste Management Oak Ridge has an onsite CERCLA disposal facility, the Environmental Management Waste Management Facility, that reduces cleanup and transportation costs....

270

Municipal Waste Combustion (New Mexico)  

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

This rule establishes requirements for emissions from, and design and operation of, municipal waste combustion units. "Municipal waste"means all materials and substances discarded from residential...

271

Waste Disposal | Department of Energy  

Office of Environmental Management (EM)

Disposal Waste Disposal Trucks transport debris from Oak Ridges cleanup sites to the onsite CERCLA disposal area, the Environmental Management Waste Management Facility....

272

22 - Radioactive waste disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses the disposal of radioactive wastes that arise from a great variety of sources, including the nuclear fuel cycle, beneficial uses of isotopes, and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. The spent fuel is accumulating, awaiting the development of a high-level waste repository. It is anticipated that a multi-barrier system involving packaging and geologic media will provide protection of the public over the centuries. The favored method of disposal is in a mined cavity deep underground. In some countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is done by casks and containers designed to withstand severe accidents. Low-level wastes come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2001-01-01T23:59:59.000Z

273

Radioactive waste disposal package  

DOE Patents (OSTI)

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.

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

274

Nuclear waste solutions  

DOE Patents (OSTI)

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.

Walker, Darrel D. (1684 Partridge Dr., Aiken, SC 29801); Ebra, Martha A. (129 Hasty Rd., Aiken, SC 29801)

1987-01-01T23:59:59.000Z

275

Radioactive waste storage issues  

SciTech Connect

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.

Kunz, D.E.

1994-08-15T23:59:59.000Z

276

Pioneering Nuclear Waste Disposal  

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

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 DOE 1980. Final Environmental Impact Statement, Waste Isolation Pilot Plant. DOE/EIS-0026, Washington, DC, Office of Environmental Management, U.S. Department of Energy. DOE 1981. Waste Isolation Pilot Plant (WIPP): Record of Decision. Federal Register, Vol. 46, No. 18, p. 9162, (46 Federal Register 9162), January 28, 1981. U.S. Department of Energy. DOE 1990. Final Supplement Environmental Impact Statement, Waste Isolation Pilot Plant. DOE/EIS-0026-FS, Washington, DC, Office of Environmental Management, U.S. Department of Energy. DOE 1990. Record of Decision: Waste Isolation Pilot Plant. Federal Register, Vol. 55, No. 121, 25689-25692, U.S. Department of Energy. DOE 1994. Comparative Study of Waste Isolation Pilot Plant (WIPP) Transportation Alternatives.

277

Salt Waste Processing Initiatives  

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

Patricia Suggs Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives 2 Overview * Current SRS Liquid Waste System status * Opportunity to accelerate salt processing - transformational technologies - Rotary Microfiltration (RMF) and Small Column Ion Exchange (SCIX) - Actinide Removal Process/Modular Caustic Side Solvent Extraction (ARP/MCU) extension with next generation extractant - Salt Waste Processing Facility (SWPF) performance enhancement - Saltstone enhancements * Life-cycle impacts and benefits 3 SRS Liquid Waste Total Volume >37 Million Gallons (Mgal) Total Curies 183 MCi (51% ) 175 MCi (49% ) >358 Million Curies (MCi) Sludge 34.3 Mgal (92% ) 3.0 Mgal (8%)

278

HLW Glass Waste Loadings  

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

HLW HLW Glass Waste Loadings Ian L. Pegg Vitreous State Laboratory The Catholic University of America Washington, DC Overview Overview  Vitrification - general background  Joule heated ceramic melter (JHCM) technology  Factors affecting waste loadings  Waste loading requirements and projections  WTP DWPF  DWPF  Yucca Mountain License Application requirements on waste loading  Summary Vitrification  Immobilization of waste by conversion into a glass  Internationally accepted treatment for HLW  Why glass?  Amorphous material - able to incorporate a wide spectrum of elements over wide ranges of composition; resistant to radiation damage  Long-term durability - natural analogs Relatively simple process - amenable to nuclearization at large  Relatively simple process - amenable to nuclearization at large scale  There

279

Stailization, Packaging, and Storage of Plutonium-Bearing Materials  

Energy.gov (U.S. Department of Energy (DOE)) 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 of plutonium- bearing metals and oxides containing at least 30 wt% plutonium plus uranium. It supersedes DOE-STD-3013-2004, "Stabilization, Packaging, and Storage of Plutonium-Bearing Materials," and is approved for use by all DOE organizations and their contractors. Metals are stabilized by

280

Levitation pressure and friction losses in superconducting bearings  

DOE Patents (OSTI)

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.

Hull, John R. (Downers Grove, IL)

2001-01-01T23:59:59.000Z

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


281

Seismic base isolation: Elastomer characterization, bearing modeling and system response  

SciTech Connect

This paper discusses several major aspects of seismic base isolation systems that employ laminated elastomer bearings. Elastomer constitutive models currently being used to represent the nonlinear elastic and hysteretic behavior are discussed. Some aspects of mechanical characterization testing of elastomers is presented along with representative tests results. The development of a finite element based mesh generator for laminated elastomer bearings is presented. Recent advances in the simulation of base isolated structures to earthquake motions are presented along with a sample problem. 13 refs., 19 figs., 1 tab.

Kulak, R.F.; Wang, C.Y.; Hughes, T.H.

1991-01-01T23:59:59.000Z

282

Rotordynamic evaluation of a roughened-land hybrid bearing  

E-Print Network (OSTI)

in 0. 123 in 0. 177 in 30. 9% 990 3. Test Facility Description All the experiments were conducted in the Turbomachinery Laboratory at Texas A&M University, using the Hybrid-Bearing Test Facility funded by Rocketdyne, NASA, and the Texas Advanced... in 0. 123 in 0. 177 in 30. 9% 990 3. Test Facility Description All the experiments were conducted in the Turbomachinery Laboratory at Texas A&M University, using the Hybrid-Bearing Test Facility funded by Rocketdyne, NASA, and the Texas Advanced...

Fayolle, Patrice Gerard

2012-06-07T23:59:59.000Z

283

Notes 06. Liquid cavitation in fluid film bearings  

E-Print Network (OSTI)

[s] U ?R. Journal surface speed [m/s] V dh/dt. Squeeze film velocity [m/s] X= ?R, y, z Coordinate system on plane of bearing ? ()/ cav ?? . Density ratio ? P ? ? ? ? . Liquid bulk-modulus [N/m 2 ] ? Liquid density [kg/m 3 ] cav... ? Density at Pcav [kg/m 3 ] ? Fluid absolute viscosity [N.s/m 2 ] ? Journal angular speed (rad/s) Subscripts * Inception of the cavitation zone a Ambient value cav Cavitation NOTES 6. CAVITATION IN LIQUID FILM BEARINGS. Dr. Luis San Andr?s ? 2009...

San Andres, Luis

2009-01-01T23:59:59.000Z

284

Aluminum Waste Reaction Indicators in a Municipal Solid Waste Landfill  

E-Print Network (OSTI)

Aluminum Waste Reaction Indicators in a Municipal Solid Waste Landfill Timothy D. Stark, F.ASCE1 landfills may contain aluminum from residential and commercial solid waste, industrial waste, and aluminum, may react with liquid in a landfill and cause uncontrolled temperature increases, significant changes

285

The development of a bearing spectral analyzer and algorithms to detect turbopump bearing wear from deflectometer and strain gage data  

SciTech Connect

Over the last several years, Rocketdyne has actively developed condition and health monitoring techniques and their elements for rocket engine components, specifically high pressure turbopumps. Of key interest is the development of bearing signature analysis systems for real-time monitoring of the cryogen-cooled turbopump shaft bearings, which spin at speeds up to 36,000 RPM. These system elements include advanced bearing vibration sensors, signal processing techniques, wear mode algorithms, and integrated control software. Results of development efforts in the areas of signal processing and wear mode identification and quantification algorithms based on strain gage and deflectometer data are presented. Wear modes investigated include: inner race wear, cage pocket wear, outer race wear, differential ball wear, cracked inner race, and nominal wear. 4 refs.

Martinez, C.L. (Rockwell International Corp., Rocketdyne Div., Canoga Park, CA (United States))

1992-07-01T23:59:59.000Z

286

Quality Services: Solid Wastes, Part 360: Solid Waste Management Facilities  

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

0: Solid Waste Management 0: Solid Waste Management Facilities (New York) Quality Services: Solid Wastes, Part 360: Solid Waste Management Facilities (New York) < Back Eligibility Agricultural Commercial Fuel Distributor Industrial Institutional Investor-Owned Utility Multi-Family Residential Municipal/Public Utility Rural Electric Cooperative Transportation Utility Program Info State New York Program Type Environmental Regulations Provider NY Department of Environmental Conservation These regulations apply to all solid wastes with the exception of hazardous or radioactive waste. Proposed solid waste processing facilities are required to obtain permits prior to construction, and the regulations provide details about permitting, construction, registration, and operation requirements. The regulations contain specific guidance for land

287

TRU Waste Sampling Program: Volume I. Waste characterization  

SciTech Connect

Volume I of the TRU Waste Sampling Program report presents the waste characterization information obtained from sampling and characterizing various aged transuranic waste retrieved from storage at the Idaho National Engineering Laboratory and the Los Alamos National Laboratory. The data contained in this report include the results of gas sampling and gas generation, radiographic examinations, waste visual examination results, and waste compliance with the Waste Isolation Pilot Plant-Waste Acceptance Criteria (WIPP-WAC). A separate report, Volume II, contains data from the gas generation studies.

Clements, T.L. Jr.; Kudera, D.E.

1985-09-01T23:59:59.000Z

288

Hanford Tank Waste Residuals  

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

Hanford 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 gallons of waste* - 149 SSTs located in 12 SST Farms - Grouped into 7 Waste Management Areas (WMAs) for RCRA closure purposes: 200 West Area S/SX T TX/TY U 200 East Area A/AX B/BX/BY C * Double-Shell Tanks (DSTs) - ~26 million gallons of waste* - 28 DSTs located in 6 DST Farms (1 West/5 East) * 17 Misc Underground Storage Tanks (MUST) * 43 Inactive MUST (IMUST) 200 East Area A/AX B/BX/BY C * Volumes fluctuate as SST retrievals and 242-A Evaporator runs occur. Major Regulatory Drivers * Radioactive Tank Waste Materials - Atomic Energy Act - DOE M 435.1-1, Ch II, HLW - Other DOE Orders * Hazardous/Dangerous Tank Wastes - Hanford Federal Facility Agreement and Consent Order (TPA) - Retrieval/Closure under State's implementation

289

Waste inspection tomography (WIT)  

SciTech Connect

The WIT program will provide an inspection system that offers the nuclear waste evaluator a unique combination of tools for regulatory-driven characterization of low-level waste (LLW), transuranic waste (TRU), and mixed waste drums. WIT provides nondestructive, noninvasive, and environmentally safe inspections using X-ray and gamma ray technologies, with reasonable cost and throughput. Two emission imaging techniques will be employed for characterizing materials in waste containers. The first of these is gamma emission tomography, commonly called single-photon emission computed tomography (SPECT). Rather than using an external radiation source, SPECT uses the emission of radioactive materials within the object of interest for imaging. In this case, emission from actual nuclear waste within a container will provide a three-dimensional image of the radioactive substances in the container. The second emission technique will use high-purity germanium detectors for gamma ray spectroscopy. This technique, called nondestructive assay (NDA), can identify the emitting isotopic species and strength. Work in emission tomography and assay of nuclear waste has been undertaken at Lawrence Livermore National Laboratory using a technique called Passive Tomography. Results from a process development unit are presented.

Bernardi, R.T.; Han, K.S.

1994-12-31T23:59:59.000Z

290

Radioactive waste material disposal  

DOE Patents (OSTI)

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.

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

1995-10-24T23:59:59.000Z

291

Radioactive waste material disposal  

DOE Patents (OSTI)

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.

Forsberg, Charles W. (155 Newport Dr., Oak Ridge, TN 37830); Beahm, Edward C. (106 Cooper Cir., Oak Ridge, TN 37830); Parker, George W. (321 Dominion Cir., Knoxville, TN 37922)

1995-01-01T23:59:59.000Z

292

Hazardous Waste Disposal Sites (Iowa)  

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

These sections contain information on fees and monitoring relevant to operators of hazardous waste disposal sites.

293

Generating power with waste wood  

SciTech Connect

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.

Atkins, R.S.

1995-02-01T23:59:59.000Z

294

Methane generation from waste materials  

DOE Patents (OSTI)

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.

Samani, Zohrab A. (Las Cruces, NM); Hanson, Adrian T. (Las Cruces, NM); Macias-Corral, Maritza (Las Cruces, NM)

2010-03-23T23:59:59.000Z

295

Certification Plan, low-level waste Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met.

