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


1

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

2

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

3

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

4

Sodium Bearing Waste Treatment Project ? Countdown to Startup  

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

Date: March 19, 2012 Media Contact: Natalie Packer, 208-533-0253 Sodium Bearing Waste Treatment Project Countdown to Startup Marking completion of another major...

5

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

6

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

7

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

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

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

8

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

9

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

10

Feed Composition for Sodium-Bearing Waste Treatment Process  

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 by a Settlement Agreement between the Department of Energy and the State of Idaho. One of the requirements of the Settlement Agreement is to complete treatment of SBW by December 31, 2012. To support both design and development studies for the SBW treatment process, detailed feed compositions are needed. This report contains the expected compositions of these feed streams and the sources and methods used in obtaining these compositions.

Barnes, C.M.

2000-10-30T23:59:59.000Z

11

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

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

2004-05-01T23:59:59.000Z

12

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

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

IWTU Integrated Waste Treatment Unit LCO Limiting Condition for Operation LSS Life Safety Systems MSA Management Self-Assessment OFI Opportunity for Improvement ORR Operational...

13

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

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

IWTU Integrated Waste Treatment Unit LCO Limiting Condition for Operation LSS Life Safety Systems MSA Management Self-Assessment OFI Opportunity for Improvement OGC Off-Gas...

14

Electrolytic Treatment of ICPP Sodium-Bearing Waste Simulant  

SciTech Connect

Two proof-of-principle tests were conducted to determine if nitrate can be destroyed electrochemically in a simulated Idaho Chemical Processing Plant (ICPP) Sodium-Bearing waste. Both tests demonstrated the destruction of nitrate as well as the removal of other metals in the simulant. Metals removal is believed to be due to precipitation as a result of a change in the pH of the waste solution from strongly acidic to highly alkaline and reduction to a metal or metal oxide. Although gas evolution at the cathode was visible during each test, there were no visible signs of NO{sub x} formation in either test.

Hobbs, D.T.

1995-02-02T23:59:59.000Z

15

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

16

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

17

Feed Composition for Sodium-Bearing Waste Treatment Process, Rev. 3  

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 by a Settlement Agreement between the Department of Energy and the State of Idaho. One of the requirements of the Settlement Agreement is to complete treatment of SBW by December 31, 2012. To support both design and development studies for the SBW treatment process, detailed feed compositions are needed. This report contains the expected compositions of these feed streams and the sources and methods used in obtaining these compositions.

Barnes, Charles Marshall

2003-09-01T23:59:59.000Z

18

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

19

Phase 2 THOR Steam Reforming Tests for Sodium Bearing Waste Treatment  

Science Conference Proceedings (OSTI)

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

20

Steam Reforming Application for Treatment of DOE Sodium Bearing Tank Wastes at Idaho National Laboratory for Idaho Cleanup Project  

SciTech Connect

The patented THOR{sup R} 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{sup R} steam reforming process will convert the SBW tank waste feed into a dry, solid, granular product. The THOR{sup R} 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{sup R} can produce a final end-product that will meet anticipated requirements for disposal as Remote-Handled TRU (RH-TRU) waste; and, with modifications, THOR{sup R} can also produce a final end-product 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{sup R} process chemistry and process equipment being designed for the IWTU. (authors)

Mason, J.B.; Wolf, K.; Ryan, K.; Roesener, S.; Cowen, M.; Schmoker, D.; Bacala, P. [THOR Treatment Technologies, LLC, 106 Newberry St. SW, Aiken, SC 29801 (United States); Landman, B. [CH2M WG Idaho, LLC, P. O. Box 1625, Idaho Falls, ID 83415 (United States)

2006-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "bearing waste treatment" 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

Steam Reforming Application for Treatment of DOE Sodium Bearing Tank Wastes at Idaho National Laboratory for Idaho Cleanup Project  