Albert, R.

1992-06-30T23:59:59.000Z

296

Force and Stiffness of Passive Magnetic Bearings Using Permanent Magnets.  

E-Print Network (OSTI)

1 Force and Stiffness of Passive Magnetic Bearings Using Permanent Magnets. Part 2 : Radial Magnetization R. Ravaud, G. Lemarquand, V. Lemarquand Abstract This paper deals with the calculation of the force and the stiffness between two ring permanent magnets whose polarization is radial

Boyer, Edmond

297

Optimization of superconducting tiling pattern for superconducting bearings  

DOE Patents (OSTI)

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.

Hull, J.R.

1996-09-17T23:59:59.000Z

298

Rotordynamic evaluation of a tangential-injection hybrid bearing  

E-Print Network (OSTI)

, and Cre = 0.001 . Data are presented for 550C water at three speeds out to 25000 rpm and three pressures out to 7.0 MPa. Compared to a radial-injection hybrid bearing, experiments show injection against rotation enhances stability, yielding reductions...

Laurant, Franck Jean

1998-01-01T23:59:59.000Z

299

Standards opportunities around data-bearing Web pages  

Science Journals Connector (OSTI)

...Articles 1003 182 Discussion Meeting Issue Web science: a new frontier organized and edited...Standards opportunities around data-bearing Web pages David Karger e-mail: karger@mit...contribution of 15 to a Discussion Meeting Issue Web science: a new frontier . The evolving...

2013-01-01T23:59:59.000Z

300

Do bears facilitate transfer of salmon resources to aquatic macroinvertebrates?  

E-Print Network (OSTI)

- tigated whether foraging activities of bears facilitate growth of stream invertebrates by increasing scavengers are likely highly patchy in time and space. Résumé : Dans les régions côtières pacifiques du nord

Palen, Wendy J.

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


301

Optimization of superconducting tiling pattern for superconducting bearings  

DOE Patents (OSTI)

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.

Hull, John R. (Hinsdale, IL)

1996-01-01T23:59:59.000Z

302

Correspondence Laboratory observations of debris-bearing ice facies frozen  

E-Print Network (OSTI)

, others argue that supercooling is not the only mechanism for producing thick basal ice sequencesCorrespondence Laboratory observations of debris-bearing ice facies frozen from supercooled water. Supercooling has been invoked to explain anomalously thick basal ice sequences beneath temperate glaciers

Knight, Peter G.

303

PRESSURE DEVELOPMENT IN SEALED CONTAINERS WITH PLUTONIUM BEARING MATERIALS  

SciTech Connect

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.

Duffey, J.; Livingston, R.

2010-02-01T23:59:59.000Z

304

Spectroscopic Evidence for Uranium Bearing Precipitates in Vadose Zone  

E-Print Network (OSTI)

Spectroscopic Evidence for Uranium Bearing Precipitates in Vadose Zone Sediments at the Hanford 300, Advanced Light Source, One Cyclotron Road, Berkeley, California 94720, United States Geological Survey Northwest Laboratory, Richland, Washington 99352 Uranium (U) solid-state speciation in vadose zone sediments

305

The Energy Expenditure of Rats Bearing Walker Carcinoma 256  

Science Journals Connector (OSTI)

...the law of conservation of energy holds true for the animal body...010 0.010 0.100 731 The Energy Expenditure of Rats Bearing...product which is difficult to mix. Samples to be burned were...nitro.. Mmir@iiet al. "Energy Expenditure of Tumorous Rats...

G. B. Mider; L. D. Fenninger; F. L. Haven; and J. J. Morton

1951-09-01T23:59:59.000Z

306

Tank Waste Strategy Update  

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

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 December 5, 2011 Background Tank Waste Subcommittee (TWS)originally chartered, in response to Secretary's request to perform a technical review of Waste Treatment and Immobilization Plant (WTP) in May 2010. Three tasks: o Verification of closure of WTP External Flowsheet Review Team (EFRT) issues. o WTP Technical Design Review o WTP potential improvements Report completed and briefed to DOE in September 2010 www.em.doe.gov safety performance cleanup closure E M Environmental Management 2 Report completed and briefed to DOE in September 2010 Follow-on scope for TWS identified immediately after briefing to DOE and

307

Waste Treatment Plant Overview  

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

Hanford Site, located in southeastern Washington state, Hanford Site, located in southeastern Washington state, was the largest of three defense production sites in the U.S. Over the span of 40 years, it was used to produce 64 metric tons of plutonium, helping end World War II and playing a major role in military defense efforts during the Cold War. As a result, 56 million gallons of radioactive and chemical wastes are now stored in 177 underground tanks on the Hanford Site. To address this challenge, the U.S. Department of Energy contracted Bechtel National, Inc., to design and build the world's largest radioactive waste treatment plant. The Waste Treatment and Immobilization Plant (WTP), also known as the "Vit Plant," will use vitrification to immobilize most of Hanford's dangerous tank waste.

308

Waste Steam Recovery  

E-Print Network (OSTI)

An examination has been made of the recovery of waste steam by three techniques: direct heat exchange to process, mechanical compression, and thermocompression. Near atmospheric steam sources were considered, but the techniques developed are equally...

Kleinfeld, J. M.

1979-01-01T23:59:59.000Z

309

Waste and Recycling  

ScienceCinema (OSTI)

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.

McCarthy, Kathy

2013-05-28T23:59:59.000Z

310

Citrus Waste Biomass Program  

SciTech Connect

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.

Karel Grohman; Scott Stevenson

2007-01-30T23:59:59.000Z

311

Beijing Jingye Bearing Manufacture for Rolling Mills Co Ltd | Open Energy  

Open Energy Info (EERE)

Jingye Bearing Manufacture for Rolling Mills Co Ltd Jingye Bearing Manufacture for Rolling Mills Co Ltd Jump to: navigation, search Name Beijing Jingye Bearing Manufacture for Rolling Mills Co Ltd Place Beijing Municipality, China Sector Wind energy Product Beijing-based wind turbine bearing maker. References Beijing Jingye Bearing Manufacture for Rolling Mills Co Ltd[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Beijing Jingye Bearing Manufacture for Rolling Mills Co Ltd is a company located in Beijing Municipality, China . References ↑ "Beijing Jingye Bearing Manufacture for Rolling Mills Co Ltd" Retrieved from "http://en.openei.org/w/index.php?title=Beijing_Jingye_Bearing_Manufacture_for_Rolling_Mills_Co_Ltd&oldid=342621

312

Analysis of electrical signatures in synchronous generators characterized by bearing faults  

E-Print Network (OSTI)

Synchronous generators play a vital role in power systems. One of the major mechanical faults in synchronous generators is related to bearings. The popular vibration analysis method has been utilized to detect bearing faults for years. However...

Choi, Jae-Won

2009-05-15T23:59:59.000Z

313

E-Print Network 3.0 - aluminium-based journal bearing Sample...  

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

of the microbearing system lies in a small journal-bearing... system drag (journal plus thrust bear- ings). The design output power of this turbine is on the order... , the...

314

Bearing options, including design and testing, for direct drive linear generators in wave energy converters  

E-Print Network (OSTI)

The key focus of this research was to investigate the bearing options most suited to operation in a novel direct drive linear generator. This was done through bearing comparisons, modelling and testing. It is fundamental ...

Caraher, Sarah

2011-11-22T23:59:59.000Z

315

E-Print Network 3.0 - alumina-on-polyethylene bearing surfaces...  

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

on-polyethylene bearing surfaces Search Powered by Explorit Topic List Advanced Search Sample search results for: alumina-on-polyethylene bearing surfaces Page: << < 1 2 3 4 5 > >>...

316

A Novel Computational Model for Tilting Pad Journal Bearings with Soft Pivot Stiffnesses  

E-Print Network (OSTI)

A novel tilting pad journal bearing model including pivot flexibility as well as temporal fluid inertia effects on the thin film fluid flow aims to accurately predict the bearing forced performance. The predictive model also accounts for the thermal...

Tao, Yujiao 1988-

2012-12-10T23:59:59.000Z

317

Test-Theory Correlation Study for an Ultra High Temperature Thrust Magnetic Bearing  

E-Print Network (OSTI)

Magnetic bearings have been researched by the National Aeronautics and Space Administration (NASA) for a very long time to be used in wide applications. This research was to assemble and test an axial thrust electromagnetic bearing, which can handle...

Desireddy, Vijesh R.

2010-01-14T23:59:59.000Z

318

Effect of Cooling Flow on the Operation of a Hot Rotor-Gas Foil Bearing System  

E-Print Network (OSTI)

Gas foil bearings (GFBs) operating at high temperature rely on thermal management procedures that supply needed cooling flow streams to keep the bearing and rotor from overheating. Poor thermal management not only makes systems inefficient...

Ryu, Keun

2012-02-14T23:59:59.000Z

319

-Omics and Cancer Biomarkers: Link to the Biological Truth or Bear the Consequences  

Science Journals Connector (OSTI)

...Link to the Biological Truth or Bear the Consequences Lance A. Liotta Emanuel...prediction can change as a consequence of cellular hypoxia, acidosis...link to the biological truth or bear the consequences. | Editorial

Lance A. Liotta and Emanuel F. Petricoin III

2012-08-01T23:59:59.000Z

320

Advances in hybrid water-lubricated journal bearings for use in ocean vessels  

E-Print Network (OSTI)

The outboard bearings that support shafts in naval ships and submarines present unique challenges to designers, shipbuilders, and operators. Such bearings must operate continuously and reliably in demanding environments ...

Heberley, Brian Douglas

2013-01-01T23:59:59.000Z

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


321

Dynamics of a parallel, high-speed, lubricated thrust bearing with Navier slip boundary conditions  

Science Journals Connector (OSTI)

......and slip bearings is in the development of fluid stiffness and the minimum...carried out at the University Technology Centre in Gas Turbine Transmission Systems at the...and stability of self-acting gas journal bearings. J. Tribol......

N.Y. Bailey; K.A. Cliffe; S. Hibberd; H. Power

2014-12-01T23:59:59.000Z

322

Independent Activity Report, Hanford Waste Treatment Plant -...  

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

Waste Treatment Plant - February 2011 Independent Activity Report, Hanford Waste Treatment Plant - February 2011 February 2011 Hanford Waste Treatment Plant Construction Quality...

323

Rhenium solubility in borosilicate nuclear waste glass  

E-Print Network (OSTI)

Glasses Developed for Nuclear Waste Immobilization," 91[12],solubility in borosilicate nuclear waste glass Ashutoshfor the researchers in nuclear waste community around the

McCloy, John S.

2014-01-01T23:59:59.000Z

324

Enterprise Assessments Operational Awareness Record, Waste Treatment...  

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

Observation of Waste Treatment and Immobilization Plant High Level Waste Facility Radioactive Liquid Waste Disposal System Hazards Analysis Activities (EA-WTP-HLW-2014-08-18(a))...

325

Municipal Solid Waste | Open Energy Information  

Open Energy Info (EERE)

Waste Jump to: navigation, search TODO: Add description List of Municipal Solid Waste Incentives Retrieved from "http:en.openei.orgwindex.php?titleMunicipalSolidWaste&oldid...

326

Waste Processing Annual Technology Development Report 2007 |...  

Office of Environmental Management (EM)

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

327

Pollution Prevention, Waste Reduction, and Recycling | Department...  

Office of Environmental Management (EM)

Pollution Prevention, Waste Reduction, and Recycling Pollution Prevention, Waste Reduction, and Recycling The Pollution Prevention, Waste Reduction and Recycling Program was...

328

Waste Isolation Pilot Plant | Department of Energy  

Office of Environmental Management (EM)

Waste Isolation Pilot Plant Waste Isolation Pilot Plant Operators prepare drums of contact-handled transuranic waste for loading into transportation containers Operators prepare...

329

Measurements versus Predictions for a Hybrid (Hydrostatic plus Hydrodynamic Thrust Bearing for a Range of Orifice Diameters  

E-Print Network (OSTI)

A fixed geometry hybrid thrust bearing is investigated with three different supply orifice diameters. The test rig uses a face-to-face thrust bearing design, with the test bearing acting as the rotor loading mechanism. A hydraulic shaker applies...

Esser, Paul R.

2011-08-08T23:59:59.000Z

330

Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)  

Open Energy Info (EERE)

Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) No revision has been approved for this page. It is currently under review by our subject matter experts. Jump to: navigation, search Last modified on February 13, 2013. EZFeed Policy Place Pennsylvania Name Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Policy Category Other Policy Policy Type Environmental Regulations Affected Technologies Biomass/Biogas, Coal with CCS, Concentrating Solar Power, Energy Storage, Fuel Cells, Geothermal Electric, Hydroelectric, Hydroelectric (Small), Natural Gas, Nuclear, Solar Photovoltaics, Wind energy Active Policy Yes Implementing Sector State/Province Program Administrator Pennsylvania Department of Environmental Protection

331

Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)  

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

Municipal Waste Planning, Recycling and Waste Reduction Act Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Pennsylvania Program Type Environmental Regulations

332

SECONDARY WASTE MANAGEMENT STRATEGY FOR EARLY LOW ACTIVITY WASTE TREATMENT  

SciTech Connect

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.

CRAWFORD TW

2008-07-17T23:59:59.000Z

333

Energy from waste via coal/waste co-firing  

SciTech Connect

The paper reviews the feasibility of waste-to-energy plants using the cocombustion of coal with refuse-derived fuels. The paper discusses the types of wastes available: municipal solid wastes, plastics, tires, biomass, and specialized industrial wastes, such as waste oils, post-consumer carpet, auto shredder residues, and petroleum coke. The five most common combustion systems used in co-firing are briefly described. They are the stoker boiler, suspension-fired boilers, cyclone furnaces, fluidized bed boilers, and cement kilns. The paper also discusses the economic incentives for generating electricity from waste.

Winslow, J.; Ekmann, J.; Smouse, S. [Dept. of Energy, Pittsburgh, PA (United States). Pittsburgh Energy Technology Center; Ramezan, M. [Burns and Roe Services Corp., Pittsburgh, PA (United States); Harding, S.

1996-12-31T23:59:59.000Z

334

Solid Waste and Infectious Waste Regulations (Ohio) | Department of Energy  

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

and Infectious Waste Regulations (Ohio) and Infectious Waste Regulations (Ohio) Solid Waste and Infectious Waste Regulations (Ohio) < Back Eligibility Utility Agricultural Investor-Owned Utility Industrial Municipal/Public Utility Local Government Rural Electric Cooperative Program Info State Ohio Program Type Environmental Regulations Provider Ohio Environmental Protection Agency This chapter of the law that establishes the Ohio Environmental Protection Agency establishes the rules and regulations regarding solid waste. The chapter establishes specific regulations for biomass facilities, which includes permitting, siting, operation, safety guidelines, and closing requirements. Siting regulations include setbacks from waste handling areas for state facilities (1000 feet from jails, schools), requirements for not siting

335

A simplified thermohydrodynamic model for fluid film bearings. Final report, February 15, 1992--February 15, 1994  

SciTech Connect

We aim to develop a simplified yet realistic model of fluid film lubrication under thermohydrodynamic conditions, with significant thermal and elastic deformation of the bearing pads. The principal thrust is transfer of technology from the researcher to the industrial designer: the end product will include two user-friendly computer programs, one for journal bearings and the other for thrust bearings, to be used for bearing design in interactive mode on a personal computer.

Szeri, A.Z. [Pittsburgh Univ., PA (United States). Dept. of Mechanical Engineering

1994-03-01T23:59:59.000Z

336

LANL reaches waste shipment milestone  

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

LANL reaches waste shipment milestone 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 Communicatons Office (505) 665-3430 Email LOS ALAMOS, New Mexico, May 31, 2011 - Los Alamos National Laboratory has reached an important milestone in its campaign to ship transuranic (TRU) waste from Cold War-era nuclear operations to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This month, the Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total.

337

The largest radioactive waste glassification  

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

largest radioactive waste glassification largest radioactive waste glassification plant in the nation, the Defense Waste Processing Facility (DWPF) converts the liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for treating liquid nuclear waste. By immobilizing the radioactivity in glass, the DWPF reduces the risks associated with the continued storage of liquid nuclear waste at SRS and prepares the waste for final disposal in a federal repository. About 38 million gallons of liquid nuclear wastes are now stored in 49 underground carbon-steel tanks at SRS. This waste has about 300 million curies of radioactivity, of which the vast majority

338

Waste Treatment Plant - 12508  

SciTech Connect

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-ion exchange columns, evaporator boilers and recirculation pumps, and various mechanical process pumps for transferring process fluids. During the first phase of pretreatment, the waste will be concentrated using an evaporation process. Solids will be filtered out, and the remaining soluble, highly radioactive isotopes will be removed using an ion-exchange process. The high-level solids will be sent to the High-Level Waste (HLW) Vitrification Facility, and the low activity liquids will be sent to the Low-Activity Waste (LAW) Vitrification Facility for further processing. The high-level waste will be transferred via underground pipes to the HLW Facility from the Pretreatment Facility. The waste first arrives at the wet cell, which rests inside a black-cell area. The pretreated waste is transferred through shielded pipes into a series of melter preparation and feed vessels before reaching the melters. Liquids from various facility processes also return to the wet cell for interim storage before recycling back to the Pretreatment Facility. (authors)

Harp, Benton; Olds, Erik [US DOE (United States)

2012-07-01T23:59:59.000Z

339

Mixed waste characterization reference document  

SciTech Connect

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.

NONE

1997-09-01T23:59:59.000Z

340

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

SciTech Connect

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.

Losinski, Sylvester John; Marshall, Douglas William

2002-08-01T23:59:59.000Z

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


341

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

SciTech Connect

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.

Moline, G.R. [Oak Ridge National Lab., TN (United States). Environmental Sciences Div.; Schreiber, M.E. [Univ. of Wisconsin, Madison, WI (United States). Dept. of Geology and Geophysics

1996-03-01T23:59:59.000Z

342

ME 379M Lubrication, Wear, and Bearing Technology ABET EC2000 syllabus  

E-Print Network (OSTI)

ME 379M � Lubrication, Wear, and Bearing Technology Page 1 ABET EC2000 syllabus ME 379M � Lubrication, Wear, and Bearing Technology Spring 2010 Required or Elective: Elective 2008-2010 Catalog Data: Topics may vary: Lubrication, Wear, and Bearing Technology Prerequisite(s): Admission to the Major

Ben-Yakar, Adela

343

Bearing Fault Detection in DFIG-Based Wind Turbines Using the First Intrinsic Mode Function  

E-Print Network (OSTI)

Bearing Fault Detection in DFIG-Based Wind Turbines Using the First Intrinsic Mode Function Y for bearing fault detection in DFIG-based wind turbines. The proposed method uses the first Intrinsic Mode Terms--Wind turbine, Doubly Fed Induction Generator (DFIG), fault detection, bearings, signal processing

Boyer, Edmond

344

Hazardous Waste/Mixed Waste Treatment Building throughput study  

SciTech Connect

The hazardous waste/mixed waste HW/MW Treatment Building (TB) is the specified treatment location for solid hazardous waste/mixed waste at SRS. This report provides throughput information on the facility based on known and projected waste generation rates. The HW/MW TB will have an annual waste input for the first four years of approximately 38,000 ft{sup 3} and have an annual treated waste output of approximately 50,000 ft{sup 3}. After the first four years of operation it will have an annual waste input of approximately 16,000 ft{sup 3} and an annual waste output of approximately 18,000 ft. There are several waste streams that cannot be accurately predicted (e.g. environmental restoration, decommissioning, and decontamination). The equipment and process area sizing for the initial four years should allow excess processing capability for these poorly defined waste streams. A treatment process description and process flow of the waste is included to aid in understanding the computations of the throughput. A description of the treated wastes is also included.

England, J.L.; Kanzleiter, J.P.

1991-12-18T23:59:59.000Z

345

Preliminary relative permeability estimates of methanehydrate-bearing sand  

SciTech Connect

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.

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

2006-05-08T23:59:59.000Z

346

Structural durability validation of bearing girders in marine Diesel engines  

Science Journals Connector (OSTI)

The aim is to present the state-of-the-art methodology for structural durability evaluation of marine Diesel engines bearing girders and to describe the responsibility of engine designers, manufacturers and system suppliers. A real example of several engines of the same type, where fatigue cracks arose in certain areas of their bearing girders, has been presented. The extensive investigation revealed the cause of the damage. The proper design was proved by properly implemented state-of-the-art design methods and by experimental verification of calculations in two ships. Quality and test specifications prescribed by the licensor have been found correct. It is concluded that the damage cause was the impermissible quality of worldwide manufacture and improper production repair welding during manufacture.

Vatroslav Grubii?; Nenad Vuli?; Samuel Snnichsen

2008-01-01T23:59:59.000Z

347

Disturbance Rejection Control of an Electromagnetic Bearing Spindle  

SciTech Connect

The force exerted on the rotor by an active magnetic bearing (AMB) is determined by the current flow in the magnet coils. This force can be controlled very precisely, making magnetic bearings a potential benefit for grinding, where cutting forces act as external disturbances on the shaft, resulting in degraded part finish. It is possible to achieve precise shaft positioning, reduce vibration of the shaft caused by external disturbances, and even damp out resonant modes. Adaptive control is an appealing approach for these systems because the controller can tune itself to account for an unknown periodic disturbance, such as cutting or grinding forces, injected into the system. In this paper the authors show how one adaptive control algorithm can be applied to an AMB system with a periodic disturbance applied to the rotor. An adaptive algorithm was developed and implemented in both simulation and hardware, yielding significant reductions in rotor displacement in the presence of an external excitation. Ultimately, this type of algorithm could be applied to a magnetic bearing grinder to reduce unwanted motion of the spindle which leads to poor part finish and chatter.

PETTEYS,REBECCA; PARKER,GORDON

2000-08-31T23:59:59.000Z

348

Waste generator services implementation plan  

SciTech Connect

Recurring waste management noncompliance problems have spurred a fundamental site-wide process revision to characterize and disposition wastes at the Idaho National Engineering and Environmental Laboratory. The reengineered method, termed Waste Generator Services, will streamline the waste acceptance process and provide waste generators comprehensive waste management services through a single, accountable organization to manage and disposition wastes in a timely, cost-effective, and compliant manner. This report outlines the strategy for implementing Waste Generator Services across the INEEL. It documents the culmination of efforts worked by the LMITCO Environmental Management Compliance Reengineering project team since October 1997. These efforts have included defining problems associated with the INEEL waste management process; identifying commercial best management practices; completing a review of DOE Complex-wide waste management training requirements; and involving others through an Integrated Process Team approach to provide recommendations on process flow, funding/charging mechanisms, and WGS organization. The report defines the work that will be performed by Waste Generator Services, the organization and resources, the waste acceptance process flow, the funding approach, methods for measuring performance, and the implementation schedule and approach. Field deployment will occur first at the Idaho Chemical Processing Plant in June 1998. Beginning in Fiscal Year 1999, Waste Generator Services will be deployed at the other major INEEL facilities in a phased approach, with implementation completed by March 1999.

Mousseau, J.; Magleby, M.; Litus, M.

1998-04-01T23:59:59.000Z

349

Transuranic Waste Tabletop  

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

Transuranic (TRU) Waste Transuranic (TRU) Waste (Hazard Class 7 Radioactive) Moderator's Version of Tabletop Prepared for the Department of Energy Office of Transportation and Emergency Management 02B00215-07D.p65 This page intentionally left blank table of contents Transportation Emergency Preparedness Program (TEPP) planning tools planning tools planning tools planning tools T T T T Tr r r r ransur ansur ansur ansur ansuranic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) Waste aste aste aste aste (Hazar (Hazar (Hazar (Hazar (Hazard Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radioactiv activ activ activ active) e) e) e) e) Moder Moder Moder Moder Moderat at at at ator' or' or' or' or's V s V s V s V s Version of T ersion of T ersion of T ersion of T ersion of Tablet ablet ablet ablet abletop

350

Pioneering Nuclear Waste Disposal  

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

2 2 3 T he journey to the WIPP began nearly 60 years before the first barrels of transuranic waste arrived at the repository. The United States produced the world's first sig- nificant quantities of transuranic material during the Manhattan Project of World War II in the early 1940s. The government idled its plutonium- producing reactors and warhead manu- facturing plants at the end of the Cold War and scheduled most of them for dismantlement. However, the DOE will generate more transuranic waste as it cleans up these former nuclear weapons facilities. The WIPP is a cor- nerstone of the effort to clean up these facilities by providing a safe repository to isolate transuranic waste in disposal rooms mined out of ancient salt beds, located 2,150 feet below ground. The need for the WIPP

351

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

SciTech Connect

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.

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

2014-12-01T23:59:59.000Z

352

FROM WASTE TO WORTH: THE ROLE OF WASTE DIVERSION IN  

E-Print Network (OSTI)

;Canadian Energy-From-Waste Coalition (CEFWC) 1 There is considerable merit to the ideas outlined commitment to foster a green and sustainable economy. The Canadian Energy-From-Waste Coalition (CEFWC sign that the system is failing. #12;Canadian Energy-From-Waste Coalition (CEFWC) 2 Like you, the CEFWC

Columbia University

353

Waste IncIneratIon and Waste PreventIon  

E-Print Network (OSTI)

disposing of waste, it also makes consider- able amounts of energy available in the form of electricity emissions annu- ally. About 50 percent of the energy contained in residual municipal waste comes from- sions from the fossil waste fraction and the fos- sil energy purchased from external sources

354

Skutterudite Thermoelectric Generator For Automotive Waste Heat...  