SciTech Connect

The patented THOR{sup R} steam reforming waste treatment technology has been selected by the Department of Energy (DOE) as the technology of choice for treatment of about one million gallons of Sodium Bearing Waste (SBW) at the Idaho National Laboratory (INL). SBW is an acidic waste created primarily from cleanup of the fuel reprocessing equipment at the Idaho Nuclear Technology and Engineering Center (INTEC) at the INL. SBW contains high concentrations of nitric acid and alkali and aluminum nitrates with minor amounts of many inorganic compounds including radionuclides, mainly cesium. The steam reforming process will convert the SBW into dry, solid, carbonate and aluminate minerals supporting a preferred path for disposal as remote handled transuranic (RH-TRU) waste at the Waste Isolation Pilot Project (WIPP). The Idaho Cleanup Project (ICP) will design, build, and operate an Integrated Waste Treatment Unit (IWTU) that will comprise an integrated THOR{sup R} process system that will utilize dual fluidized bed steam reformers (FBSR) for treatment of the SBW. Design of the IWTU is nearing completion. The IWTU will be constructed at INTEC, immediately east of the New Waste Calcine Facility (NWCF), with planned fabrication and construction to start in early 2007 upon receipt of needed permits and completion of design and engineering. This paper provides a project and process overview of the IWTU and discusses the design and construction status. IWTU equipment and facility designs and bases will be presented. (authors)

Landman, W.; Roesener, S. [CH2M WG Idaho, LLC, Idaho Falls, ID (United States); Mason, B.; Wolf, K.; Amaria, N. [THOR Treatment Technologies, LLC, Aiken, SC (United States)

2007-07-01T23:59:59.000Z

22

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

23

Steam Reforming Application for Treatment of DOE Sodium-Bearing Tank Wastes at Idaho National Laboratory for Idaho Cleanup Project  

SciTech Connect

The patented THOR{sup R} steam reforming waste treatment technology has been selected by the U.S. Department of Energy (DOE) as the technology of choice for treatment of about one million gallons of sodium-bearing waste (SBW) at the Idaho National Laboratory (INL) Site 1. SBW is an acidic waste created primarily from cleanup of the fuel reprocessing equipment at the Idaho Nuclear Technology and Engineering Center (INTEC) at the INL. SBW contains high concentrations of nitric acid and alkali and aluminum nitrates with minor amounts of many inorganic compounds including radionuclides, mainly cesium. The steam reforming process will convert the SBW into dry, solid, carbonate and aluminate minerals supporting a preferred path for disposal as remote handled transuranic (RH-TRU) waste at the Waste Isolation Pilot Project (WIPP). The Idaho Cleanup Project (ICP) will design, build, and operate an Integrated Waste Treatment Unit (IWTU) that will comprise an integrated THOR{sup R} process system that will utilize dual fluidized bed steam reformers (FBSR) for treatment of the SBW. The IWTU is being constructed at INTEC, immediately east of the New Waste Calcine Facility (NWCF). Detailed design of the IWTU has been completed and DOE has approved the CD-3 detailed design. The State of Idaho has approved the RCRA and construction air permits. Construction of the IWTU started in April 2007 with civil and foundation work. This paper provides a project and process overview of the IWTU and discusses the design and construction status. IWTU equipment and facility designs and bases will be presented. (authors)

Landman, W.; Roesener, S. [CH2M-WG Idaho, LLC, Idaho Falls, ID (United States); Bradley Mason, J.; Bourgeois, T.; Amaria, N. [THOR Treatment Technologies, LLC, Aiken, SC (United States)

2008-07-01T23:59:59.000Z

24

Idaho Nuclear Technology and Engineering Center Sodium-Bearing Waste Treatment Research and Development FY-2002 Status Report  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) is considering several optional processes for disposal of liquid sodium-bearing waste. During fiscal year 2002, immobilization-related research included of grout formulation development for sodium-bearing waste, absorption of the waste on silica gel, and off-gas system mercury collection and breakthrough using activated carbon. Experimental results indicate that sodium-bearing waste can be immobilized in grout at 70 weight percent and onto silica gel at 74 weight percent. Furthermore, a loading of 11 weight percent mercury in sulfur-impregnated activated carbon was achieved with 99.8% off-gas mercury removal efficiency.