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

Skutterudite Thermoelectric Generator For Automotive Waste Heat Recovery Skutterudite Thermoelectric Generator For Automotive Waste Heat Recovery Skutterudite TE modules were...

355

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...

356

High-Level Waste Requirements  

Directives, Delegations, and Requirements

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.

1999-07-09T23:59:59.000Z

357

Pathology waste includes: Transgenic animals.  

E-Print Network (OSTI)

resistant, have tight fitting covers, be clean, and in good repair. · Pathology waste must be transferred via the Internet: · Visit www.ehs.uci.edu/programs/enviro/. · Fill out the "Biomedical Waste

George, Steven C.

358

Waste Management Coordinating Lead Authors  

E-Print Network (OSTI)

-use and recycling ..............602 10.4.6 Wastewater and sludge treatment.....................602 10.4.7 Waste ............................................591 10.2.2 Wastewater generation ....................................592 10.2.3 Development trends for waste and ......................... wastewater ......................................................593

Columbia University

359

Leaching of Nuclear Waste Glasses  

Science Journals Connector (OSTI)

Resistance to aqueous corrosion is the most important requirement of glasses designed to immobilize high level radioactive wastes. Obtaining a highly durable nuclear waste glass is complicated by the requirement ...

L. L. Hench

1985-01-01T23:59:59.000Z

360

The Discovery of Nuclear Waste  

Science Journals Connector (OSTI)

When did man discover nuclear waste? To answer this question, we first have to ask if nuclear waste really is something that could be called ... Prize in physics. In early writings within nuclear energy research ...

Gran Sundqvist

2002-01-01T23:59:59.000Z

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


361

Nuclear Waste Disposal Plan Drafted  

Science Journals Connector (OSTI)

Nuclear Waste Disposal Plan Drafted ... Of all the issues haunting nuclear power plants, that of disposing of the radioactive wastes and spent nuclear fuel they generate has been the most vexing. ...

1984-01-09T23:59:59.000Z

362

Hydrothermal Processing of Wet Wastes  

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

Breakout Session 3AConversion Technologies III: Energy from Our WasteWill we Be Rich in Fuel or Knee Deep in Trash by 2025? Hydrothermal Processing of Wet Wastes James R. Oyler, President, Genifuel Corporation

363

Zero Waste, Renewable Energy & Environmental  

E-Print Network (OSTI)

· Dioxins & Furans · The `State of Waste' in the US · WTE Technologies · Thermal Recycling ­ Turnkey dangerous wastes in the form of gases and ash, often creating entirely new hazards, like dioxins and furans

Columbia University

364

Delaware Solid Waste Authority (Delaware)  

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

The Delaware Solid Waste Authority (DSWA) runs three landfills, all of which recover methane and generate electricity with a total capacity of 24 MWs. The DSWA Solid Waste Plan includes goals,...

365

Explosive Waste Treatment Facility  

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

106 106 Environment a 1 Assessment for th.e Explosive Waste Treatment Facility at Site 300 Lawrence Livermore National Laboratory MASTER November 1995 U.S. Department of Energy Office of Environmental Restoration and Waste Management Washington, DOC. 20585 Portions of this document maly be illegible in electronic image products. Images are produced from the best available original document. Table of Contents 1 . 0 2.0 3 . 0 4.0 5 . 0 6.0 7 . 0 8 . 0 Document Summary .............................................................. 1 Purpose and Need for Agency Action ............................................. 3 Description of the Proposed Action and Alternatives ............................ 4 3.1.1 Location ............................................................. 4

366

Waste Isolation Pilot Plant  

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

Waste Isolation Pilot Plant Waste Isolation Pilot Plant AFFIDAVIT FOR SURVIVING RELATIVE STATE _______________ ) ) ss: __________________ COUNTY OF _____________ ) That I, ________________________, am the _________________________ (Indicate relationship) of ___________________________, who is deceased and make the attached request pursuant to 10 CFR, Section 1008. That the information contained on the attached request is true and correct to the best of my knowledge and belief, and I am signing this authorization subject to the penalties provided in 18 U.S.C. 1001. ____________________________ SIGNATURE NOTARIZATION: SUBSCRIBED and SWORN to before me this ______day of __________, 20_____

367

Converter waste disposal study  

SciTech Connect

The importance of waste management and disposal issues to the converting and print industries is demonstrated by the high response rate to a survey of US and Canadian converters and printers. The 30-item questionnaire measured the impact of reuse, recycling, source reduction, incineration, and landfilling on incoming raw-material packaging, process scrap, and waste inks, coatings, and adhesives. The results indicate that significant amounts of incoming packaging materials are reused in-house or through supplier take-back programs. However, there is very little reuse of excess raw materials and process scrap, suggesting the need for greater source reduction within these facilities as the regulatory climate becomes increasingly restrictive.

Schultz, R.B. (RBS Technologies, Inc., Skokie, IL (United States))

1993-07-01T23:59:59.000Z

368

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

SciTech Connect

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.

NONE

1998-03-01T23:59:59.000Z

369

WORLDWIDE FOCUS ON NUCLEAR WASTE  

Science Journals Connector (OSTI)

WORLDWIDE FOCUS ON NUCLEAR WASTE ... Volume grows and years pile up, but world lacks consensus on disposing of nuclear waste ... WHAT TO DO WITH SPENT nuclear fuel and high-level radioactive waste is a problem shared by much of the world. ...

JEFF JOHNSON

2001-06-18T23:59:59.000Z

370

RETHINKING WASTE, RECYCLING, AND HOUSEKEEPING  

E-Print Network (OSTI)

RETHINKING WASTE, RECYCLING, AND HOUSEKEEPING EFFICIENCY.EFFICIENCY. A l GA leaner Green #12 t R li Management Recycling Staff The Office of Waste Reduction & Recycling started in The Office of Waste Reduction & Recycling started in 1990, we have 14 full time staff positions. ·We collect over 40

Howitt, Ivan

371

Mixed Waste Working Group report  

SciTech Connect

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.

Not Available

1993-11-09T23:59:59.000Z

372

Waste-to-Energy Workshop  

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

The Waste to Energy Roadmapping Workshop was held on November 5, 2014, in Arlington, Virginia. This workshop gathered waste-to-energy experts to identify the key technical barriers to the commercial deployment of liquid transportation fuels from wet waste feedstocks.

373

Disposal of Nuclear Wastes  

Science Journals Connector (OSTI)

...generated between now and A.D. 2000 is about 0.04 km3 (0.01...high-level wastes do not be-come a public hazard. The AEC adopts this...pre-sented at the 66th national meeting of the American Institute of...ARH-SA-41 (Atlantic Richfield Hanford Co., Richland, Washington...

Arthur S. Kubo; David J. Rose

1973-12-21T23:59:59.000Z

374

Radioactive Waste Management  

Directives, Delegations, and Requirements

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

1999-07-09T23:59:59.000Z

375

D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE  

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

10 CFR Ch. X (1-1-12 Edition) Pt. 1022 D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE Siting, construction or expansion, and op- eration of disposal facilities for transuranic (TRU) waste and TRU mixed waste (TRU waste also containing hazardous waste as designated in 40 CFR part 261). D12 INCINERATORS Siting, construction, and operation of in- cinerators, other than research and develop- ment incinerators or incinerators for non- hazardous solid waste (as designated in 40 CFR 261.4(b)). PART 1022-COMPLIANCE WITH FLOODPLAIN AND WETLAND EN- VIRONMENTAL REVIEW REQUIRE- MENTS Subpart A-General Sec. 1022.1 Background. 1022.2 Purpose and scope. 1022.3 Policy. 1022.4 Definitions. 1022.5 Applicability. 1022.6 Public inquiries. Subpart B-Procedures for Floodplain and

376

Solid Waste Regulation No. 8 - Solid Waste Composting Facilities (Rhode  

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

Regulation No. 8 - Solid Waste Composting Facilities Regulation No. 8 - Solid Waste Composting Facilities (Rhode Island) Solid Waste Regulation No. 8 - Solid Waste Composting Facilities (Rhode Island) < Back Eligibility Commercial Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State Rhode Island Program Type Environmental Regulations Provider Department of Environmental Management Facilities which compost putrescible waste and/or leaf and yard waste are subject to these regulations. The regulations establish permitting, registration, and operational requirements for composting facilities. Operational requirements for putrescible waste facilities include siting, distance, and buffer requirements, as well as standards for avoiding harm to endangered species and contamination of air and water sources. Specific

377

WIPP TRANSURANIC WASTE How has the WIPP TRU Waste Inventory Changed  

E-Print Network (OSTI)

of tank waste from the Hanford site that is currently managed as high-level waste. None of this waste has that these Hanford tank wastes will be treated and will eventually be able to meet the WIPP waste acceptance criteria on the Hanford Tank Waste and K-Basin Sludges that were included in the waste inventory for recertifica- tion

378

Hanford Tank Waste - Near Source Treatment of Low Activity Waste  

SciTech Connect

Treatment and disposition of Hanford Site waste as currently planned consists of I 00+ 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 ofthis 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 ofthe 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 describes the potential near source treatment and waste disposition options as well as the impact these options could have on reducing infrastructure requirements, project cost and mission schedule.

Ramsey, William Gene

2013-08-15T23:59:59.000Z

379

Innovative systems for mixed waste retrieval and/or treatment in confined spaces  

SciTech Connect

Fernald established operations in 1951 and produced uranium and other metals for use at other DOE facilities. A part of the sitewide remediation effort is the removal, treatment, and disposal of the K-65 wastes from Silos 1 and 2. These silos contain radium-bearing residues from the processing of pitchblende ore. An Engineering Evaluation/Cost Analysis was prepared to evaluate the removal action alternatives using the preliminary characterization data and select a preferred alternative. The selected alternative consisted of covering the K-65 residues and the silo dome. The remediation of the K-65 wastes consists of the retrieval and treatment of the wastes prior to final disposal, which has not yet been determined. Treatment will be performed in a new facility to be built adjacent to the silos. The wastes must be retrieved from silos in an efficient and reliable way and delivered to the treatment facility. The first challenge of covering the wastes with bentonite has been successfully met. The second phase of retrieving the wastes from the silos is not due for a few years. However, conceptual design and configuration of the retrieval system have been developed as part of the Conceptual Design Report. The system is based on the utilization of hydraulic mining techniques, and is based on similar successful applications. This report describes the emplacement of the bentonite grant and the design for the slurry retrieval system.

Fekete, L.J.; Ghusn, A.E. [Parsons Environmental Services, Inc., Fairfield, OH (United States)

1993-03-01T23:59:59.000Z

380

Waste acceptance and waste loading for vitrified Oak Ridge tank waste  

SciTech Connect

The Office of Science and Technology of the DOE has funded a joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC) to evaluate vitrification and grouting for the immobilization of sludge from ORNL tank farms. The radioactive waste is from the Gunite and Associated Tanks (GAAT), the Melton Valley Storage Tanks (MVST), the Bethel Valley Evaporator Service Tanks (BVEST), and the Old Hydrofractgure Tanks (OHF). Glass formulation development for sludge from these tanks is discussed in an accompanying article for this conference (Andrews and Workman). The sludges contain transuranic radionuclides at levels which will make the glass waste form (at reasonable waste loadings) TRU. Therefore, one of the objectives for this project was to ensure that the vitrified waste form could be disposed of at the Waste Isolation Pilot Plant (WIPP). In order to accomplish this, the waste form must meet the WIPP Waste Acceptance Criteria (WAC). An alternate pathway is to send the glass waste forms for disposal at the Nevada Test Site (NTS). A sludge waste loading in the feed of 6 wt percent will lead to a waste form which is non-TRU and could potentially be disposed of at NTS. The waste forms would then have to meet the requirements of the NTS WAC. This paper presents SRTC`s efforts at demonstrating that the glass waste form produced as a result of vitrification of ORNL sludge will meet all the criteria of the WIPP WAC or NTS WAC.

Harbour, J.R.; Andrews, M.K.

1997-06-06T23:59:59.000Z

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


381

Environmental waste disposal contracts awarded  

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

Environmental contracts awarded locally Environmental contracts awarded locally Environmental waste disposal contracts awarded locally Three small businesses with offices in Northern New Mexico awarded nuclear waste clean-up contracts. April 3, 2012 Worker moves drums of transuranic (TRU) waste at a staging area A worker stages drums of transuranic waste at Los Alamos National Laboratory's Technical Area 54. the Lap ships such drums to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) in Southern New Mexico. The Lab annually averages about 120 shipments of TRU waste to WIPP. Contact Small Business Office (505) 667-4419 Email "They will be valuable partners in the Lab's ability to dispose of the waste safely and efficiently." Small businesses selected for environmental work at LANL

382

Waste Isolation Pilot Plant - Reports  

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

Reports Reports Waste Isolation Pilot Plant Review Report 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control Activities, April 2013 Review Report 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant, November 2012 Activity Reports 2011 Orientation Visit to the Waste Isolation Pilot Plant, September 2011 Review Reports 2007 Independent Oversight Inspection of Emergency Management at the Carlsbad Field Office and Waste Isolation Pilot Plant, December 2007 Review Reports 2002 Inspection of Environment, Safety, and Health and Emergency Management at the Waste Isolation Pilot Plant - Summary Report, August 2002 Inspection of Environment, Safety, and Health Management at the Waste Isolation Pilot Plant - Volume I, August 2002

383

Waste Management | Department of Energy  

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

Management Management Waste Management 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 The Department has approximately 88 million gallons of liquid 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, treatment and disposal of this waste exceeds $50 billion to be spent over several decades.

384

Process Waste Assessment, Mechanics Shop  

SciTech Connect

This Process Waste Assessment was conducted to evaluate hazardous wastes generated in the Mechanics Shop. The Mechanics Shop maintains and repairs motorized vehicles and equipment on the SNL/California site, to include motorized carts, backhoes, street sweepers, trash truck, portable emergency generators, trencher, portable crane, and man lifts. The major hazardous waste streams routinely generated by the Mechanics Shop are used oil, spent off filters, oily rags, and spent batteries. The used off and spent off filters make up a significant portion of the overall hazardous waste stream. Waste oil and spent batteries are sent off-site for recycling. The rags and spent on filters are not recycled. They are disposed of as hazardous waste. Mechanics Shop personnel continuously look for opportunities to minimize hazardous wastes.

Phillips, N.M.

1993-05-01T23:59:59.000Z

385

Waste Management | Department of Energy  

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

Cleanup » Waste Management Cleanup » Waste Management Waste Management November 12, 2013 U.S. Department of Energy to Host Press Call on Radioactive Waste Shipment and Disposal On Tuesday, November 12, 2013, the U.S. Department of Energy (DOE) will host a press call to discuss Consolidated Edison Uranium Solidification Project (CEUSP) shipment and disposal plans in Nevada. September 24, 2013 Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and

386

WASTE/BY-PRODUCT HYDROGEN DOE/DOD Workshop  

E-Print Network (OSTI)

; 6 Waste/Byproduct HydrogenWaste/By product Hydrogen Waste H2 sources include: Waste biomass: biogas Waste/Byproduct Hydrogen Waste/By product Hydrogen Fuel FlexibilityFuel Flexibility Biogas: generated

387

Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 3. Revision 1  

SciTech Connect

This report consists of information related to the waste forms at the WIPP facility from the waste originators. Data for retrievably stored, projected and total wastes are given.

NONE

1995-02-01T23:59:59.000Z

388

Process for recovering hydrocarbons from a hydrocarbon-bearing formation  

SciTech Connect

A method is described for transporting heavy crude oil through a pipeline which involves introducing into a pipeline or well-bore with the viscous hydrocarbons an aqueous solution containing (1) a sulfonate surfactant, (2) a rosin soap or a naphthenic acid soap and, optionally (3) coupling agent whereby there is spontaneously formed a low viscosity, salt tolerant, oil-in-water emulsion. Also disclosed is a method of recovery of hydrocarbons from a hydrocarbon bearing formation employing an aqueous solution containing (1) a sulfonate surfactant, (2) a rosin soap or a naphthenic acid soap and, optionally (3) a coupling agent.

Alston, R.B.; Braden, W.B.; Flournoy, K.H.

1980-03-11T23:59:59.000Z

389

Method for digesting a nitro-bearing explosive compound  

DOE Patents (OSTI)

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.

Shah, Manish M. (Richland, WA)

2000-01-01T23:59:59.000Z

390

The use of elastomeric pads as bearings for steel beams  

E-Print Network (OSTI)

SCIEWCE August lg6S Ma)or Subjects Civil Eugiueeriag THE HSE OP BIASTMEEXC PASS AS EEARIHCS FOR STEE7 SEAMS A Thesis Hardy E. Fairbanks Approved as to style and content by; Chairnan of Coeeittee Head of Separtme t August 1960 TABLE OP CONTENTS... on Richmond Avenue in Houston, Texas Figure 5 Current Practice Concerning the Use of Elasto- meric Beazing Pads Pigure 6 Economic Comparison of Conventional and Elasto- 8 meric Bearings Figure 7 Figure 8 Figure 9 Teat Set-Up for Phase I Experimental...

Fairbanks, Hardy Ewald

2012-06-07T23:59:59.000Z

391

Treatment of halogen-containing waste and other waste materials  

DOE Patents (OSTI)

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.

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

1997-03-18T23:59:59.000Z

392

Treatment of halogen-containing waste and other waste materials  

DOE Patents (OSTI)

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.

Forsberg, Charles W. (Oak Ridge, TN); Beahm, Edward C. (Oak Ridge, TN); Parker, George W. (Concord, TN)

1997-01-01T23:59:59.000Z

393

Managing America's Defense Nuclear Waste | Department of Energy  

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

Managing America's Defense Nuclear Waste Managing America's Defense Nuclear Waste Managing America's Defense Nuclear Waste More Documents & Publications National Defense...

394

Experimental and Analytical Studies on Pyroelectric Waste Heat Energy Conversion  

E-Print Network (OSTI)

Waste heat Pyroelectric energy3 Pyroelectric Waste Heat Energy Harvesting Using Heat4 Pyroelectric Waste Heat Energy Harvesting Using Relaxor

Lee, Felix

2012-01-01T23:59:59.000Z

395

Nuclear waste management. Semiannual progress report, October 1983-March 1984  

SciTech Connect

Progress in the following studies on radioactive waste management is reported: defense waste technology; Nuclear Waste Materials Characterization Center; waste isolation; and supporting studies. 58 figures, 22 tables.

McElroy, J.L.; Powell, J.A.

1984-06-01T23:59:59.000Z

396

Gas Production from Hydrate-Bearing Sediments - Emergent Phenomena -  

SciTech Connect

Even a small fraction of fine particles can have a significant effect on gas production from hydrate-bearing sediments and sediment stability. Experiments were conducted to investigate the role of fine particles on gas production using a soil chamber that allows for the application of an effective stress to the sediment. This chamber was instrumented to monitor shear-wave velocity, temperature, pressure, and volume change during CO{sub 2} hydrate formation and gas production. The instrumented chamber was placed inside the Oak Ridge National Laboratory Seafloor Process Simulator (SPS), which was used to control the fluid pressure and temperature. Experiments were conducted with different sediment types and pressure-temperature histories. Fines migrated within the sediment in the direction of fluid flow. A vuggy structure formed in the sand; these small cavities or vuggs were precursors to the development of gas-driven fractures during depressurization under a constant effective stress boundary condition. We define the critical fines fraction as the clay-to-sand mass ratio when clays fill the pore space in the sand. Fines migration, clogging, vugs, and gas-driven fracture formation developed even when the fines content was significantly lower than the critical fines fraction. These results show the importance of fines in gas production from hydrate-bearing sediments, even when the fines content is relatively low.

Jung, J.W. [Georgia Institute of Technology; Jang, J.W. [Georgia Institute of Technology; Tsouris, Costas [ORNL; Phelps, Tommy Joe [ORNL; Rawn, Claudia J [ORNL; Santamarina, Carlos [Georgia Institute of Technology

2012-01-01T23:59:59.000Z

397

Combined passive magnetic bearing element and vibration damper  

DOE Patents (OSTI)

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.

Post, Richard F. (Walnut Creek, CA)

2001-01-01T23:59:59.000Z

398

Municipal Solid Waste:  

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

Methodology for Allocating Municipal Solid Waste 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 construed as advocating or reflecting any policy of the Department of Energy or any other organization. Contact This report was prepared by staff of the Renewable Information Team, Coal, Nuclear, and Renewables Division, Office of Coal, Nuclear, Electric and Alternate Fuels.

399

Tritium waste package  

DOE Patents (OSTI)

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.

Rossmassler, Rich (Cranbury, NJ); Ciebiera, Lloyd (Titusville, NJ); Tulipano, Francis J. (Teaneck, NJ); Vinson, Sylvester (Ewing, NJ); Walters, R. Thomas (Lawrenceville, NJ)

1995-01-01T23:59:59.000Z

400

Waste | OpenEI  

Open Energy Info (EERE)

Waste Waste Dataset Summary Description The Planning Database Project provides the UK Department of Energy and Climate Change (DECC) with regular data to track progress towards achieving EU targets for electricity generation from renewable energy (RE) sources. Extracts from the database are available each month. Information collected in the database includes: name, location and installed capacity of RE projects over 0.1MW; environmental designations; planning status; and construction status. Included here is the October 2010 Progress Datasheet, and an extract from December, 15, 2010 (i.e. Source UK Department of Energy and Climate Change (DECC) Date Released December 15th, 2010 (3 years ago) Date Updated Unknown Keywords biomass co-firing installed capacity

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


401

Tritium waste package  

DOE Patents (OSTI)

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.

Rossmassler, R.; Ciebiera, L.; Tulipano, F.J.; Vinson, S.; Walters, R.T.

1995-11-07T23:59:59.000Z

402

SRS - Programs - Liquid Waste Disposition  

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

Liquid Waste Disposition Liquid Waste Disposition This includes both the solidification of highly radioactive liquid wastes stored in SRS's tank farms and disposal of liquid low-level waste generated as a by-product of the separations process and tank farm operations. This low-level waste is treated in the Effluent Treatment Facility. High-activity liquid waste is generated at SRS as by-products from the processing of nuclear materials for national defense, research and medical programs. The waste, totaling about 36 million gallons, is currently stored in 49 underground carbon-steel waste tanks grouped into two "tank farms" at SRS. While the waste is stored in the tanks, it separates into two parts: a sludge that settles on the bottom of the tank, and a liquid supernate that resides on top of the sludge. The waste is reduced to about 30 percent of its original volume by evaporation. The condensed evaporator "overheads" are transferred to the Effluent Treatment Project for final cleanup prior to release to the environment. As the concentrate cools a portion of it crystallizes forming solid saltcake. The concentrated supernate and saltcake are less mobile and therefore less likely to escape to the environment in the event of a tank crack or leak.

403

Chapter 22 - Radioactive Waste Disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses safe disposal of radioactive waste in order to provide safety to workers and the public. Radioactive wastes arise from a great variety of sources, including the nuclear fuel cycle, and from beneficial uses of isotopes and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. In the United States spent fuel is accumulating, awaiting the development of a high-level waste repository. A multi-barrier system involving packaging and geological media will provide protection of the public over the centuries the waste must be isolated. The favored method of disposal is in a mined cavity deep underground. In other countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is by casks and containers designed to withstand severe accidents. Low-level wastes (LLWs) come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Establishment of regional disposal sites by interstate compacts has generally been unsuccessful in the United States. Decontamination of defense sites will be long and costly. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2009-01-01T23:59:59.000Z

404

Method for processing aqueous wastes  

DOE Patents (OSTI)

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.

Pickett, John B. (3922 Wood Valley Dr., Aiken, SC 29803); Martin, Hollis L. (Rt. 1, Box 188KB, McCormick, SC 29835); Langton, Christine A. (455 Sumter St. SE., Aiken, SC 29801); Harley, Willie W. (110 Fairchild St., Batesburg, SC 29006)

1993-01-01T23:59:59.000Z

405

Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage  

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

Disposal, Hazardous Waste Management Act, Underground Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) < Back Eligibility Agricultural Commercial Construction Developer Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Nonprofit Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Tribal Government Utility Program Info State Tennessee Program Type Environmental Regulations Siting and Permitting Provider Tennessee Department Of Environment and Conservation The Solid Waste Disposal Laws and Regulations are found in Tenn. Code 68-211. These rules are enforced and subject to change by the Public Waste Board (PWB), which is established by the Division of Solid and Hazardous

406

Theory versus experimental results and comparisons for five orifice-compensated hybrid bearing configurations  

E-Print Network (OSTI)

). . . . . . 16 Static Loader (Kurtin, et al. , 1991). . . . . . . . . . . . . 17 Dynamic Excitation (Childs, Hale, and Rouvas, 1991). . . . . 18 Hydrostatic Bearing (Rowe, 1983) Pressure Distribution for an Orifice-Compensated Circular Hydrostatic Pad (Rowe... hydrostatic bearing, shown in Fig. 12, is an externally pressurized journal bearing which employs compensation (i. e. , flow restriction) devices to pro- vide both stability and load support for the journal. This compensation is accomplished by injecting a...