Herbst, Alan Keith; Deldebbio, John Anthony; Mc Cray, John Alan; Kirkham, Robert John; Olson, Lonnie Gene; Scholes, Bradley Adams

2002-09-01T23:59:59.000Z

25

Treatment studies of plutonium-bearing INEEL waste surrogates in a bench-scale arc furnace  

SciTech Connect

Since 1989, the Subsurface Disposal Area (SDA) at the Idaho National Environmental and Engineering Laboratory (INEEL) has been included on the National Priority List for remediation. Arc- and plasma-heated furnaces are being considered for converting the radioactive mixed waste buried in the SDA to a stabilized-vitreous form. Nonradioactive, surrogate SDA wastes have been melted during tests in these types of furnaces, but data are needed on the behavior of transuranic (TRU) constituents, primarily plutonium, during thermal treatment. To begin collecting this data, plutonium-spiked SDA surrogates were processed in a bench-scale arc furnace to quantify the fate of the plutonium and other hazardous and nonhazardous metals. Test conditions included elevating the organic, lead, chloride, and sodium contents of the surrogates. Blends having higher organic contents caused furnace power levels to fluctuate. An organic content corresponding to 50% INEEL soil in a soil-waste blend was the highest achievable before power fluctuations made operating conditions unacceptable. The glass, metal, and off-gas solids produced from each surrogate blend tested were analyzed for elemental (including plutonium) content and the partitioning of each element to the corresponding phase was calculated.

Freeman, C.J.

1997-05-01T23:59:59.000Z

26

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

Science Conference Proceedings (OSTI)

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

27

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

Science Conference Proceedings (OSTI)

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

28

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

29

Idaho Nuclear Technology and Engineering Center (INTEC) Sodium Bearing Waste - Waste Incidental to Reprocessing Determination  

SciTech Connect

U.S. Department of Energy Manual 435.1-1, Radioactive Waste Management, Section I.1.C, requires that all radioactive waste subject to Department of Energy Order 435.1 be managed as high-level radioactive waste, transuranic waste, or low-level radioactive waste. Determining the radiological classification of the sodium-bearing waste currently in the Idaho Nuclear Technology and Engineering Center Tank Farm Facility inventory is important to its proper treatment and disposition. This report presents the technical basis for making the determination that the sodium-bearing waste is waste incidental to spent fuel reprocessing and should be managed as mixed transuranic waste. This report focuses on the radiological characteristics of the sodiumbearing waste. The report does not address characterization of the nonradiological, hazardous constituents of the waste in accordance with Resource Conservation and Recovery Act requirements.

Jacobson, Victor Levon

2002-08-01T23:59:59.000Z

30

Feasibility Study for Vitrification of Sodium-Bearing Waste  

Science Conference Proceedings (OSTI)

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

31

Waste Treatment  

Science Conference Proceedings (OSTI)

...rates, and batch collection volume requirements Water conservation possibilities What is required to meet discharge limits Availability and type of treatment chemicals How sludge will be dewatered, dried, and disposed...

32

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

33

Mixed Waste Treatment Study  

Science Conference Proceedings (OSTI)

As part of an ongoing integrated mixed waste program, EPRI has documented nuclear utility industry experience in the on-site treatment of mixed waste. This report reviews all available exclusions/exceptions to EPA permitting requirements for environmentally responsible on-site management of mixed waste. Included is a description of emerging mixed waste treatment technologies along with a detailed evaluation of off-site treatment/disposal facilities.

1996-01-31T23:59:59.000Z

34

Sodium Bearing Waste Processing Alternatives Analysis  

SciTech Connect

A multidisciplinary team gathered to develop a BBWI recommendation to DOE-ID on the processing alternatives for the sodium bearing waste in the INTEC Tank Farm. Numerous alternatives were analyzed using a rigorous, systematic approach. The data gathered were evaluated through internal and external peer reviews for consistency and validity. Three alternatives were identified to be top performers: Risk-based Calcination, MACT to WIPP Calcination and Cesium Ion Exchange. A dual-path through early Conceptual design is recommended for MACT to WIPP Calcination and Cesium Ion Exchange since Risk-based Calcination does not require design. If calcination alternatives are not considered based on giving Type of Processing criteria significantly greater weight, the CsIX/TRUEX alternative follows CsIX in ranking. However, since CsIX/TRUEX shares common uncertainties with CsIX, reasonable backups, which follow in ranking, are the TRUEX and UNEX alternatives. Key uncertainties must be evaluated by the decision-makers to choose one final alternative. Those key uncertainties and a path forward for the technology roadmapping of these alternatives is provided.