Franchek, Nancy Marie

1992-01-01T23:59:59.000Z

407

Waste Growth Challenges Local Democracy. The Politics of Waste between Europe and the Mediterranean: a Focus on Italy  

E-Print Network (OSTI)

activities, such as waste burning versus waste dumping.and the Geographies of Waste Governance: A Burning Issue forEurope: Burning oriented Incineration (waste-to-energy)

Mengozzi, Alessandro

2010-01-01T23:59:59.000Z

408

RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 RADIOACTIVE WASTE DISPOSAL  

E-Print Network (OSTI)

RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 CHAPTER 7 RADIOACTIVE WASTE DISPOSAL PAGE I. Radioactive Waste Disposal ............................................................................................ 7-2 II. Radiation Control Technique #2 Instructions for Preparation of Radioactive Waste

Slatton, Clint

409

Argonne Researchers Shine "Light" on Origins of Wind Turbine Bearing Failures  

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

Researchers at DOE's Argonne National Laboratory are investigating the root cause of failures to wind turbine drivetrain components, such as bearings and gears.

410

Optimisation of deep cryogenic treatment for 100cr6 bearing steel using the grey taguchi technique; -.  

E-Print Network (OSTI)

??Deep Cryogenic treatment is a supplementary process to the conventional heat treatment for enhancing the mechanical properties of steels 100Cr6 bearing steel is widely used (more)

Sri Siva, R

2014-01-01T23:59:59.000Z

411

E-Print Network 3.0 - actively lubricated bearings Sample Search...  

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

Summary: to operation of bearings and splines include wear, fatigue, lubrication, and heat dissipation. Mechanical... shafts that are lined along the length of the engine. Both...

412

Bearing options, including design and testing, for direct drive linear generators in wave energy converters.  

E-Print Network (OSTI)

??The key focus of this research was to investigate the bearing options most suited to operation in a novel direct drive linear generator. This was (more)

Caraher, Sarah

2011-01-01T23:59:59.000Z

413

Improvement of bearing strength of laminated composites by nanoclay and Z-pin reinforcement.  

E-Print Network (OSTI)

??The bearing behavior of bolted composite joints is significantly poorer than that of their metallic counterparts. The objective of the present study was to examine (more)

Huong, Tran Phuong Nam

2008-01-01T23:59:59.000Z

414

Synthesis, characterization, and reactivity studies of iridium complexes bearing the ligand diphenylphosphidoboratabenzene  

E-Print Network (OSTI)

The synthesis, structure, and reactivity properties of three iridium square planar complexes bearing the anionic phosphine ligand diphenylphosphidoboratabenzene (DPB) are described. Reactivity studies show a rate enhancement ...

Arizpe, Luis (Luis Alfredo)

2011-01-01T23:59:59.000Z

415

WASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED,  

E-Print Network (OSTI)

/spills and subsequent clean up costs ($20,000) Sewage Sludge Volume Reduction 234,000 Radioactive Waste $910,000 $193,400 $716,600 60,000 gallons of radioactive STP liquid waste could have been disposed of through,000) Digital Imaging System Substitution 282 Hazardous Waste / Radioactive Waste / Industrial Waste $25,000 $25

416

WASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED,  

E-Print Network (OSTI)

equipment. Savings are based on the cost of one PCB spill and clean-up event. Radioactive Waste Source Reduction 1,500 Radioactive Waste $6,000 $2,500 $6,000 Waste Yard Sorting Table surveying to sort clean waste from radioactive waste Radioactive Emissions Emission Reduction 0 Radioactive Emissions $0

417

Hydration Aging of Nuclear Waste Glass  

Science Journals Connector (OSTI)

...of Nuclear Waste Glass 10...STEINDLER Chemical Engineering...60439 The aging of simulated nuclear waste glass by...nuclear waste forms can meet...simulated aging reac-tions...whether a waste formn can...pro-jected Nuclear Regulatory...STEINDLEt Chemical Engineering...Basisfor Waste Form Integrity...

J. K. BATES; L. J. JARDINE; M. J. STEINDLER

1982-10-01T23:59:59.000Z

418

Waste Management | Department of Energy  

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

July 27, 2011 July 27, 2011 End of Year 2010 SNF & HLW Inventories Map of the United States of America that shows the location of approximately 64,000 MTHM of Spent Nuclear Fuel (SNF) & 275 High-Level Radioactive Waste (HLW) Canisters. July 27, 2011 FY 2007 Total System Life Cycle Cost, Pub 2008 The Analysis of the Total System Life Cycle Cost (TSLCC) of the Civilian Radioactive Waste Management Program presents the Office of Civilian Radioactive Waste Management's (OCRWM) May 2007 total system cost estimate for the disposal of the Nation's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The TSLCC analysis provides a basis for assessing the adequacy of the Nuclear Waste Fund (NWF) Fee as required by Section 302 of the Nuclear Waste Policy Act of 1982 (NWPA), as amended.

419

Waste/By-Product Hydrogen  

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

WASTE/BY-PRODUCT HYDROGEN WASTE/BY-PRODUCT HYDROGEN Ruth Cox DOE/DOD Workshop January 13, 2011 January 13, 2011 Fuel Cell and Hydrogen Energy Association The Fuel Cell and Hydrogen Energy Association FCHEA ƒ Trade Association for the industry ƒ Member driven - Market focused ƒ Developers, suppliers, customers, nonprofits, government Ad ƒ Advocacy ƒ Safety and standardization ƒ Education ƒ Strategic Alliances Fuel Cell and Hydrogen Energy Association O M b Our Members 5 W t /B d t H d Waste/By-product Hydrogen Overview Overview ƒ Growing populations, rising standards of living, and increased urbanization leads to a escalating volume of waste leads to a escalating volume of waste. ƒ Huge volumes of waste are collected in dumps, creating a major environmental issue. ƒ ƒ Wastewater treatment plants generate noxious gasses that are released in Wastewater treatment plants generate noxious gasses that are released in

420

WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION  

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

Carlsbad, New Mexico 8822 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 Hazardous Waste Facility Perm it Part 2, Permit Condition 2.4. We certify under penalty of law that this document and all enclosures were prepared under our direction or supervision according to a system designed to assure that qualified personnel properly gather and evaluate the information submitted

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


421

Development programs in the United States of America for the application of cement-based grouts in radioactive waste management  

SciTech Connect

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.

Dole, L.R.; Row, T.H.

1984-01-01T23:59:59.000Z

422

Neutronics analysis for an accelerator-based nuclear waste transmuter  

SciTech Connect

The neutronic analysis for a target/blanket design that is capable of supporting the high level waste stream from 2.5 LWR`s is described. The target consists of a set of solid tungsten and lead plates, cooled by heavy water and surrounded by a lead annulus. The annular blanket, which surrounds the target, consists of a set of AcO{sub 2} slurry bearing tubes, each 3 meters long, surrounded by heavy water moderator. Heat removal from the slurry tubes is by passing the rapidly moving slurry through an external heat exchanger. There are separate regions for long-lived fission product burning. Using the Monte Carlo codes LAHET and MCNP we have optimized the design for a minimum beam current of 62.5 mA of 1.6 GeV protons.

Sailor, W.C.; Beard, C.A.

1993-07-01T23:59:59.000Z

423

Hydrothermal Processing of Wet Wastes  

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

Mill Waste, Plastic Bottles Aquatic Water Hyacinths, Kelp (Marine), Red Algae (Marine), Green Algae (Brackish), Green Algae (Marine), Green Algae (Fresh), Diatoms, Cyanobacteria...

424

Chernobyls waste site  

SciTech Connect

An analysis of the prospects for using the Chernobyl exclusion zone for development of a spent fuel store, waste disposal site and other nuclear facilities.

Schmieman, Eric A.; Paskevych, Sergiy; Sizov, Andrey; Batiy, Valeriy

2007-02-15T23:59:59.000Z

425

Process for preparing liquid wastes  

DOE Patents (OSTI)

A process for preparing radioactive and other hazardous liquid wastes for treatment by the method of vitrification or melting is provided for.

Oden, Laurance L. (Albany, OR); Turner, Paul C. (Albany, OR); O'Connor, William K. (Lebanon, OR); Hansen, Jeffrey S. (Corvallis, OR)

1997-01-01T23:59:59.000Z

426

Funds denied for nuclear waste  

Science Journals Connector (OSTI)

... curb on the amount of nuclear waste that can be stored in the state's West Valley .facility, which has been closed since 1972. ...

David Dickson

1979-05-24T23:59:59.000Z

427

Tank Waste Committee Page 1  

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

7, 2014 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD TANK WASTE COMMITTEE May 7, 2014 Richland, WA Topics in this Meeting Summary Opening ......

428

Tank Waste Committee Page 1  

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

June 9, 2011 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD TANK WASTE COMMITTEE MEETING June 9, 2011 Richland, WA Topics in this Meeting Summary Welcome and Introductions...

429

Tank Waste Committee Page 1  

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

Waste Permit (Permit), introduced the discussion of Permit units that relate to tanks. Liz said the Permit was last available for review in 1994. There have been revisions...

430

Tank Waste Committee Page 1  

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

... 2 Review of Responses to HAB Advice 271 Leaking Tanks and HAB Advice 273 Openness and Transparency Related to Tank Waste Treatment...

431

Waste/By-Product Hydrogen  

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

Presentation by Ruth Cox, Fuel Cell and Hydrogen Energy Association, at the DOE-DOD Waste-to-Energy using Fuel Cells Workshop held Jan. 13, 2011

432

Progress Update: TRU Waste Shipping  

SciTech Connect

A progress update at the Savannah River Site. A continued effort on shipping TRU waste to WIPP in Carlsbad, New Mexico.

Cody, Tom

2010-01-01T23:59:59.000Z

433

WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION  

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

or statements that outline goals, objectives, and methods for source reduction and recycling of hazardous and mixed waste at the facility; 2. Employee training or incentive...

434

Reporting Fraud, Waste, and Abuse  

Directives, Delegations, and Requirements

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.

2004-09-15T23:59:59.000Z

435

Nuclear waste could bury itself  

Science Journals Connector (OSTI)

... we can have strong scientific confidence in," says the chairman of Britain's Radioactive Waste Management Advisory Committee, Charles Curtis, a geochemist at the University of Manchester. ...

Tom Clarke

2003-08-13T23:59:59.000Z

436

Tank Waste Committee - Transcribed Flipcharts  

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

TRU waste retrieval Provided the State of New Mexico concurs Determine not HLW (process knowledge) As long as meets all applicable requirements "evaluation" not...

437

Environmental sustainability comparison of a hypothetical pneumatic waste collection system and a door-to-door system  

SciTech Connect

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 significant bearing on the results, emissions due to manufacturing the system's components prove decisive.

Punkkinen, Henna, E-mail: henna.punkkinen@vtt.fi [VTT Technical Research Centre of Finland, Biologinkuja 7, P.O. Box 1000, FI-02044 VTT (Finland); Merta, Elina, E-mail: elina.merta@vtt.fi [VTT Technical Research Centre of Finland, Biologinkuja 7, P.O. Box 1000, FI-02044 VTT (Finland); Teerioja, Nea, E-mail: nea.teerioja@helsinki.fi [University of Helsinki, Department of Economics and Management, Latokartanonkaari 9, P.O. Box 27, FI-00014 HY (Finland); Moliis, Katja, E-mail: katja.moliis@helsinki.fi [University of Helsinki, Department of Economics and Management, Latokartanonkaari 9, P.O. Box 27, FI-00014 HY (Finland); Kuvaja, Eveliina, E-mail: eveliina.kuvaja@helsinki.fi [University of Helsinki, Department of Economics and Management, Latokartanonkaari 9, P.O. Box 27, FI-00014 HY (Finland)

2012-10-15T23:59:59.000Z

438

DOE Solar Decathlon: University of Virginia: Bearing Solar Gifts  

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

Virginia's house on the National Mall at Solar Decathlon 2002. Virginia's house on the National Mall at Solar Decathlon 2002. Enlarge image The Trojan Goat incorporates recycled materials, including copper cladding reclaimed from a roof, wood panels reclaimed from shipping pallets, and paving stones reclaimed from the Rotunda at the University of Virginia. (Credit: Chris Gunn/U.S. Department of Energy Solar Decathlon) Who: University of Virginia What: Trojan Goat Where: Private residence Crozet, VA 22932 Map This House Public tours: Not available Solar Decathlon 2002 University of Virginia: Bearing Solar Gifts Like the Trojan horse that launched the Greeks to victory, the Trojan Goat earned the University of Virginia second place in the U.S. Department of Energy Solar Decathlon 2002. Since then, the house has gone on to inspire

439

Stabilization, Packaging, and Storage of Plutonium-Bearing Materials  

Energy.gov (U.S. Department of Energy (DOE)) 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: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-STD-3013-2000 iii ABSTRACT This Standard provides guidance for the stabilization, packaging and safe storage of plutonium-

440

Criteria for Packaging and Storing Uranium-233-Bearing Materials  

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

3028-2000 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. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-STD-3028-2000 iii ABSTRACT This Standard provides guidance for the packaging and long-term (50 years) storage of stabilized, separated uranium-233(

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


441

Development of high efficiency ball-bearing turbocharger  

SciTech Connect

Turbochargers have become very popular on passenger cars since the first mass-produced turbocharged passenger cars were put on market in Japan in 1979. Turbo lag is one of the most serious problem since the first mass-production started. Several new technologies such as a variable geometry turbocharger, ceramic turbocharger, etc. have been introduced to improve acceleration performance. A variable geometry turbocharger changes the area of gas flow passage and increases exhaust gas speed at low engine speed. A ceramic turbocharger reduces inertia moment of a turbine wheel and shaft. Turbocharger mechanical efficiency has equal importance as compressor efficiency and turbine efficiency. This paper describes the test results of ball bearing turbochargers.

Miyashita, K.; Kurasawa, M.; Matsuoka, H.; Ikeya, N.

1987-01-01T23:59:59.000Z

442

Magnetic bearing development for support of satellite flywheels  

Science Journals Connector (OSTI)

The use of magnetic bearings (MB) for support of space based flywheels can provide significant improvement in efficiency due to reduction in drag torque. A NASA supported program directed through the Texas A&M Center for Space Power has been formed to advance the technology of MBs for satellite flywheel applications. The five areas of the program are: (a) Magnetic Field Simulation (b) MB controller Development (c) Electromechanical Rotordynamics Modeling (d) Testing and (e) Technology Exchange. Planned innovations in these tasks include eddy current drag torque and power loss determination including moving conductor effects digital (DSP) based control for high speed operation MATLAB-based coupled flexible rotor/controller/actuator electromechanical model with fuzzy logic nonlinear control and ultra high speed>100?krpm measurement of drag torque. The paper examines these areas and provides an overview of the project.

Alan Palazzolo; Mu Li; Andrew Kenny; Shuliang Lei; Danny Havelka; Albert Kascak

1998-01-01T23:59:59.000Z

443

Preliminary relative permeability estimates of methanehydrate-bearing sand  

SciTech Connect

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.

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

2006-05-08T23:59:59.000Z

444

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation  

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

ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment October 3, 2011 - 12:00pm Addthis DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, N.M. - The Waste Isolation Pilot Plant (WIPP) received its

445

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation  

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

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment October 3, 2011 - 12:00pm Addthis DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, N.M. - The Waste Isolation Pilot Plant (WIPP) received its

446

Technology development program for Idaho Chemical Processing Plant spent fuel and waste management  

SciTech Connect

Acidic high-level radioactive waste (HLW) resulting from fuel reprocessing at the Idaho Chemical Processing Plant (ICPP) for the U.S. Department of Energy (DOE) has been solidified to a calcine since 1963 and stored in stainless steel bins enclosed by concrete vaults. Several different types of unprocessed irradiated DOE-owned fuels are also in storage at the ICPP. In April, 1992, DOE announced that spent fuel would no longer be reprocessed to recover enriched uranium and called for a shutdown of the reprocessing facilities at the ICPP. A new Spent Fuel and HLW Technology Development program was subsequently initiated to develop technologies for immobilizing ICPP spent fuels and HLW for disposal, in accordance with the Nuclear Waste Policy Act. The Program elements include Systems Analysis, Graphite Fuel Disposal, Other Spent Fuel Disposal, Sodium-Bearing Liquid Waste Processing, Calcine Immobilization, and Metal Recycle/Waste Minimization. This paper presents an overview of the ICPP radioactive wastes and current spent fuels, and describes the Spent Fuel and HLW Technology program in more detail.

Ermold, L.F.; Knecht, D.A.; Hogg, G.W.; Olson, A.L.

1993-08-01T23:59:59.000Z

447

Response of oceanic hydrate-bearing sediments to thermalstresses  

SciTech Connect

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 packs that allow gas venting and pressure relief result insubstantially lower pressures.

Moridis, G.J.; Kowalsky, M.B.

2006-05-01T23:59:59.000Z

448

ALUMINUM REMOVAL FROM HANFORD WASTE BY LITHIUM HYDROTALCITE PRECIPITATION - LABORATORY SCALE VALIDATION ON WASTE SIMULANTS TEST REPORT  

SciTech Connect

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.

SAMS T; HAGERTY K

2011-01-27T23:59:59.000Z

449

Waste acceptance criteria for the Waste Isolation Pilot Plant  

SciTech Connect

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.

NONE

1996-04-01T23:59:59.000Z

450

Waste gas combustion in a Hanford radioactive waste tank  

SciTech Connect

It has been observed that a high-level radioactive waste tank generates quantities of hydrogen, ammonia, nitrous oxide, and nitrogen that are potentially well within flammability limits. These gases are produced from chemical and nuclear decay reactions in a slurry of radioactive waste materials. Significant amounts of combustible and reactant gases accumulate in the waste over a 110- to 120-d period. The slurry becomes Taylor unstable owing to the buoyancy of the gases trapped in a matrix of sodium nitrate and nitrite salts. As the contents of the tank roll over, the generated waste gases rupture through the waste material surface, allowing the gases to be transported and mixed with air in the cover-gas space in the dome of the tank. An ignition source is postulated in the dome space where the waste gases combust in the presence of air resulting in pressure and temperature loadings on the double-walled waste tank. This analysis is conducted with hydrogen mixing studies HMS, a three-dimensional, time-dependent fluid dynamics code coupled with finite-rate chemical kinetics. The waste tank has a ventilation system designed to maintain a slight negative gage pressure during normal operation. We modeled the ventilation system with the transient reactor analysis code (TRAC), and we coupled these two best-estimate accident analysis computer codes to model the ventilation system response to pressures and temperatures generated by the hydrogen and ammonia combustion.

Travis, J.R.; Fujita, R.K.; Spore, J.W.

1994-07-01T23:59:59.000Z

451

Tank Waste Remediation System Tank Waste Analysis Plan. FY 1995  

SciTech Connect

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.

Haller, C.S.; Dove, T.H.

1994-11-01T23:59:59.000Z

452

Radioactive waste processing apparatus  

DOE Patents (OSTI)

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.

Nelson, R.E.; Ziegler, A.A.; Serino, D.F.; Basnar, P.J.

1985-08-30T23:59:59.000Z

453

Evaluation of Used Fuel Disposition in Clay-Bearing Rock  

SciTech Connect

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 70s and mid 80s. 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 repository leveraging in large part on the information garnered in URLs and laboratory data to test and demonstrate model prediction capability and to accurately represent behavior of the EBS and the natural (barrier) system (NS). In addition, experimental work to improve our understanding of clay barrier interactions and TM couplings at high temperatures are key to evaluate thermal effects as a result of relatively high heat loads from waste and the extent of sacrificial zones in the EBS. To assess the latter, experiments and modeling approaches have provided important information on the stability and fate of barrier materials under high heat loads. This information is central to the assessment of thermal limits and the implementation of the reference case when constraining EBS properties and the repository layout (e.g., waste package and drift spacing). This report is comprised of various parts, each one describing various R&D activities applicable to shale/argillite media. For example, progress made on modeling and experimental approaches to analyze physical and chemical interactions affecting clay in the EBS, NS, and used nuclear fuel (source term) in support of R&D objectives. It also describes the development of a reference case for shale/argillite media. The accomplishments of these activities are summarized as follows: ? Development of a reference case for shale/argillite; ? Investigation of Reactive Transport and Coupled THM Processes in EBS: FY14; ? Update on Experimental Activities on Buffer/Backfill Interactions at elevated Pressure and Temperature; ? Thermodynamic Database Development: Evaluation Strategy, Modeling Tools, First-Principles Modeling of Clay, and Sorption Database Assessment; ? ANL Mixed Potential Model For Used Fuel Degradation: Application to Argillite and Crystalline Rock Environments.

Carlos F. Jov Coln; Philippe F. Weck; David H. Sassani; Liange Zheng; Jonny Rutqvist; Carl I. Steefel; Kunhwi Kim; Seiji Nakagawa; James Houseworth; Jens Birkholzer; Florie A. Caporuscio; Michael Cheshire; Michael S. Rearick; Mary K. McCarney; Mavrik Zavarin; Ana Benedicto; Annie B. Kersting; Mark Sutton; James Jerden; Kurt E. Frey; Jacqueline M. Copple; William Ebert

2014-08-29T23:59:59.000Z

454

Nuclear Waste Policy Act | Department of Energy  

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

455

Available Options for Waste Disposal [and Discussion  

Science Journals Connector (OSTI)

...vitrified high-activity waste in properly selected deep...alternatives to present projects of waste disposal, but rather as...benefits will be different. Long-term storage of either spent fuel or vitrified waste, although not an alternative...

1986-01-01T23:59:59.000Z

456

Waste oil reduction: GKN  

SciTech Connect

This report details the steps required to establish a waste oil management program. Such a program can reduce operational costs, cut wastewater treatment costs and produce a better quality wastewater effluent through such means as: reducing the volume of oils used; segregating oils at the source of generation for recovery and reuse; and reducing the quality of oily wastewater generated. It discusses the metal-working fluid recovery options available for such a program, namely settling, filtration, hydrocyclone, and centrifugation. Included are source lists for vendors of oil skimmer equipment and coolant recovery systems.

Hunt, G.

1995-08-01T23:59:59.000Z

457

Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility  

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

6 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. Department of Energy Office of River Protection under Contract DE-AC05-76RL01830 07-DESIGN-046 iii Summary The U.S. Department of Energy (DOE), Office of River Protection (ORP) and the DOE Office of Environmental and Radioactive Waste Management (EM), Office of Project Recovery have completed a

458

Experience in operating and reconstructing the turbine bearings of units of the Sayano-Shushenskoe hydroelectric station  

SciTech Connect

This article reviews some of the operations and maintenance experiences at the Sayano-Shushenskoe hydroelectric sstation in Russia. In particular, the experiences gained in the operation of the turbines and the reconstruction of the turbine bearings are noted. The compact layout of this facility did not permit the traditional babbitt bearing or rubber ring bearing with water lubrication. Instead, a rubber sugmented bearing with water lubrication was used. The design and construction of this bearing, as well as the operation and maintenance of this bearing, is discussed in this article. The operating experiences have shown that the component is highly reliable.

Nikitenko, G.I.

1994-10-01T23:59:59.000Z

459

Waste acid detoxification and reclamation: Summary of bench-scale tests for FY 1986 and FY 1987  

SciTech Connect

Processes to reduce the volume, quantity, and toxicity of metal-bearing waste acid are being demonstrated at Pacific Northwest Laboratory. Two precipitation processes and a distillation process are being developed to minimize waste from fuel fabrication operations, which comprise a series of metal-finishing operations. Waste process acids such as HF-HNO/sub 3/, etch solutions containing Zr as a major metal impurity, and HNO/sub 3/ strip solution containing Cu as a major metal impurity are detoxified and reclaimed by concurrently precipitating heavy metals and regenerating acid for recycle. Acid from a third waste acid stream generated from chemical milling operations will be reclaimed using distillation. This stream comprises HNO/sub 3/ and H/sub 2/SO/sub 4/ containing U as the major metal impurity. Distillation allows NO/sub 3//sup -/ to be displaced by SO/sub 4//sup -2/ in metal salts; free HNO/sub 3/ is then vaporized from the U-bearing sulfate stream. Uranium can be recovered from the sulfate stream in a downstream precipitation step. 10 refs., 15 figs., 13 tabs.

Stewart, T.L.

1987-09-01T23:59:59.000Z

460

The Local Seeing Environment at Big Bear Solar Observatory Angelo Verdoni and Carsten Denker1  

E-Print Network (OSTI)

­ Big Bear Solar Observatory (BBSO) in California, Mees Solar Observatory (MSO) on Haleakal¯a, MauiThe Local Seeing Environment at Big Bear Solar Observatory Angelo Verdoni and Carsten Denker1 New Jersey Institute of Technology, Center for Solar-Terrestrial Research, 323 Martin Luther King Blvd

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


461

Experimental response of a rotor supported on Rayleigh step gas bearings  

E-Print Network (OSTI)

contact during start-up and shutdown. Quick lifting of the rotor in the air bearings reduces the wear and damage of solid surfaces for long durability of the bearings under cyclic start/stop operation. 6 Sastri et al. [27] study the tribological...

Zhu, Xuehua

2004-11-15T23:59:59.000Z

462

Applying the gravity approach to sector trade: Who bears the trade costs?  

E-Print Network (OSTI)

, France Financial support received by the "New Issues in Agricultural, Food and Bio-energy TradeApplying the gravity approach to sector trade: Who bears the trade costs? Angela CHEPTEA, Alexandre to sector trade: Who bears the trade costs? Angela CHEPTEA INRA, UMR1302 SMART, F-35000 Rennes, France

Paris-Sud XI, Université de

463

THEORETICAL & APPLIED MECHANICS LETTERS 4, 022001 (2014) Unified gas-kinetic simulation of slider air bearing  

E-Print Network (OSTI)

, slider air-bearing, non-equilibrium The slider air bearing problem arises from the hard disk industry. The demand of higher recording density requires the spacing between the read/write head and the disk-assisting magnetic recording (HAMR) that introduces a heat source into the slider system. Both the nano-scale flying

Xu, Kun

464

Experimental response of gas hybrid bearings for high speed oil-free turbomachinery  

E-Print Network (OSTI)

conducted on a small rotor supported on three lobed hybrid (hydrostatic/hydrodynamic) rigid gas bearings. The rigid bearings are made up of preloaded 120? lobes with minute feed holes for external pressurization that are fed, for example, by bleed off from...

Wilde, Deborah Anne

2012-06-07T23:59:59.000Z

465

Response of a bubble bearing viscoelastic fluid to rapid decompression: Implications for explosive volcanic eruptions  

E-Print Network (OSTI)

Response of a bubble bearing viscoelastic fluid to rapid decompression: Implications for explosive Abstract We conducted rapid decompression experiments using bubble-bearing viscoelastic fluid in a vertical of the bubbles, DP=Pg ?Po, to understand the behavior of bubbly-magmas under rapid decompression. We find

Manga, Michael

466

The effect of side-restraint bearings on the performance of base-isolated buildings  

E-Print Network (OSTI)

1 The effect of side-restraint bearings on the performance of base- isolated buildings J P Talbot * Corresponding author. Email: jpt1000@eng.cam.ac.uk Abstract: Base-isolation of buildings is a common solution vibration isolation bearings between a building and its foundation, aligned in the vertical direction so

Talbot, James P.

467

Notice of Comment Extension for the Preferred Sodium Bearing Waste Treatment Technology (DOE/EIS-0287) (08/23/05)  

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

64 Federal Register 64 Federal Register / Vol. 70, No. 162 / Tuesday, August 23, 2005 / Notices FOR FURTHER INFORMATION CONTACT: Elizabeth Payer, Institute of Education Sciences, U.S. Department of Education, 555 New Jersey Avenue, NW., room 602C, Washington, DC 20208. Telephone: (202) 219-1310 or via Internet: elizabeth.payer@ed.gov. If you use a telecommunications device for the deaf (TDD), you may call the Federal Relay Service (FRS) at 1- 800-877-8339. Individuals with disabilities may obtain this document in an alternative format (e.g., Braille, large print, audiotape, or computer diskette) on request to the contact person listed under FOR FURTHER INFORMATION CONTACT. SUPPLEMENTARY INFORMATION: On June 13, 2000, we published a notice in the Federal Register (65 FR 37229) inviting

468

Hazardous Wastes Management (Alabama) | Department of Energy  

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

Hazardous Wastes Management (Alabama) Hazardous Wastes Management (Alabama) Hazardous Wastes Management (Alabama) < Back Eligibility Commercial Construction Developer Industrial Transportation Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Alabama Program Type Environmental Regulations Safety and Operational Guidelines This legislation gives regulatory authority to the Department of Environmental Management to monitor commercial sites for hazardous wastes; fees on waste received at such sites; hearings and investigations. The legislation also states responsibilities of generators and transporters of hazardous waste as well as responsibilities of hazardous waste storage and treatment facility and hazardous waste disposal site operators. There

469

Independent Oversight Assessment, Salt Waste Processing Facility...  

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

Salt Waste Processing Facility Project - January 2013 January 2013 Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project The U.S. Department of Energy...

470

Independent Oversight Review, Waste Treatment and Immobilization...  

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

Review, Waste Treatment and Immobilization Plant - March 2012 March 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality This...

471

Independent Oversight Review, Waste Treatment and Immobilization...  

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

Waste Treatment and Immobilization Plant - October 2012 October 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report...

472

Independent Oversight Review, Waste Treatment and Immobilization...  

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

Waste Treatment and Immobilization Plant - August 2012 August 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report...

473

Independent Oversight Activity Report, Hanford Waste Treatment...  

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

and Tank Farm - January 2014 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant and Tank Farm - January 2014 January 2014 Hanford Waste...

474

Independent Oversight Activity Report, Hanford Waste Treatment...  

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

July 2013 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - July 2013 July 2013 Operational Awareness of Waste Treatment and Immobilization...

475

Independent Oversight Review, Waste Treatment and Immobilization...  

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

Waste Treatment and Immobilization Plant - November 2011 November 2011 Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality This...

476

Independent Oversight Review, Waste Treatment and Immobilization...  

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

Review, Waste Treatment and Immobilization Plant - March 2013 March 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S....

477

Oversight Reports - Waste Isolation Pilot Plant | Department...  

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

2011 Orientation Visit to the Waste Isolation Pilot Plant HIAR-WIPP-2011-09-07 November 26, 2007 Independent Oversight Inspection, Waste Isolation Pilot Plant - December 2007...

478

Environmental Management Waste Management Facility (EMWMF) at...  

Office of Environmental Management (EM)

Environmental Management Waste Management Facility (EMWMF) at Oak Ridge Environmental Management Waste Management Facility (EMWMF) at Oak Ridge Full Document and Summary Versions...

479

Development of Thermoelectric Technology for Automotive Waste...  

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

Thermoelectric Technology for Automotive Waste Heat Recovery Development of Thermoelectric Technology for Automotive Waste Heat Recovery Overview and status of project to develop...

480

Development of Thermoelectric Technology for Automotive Waste...  

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

Thermoelectric Technology for Automotive Waste Heat Recovery Development of Thermoelectric Technology for Automotive Waste Heat Recovery Presentation from the U.S. DOE Office of...

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


481

WIPP Receives Waste Characterized With Mobile System  

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

For Immediate Release WIPP Receives Waste Characterized With Mobile System CARLSBAD, N.M., April 12, 2002 - The first shipment of transuranic waste characterized by the Central...

482

Independent Oversight Activity Report, Hanford Waste Treatment...  

Office of Environmental Management (EM)

of River Protection review of the High Level Waste Facility heating, ventilation, and air conditioning systems. Independent Oversight Activity Report, Hanford Waste Treatment...

483

Enterprise Assessments Operational Awareness Record, Waste Treatment...  

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

the melter handling system (LMH), the melter equipment support handling system (LSH), the radioactive solid waste handling system (RWH), and the radioactive liquid waste disposal...

484

Missouri Hazardous Waste Management Law (Missouri)  

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

The Hazardous Waste Program, administered by the Hazardous Waste Management Commission in the Department of Natural Resources, regulates the processing, transportation, and disposal of hazardous...

485

Civilian Radioactive Waste Management System Requirements Document...  

Office of Environmental Management (EM)

Civilian Radioactive Waste Management System Requirements Document Civilian Radioactive Waste Management System Requirements Document This document specifies the top-level...

486

Nuclear waste storage bill passes Congress  

Science Journals Connector (OSTI)

Nuclear waste storage bill passes Congress ... The law sets up provisions to evaluate ways to store spent nuclear fuel and wastes. ...

1983-01-03T23:59:59.000Z

487

Independent Oversight Activity Report, Hanford Waste Treatment...  

Energy Savers (EERE)

October 2013 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - October 2013 October 2013 Observation of Waste Treatment and Immobilization...

488

Sandia National Laboratories: Defense Waste Management Programs  

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

Programs provides scientific analyses and programmatic advice to the U.S. Department of Energy in support of defense waste management challenges. Defense waste encompasses...

489

Voluntary Protection Program Onsite Review, Transuranic Waste...  

Energy Savers (EERE)

Transuranic Waste Processing Center - September 2012 Voluntary Protection Program Onsite Review, Transuranic Waste Processing Center - September 2012 September 2012 Evaluation to...

490

Sandia National Laboratories: radiation waste cleanup  

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

waste cleanup ECIS and UOP (a Honewell Company): CSTs Clean Radioactive Waste in Fukushima and Worldwide On February 14, 2013, in Energy, Materials Science, Nuclear Energy,...

491

Independent Oversight Review, Waste Treatment and Immobilization...  

Energy Savers (EERE)

January 2013 Independent Oversight Review, Waste Treatment and Immobilization Plant - January 2013 January 2013 Review of the Hanford Waste Treatment and Immobilization Plant...

492

1993 Solid Waste Reference Forecast Summary  

SciTech Connect

This report, which updates WHC-EP-0567, 1992 Solid Waste Reference Forecast Summary, (WHC 1992) forecasts the volumes of solid wastes to be generated or received at the US Department of Energy Hanford Site during the 30-year period from FY 1993 through FY 2022. The data used in this document were collected from Westinghouse Hanford Company forecasts as well as from surveys of waste generators at other US Department of Energy sites who are now shipping or plan to ship solid wastes to the Hanford Site for disposal. These wastes include low-level and low-level mixed waste, transuranic and transuranic mixed waste, and nonradioactive hazardous waste.

Valero, O.J.; Blackburn, C.L. [Westinghouse Hanford Co., Richland, WA (United States); Kaae, P.S.; Armacost, L.L.; Garrett, S.M.K. [Pacific Northwest Lab., Richland, WA (United States)

1993-08-01T23:59:59.000Z

493

Aluminoborosilicate Waste Glass Dissolution under Alkaline Conditions...  

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

Aluminoborosilicate Waste Glass Dissolution under Alkaline Conditions at 40C: Implications for a Chemical Affinity-Based Aluminoborosilicate Waste Glass Dissolution under...

494

Waste Management Programmatic Environmental Impact Statement...  

Office of Environmental Management (EM)

Waste Management Programmatic Environmental Impact Statement (WM PEIS) Reports and Records of Decision Waste Management Programmatic Environmental Impact Statement (WM PEIS)...

495

Radioactive Waste Management Complex Wide Review | Department...  

Office of Environmental Management (EM)

Radioactive Waste Management Complex Wide Review Radioactive Waste Management Complex Wide Review The main goal of this complex-wide review was to obtain feedback from DOE sites...

496

Independent Oversight Assessment, Waste Treatment and Immobilization...  

Office of Environmental Management (EM)

Waste Treatment and Immobilization Plant - January 2012 Independent Oversight Assessment, Waste Treatment and Immobilization Plant - January 2012 January 2012 Assessment of the...

497

Municipal Solid Waste Resources and Technologies  

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

This page provides a brief overview of municipal solid waste energy resources and technologies supplemented by specific information to apply waste to energy within the Federal sector.

498

Independent Oversight Review, Waste Treatment and Immobilization...  

Office of Environmental Management (EM)

Waste Treatment and Immobilization Plant Project - October 2010 October 2010 Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant...

499

The e-waste impact  

Science Journals Connector (OSTI)

The e-services have gained a wide range of attention and became an indispensable part of the majority of people and nations' life and living. New technology is constantly emerging making that old working gadget no longer desirable. On the other hand, ... Keywords: WEEE, e-waste, environment and health hazards, high tech waste, recycle, treatment

Mansour Jaragh; Jenan Boushahri

2009-11-01T23:59:59.000Z

500

The reduction of packaging waste  

SciTech Connect

Nationwide, packaging waste comprises approximately one-third of the waste disposed in sanitary landfills. the US Department of Energy (DOE) generated close to 90,000 metric tons of sanitary waste. With roughly one-third of that being packaging waste, approximately 30,000 metric tons are generated per year. The purpose of the Reduction of Packaging Waste project was to investigate opportunities to reduce this packaging waste through source reduction and recycling. The project was divided into three areas: procurement, onsite packaging and distribution, and recycling. Waste minimization opportunities were identified and investigated within each area, several of which were chosen for further study and small-scale testing at the Hanford Site. Test results, were compiled into five ``how-to`` recipes for implementation at other sites. The subject of the recipes are as follows: (1) Vendor Participation Program; (2) Reusable Containers System; (3) Shrink-wrap System -- Plastic and Corrugated Cardboard Waste Reduction; (4) Cardboard Recycling ; and (5) Wood Recycling.

Raney, E.A.; Hogan, J.J.; McCollom, M.L.; Meyer, R.J.

1994-04-01T23:59:59.000Z