Murphy, James Anthony; Palmer, Brent J; Perry, Keith Joseph

2003-12-01T23:59:59.000Z

35

Wet oxidation of oil-bearing sulfide wastes  

SciTech Connect

Oil-bearing metal sulfide sludges produced in treatment of an industrial wastewater, which includes plating wastes, have yielded to treatment by electrooxidation and hydrogen peroxide processes. The oxidation can be controlled to be mild enough to avoid decomposition of the organic phase while oxidizing the sulfides to sulfates. The pH is controlled to near neutral conditions where iron, aluminum and chromium(III) precipitate as hydrous oxides. Other metals, such as lead and barium, may be present as sulfate precipitates with limited solubility, while metals such as nickel and cadmium would be present as complexed ions in a sulfate solution. The oxidations were found to proceed smoothly, without vigorous reaction; heat liberation was minimal. 2 refs., 12 figs.

Miller, R.L.; Hotz, N.J.

1991-01-01T23:59:59.000Z

36

Treatment of Waste Soils / Solids  

Science Conference Proceedings (OSTI)

About the 1996 International Symposium on Extraction and Processing for the Treatment and Minimization of Wastes: Treatment of Waste Soils / Solids ...

37

TRUEX partitioning from radioactive ICPP sodium bearing waste  

SciTech Connect

The Idaho Chemical Processing Plant (ICPP) located at the Idaho National Engineering Laboratory in Southeast Idaho is currently evaluating several treatment technologies applicable to waste streams generated over several decades of-nuclear fuel reprocessing. Liquid sodium bearing waste (SBW), generated primarily during decontamination activities, is one of the waste streams of interest. The TRansUranic EXtraction (TRUEX) process developed at Argonne National Laboratory is currently being evaluated to separate the actinides from SBW. On a mass basis, the amount of the radioactive species in SBW are low relative to inert matrix components. Thus, the advantage of separations is a dramatic decrease in resulting volumes of high activity waste (HAW) which must be dispositioned. Numerous studies conducted at the ICPP indicate the applicability of the TRUEX process has been demonstrated; however, these studies relied on a simulated SBW surrogate for the real waste. Consequently, a series of batch contacts were performed on samples of radioactive ICPP SBW taken from tank WM-185 to verify that actual waste would behave similarly to the simulated waste. The test results with SBW from tank WM-185 indicate the TRUEX solvent effectively extracts the actinides from the samples of actual waste. Gross alpha radioactivity, attributed predominantly to Pu and Am, was reduced from 3.14E+04 dps/mL to 1.46 dps/mL in three successive batch contacts with fresh TRUEX solvent. This reduction corresponds to a decontamination factor of DF = 20,000 or 99.995% removal of the gross a activity in the feed. The TRUEX solvent also extracted the matrix components Zr, Fe, and Hg to an appreciable extent (D{sub Zr} > 10, D{sub Fe} {approx} 2, D{sub Hg} {approx}6). Iron co-extracted with the actinides can be successfully scrubbed from the organic with 0.2 M HNO{sub 3}. Mercury can be selectively partitioned from the actinides with either sodium carbonate or nitric acid ({ge} 5 M HNO{sub 3}) solutions.

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

1995-03-01T23:59:59.000Z

38

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

SciTech Connect

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

Herbst, Alan K.

2002-01-02T23:59:59.000Z

39

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

SciTech Connect

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

Herbst, Alan Keith

2002-01-01T23:59:59.000Z

40

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

Note: This page contains sample records for the topic "bearing waste treatment" 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

Review of FY 2001 Development Work 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 by the Settlement Agreement between the Department of Energy and the State of Idaho. This report discusses significant findings from vitrification technology development during 2001 and their impacts on the design basis for SBW vitrification.

Taylor, Dean Dalton; Barnes, Charles Marshall

2002-09-01T23:59:59.000Z

42

Review of FY2001 Development Work 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 by the Settlement Agreement between the Department of Energy and the State of Idaho. This report discusses significant findings from vitrification technology development during 2001 and their impacts on the design basis for SBW vitrification.

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

2002-09-09T23:59:59.000Z

43

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.

44

Glass Formulation Development for INEEL Sodium-Bearing Waste  

SciTech Connect

For about four decades, radioactive wastes have been collected and calcined from nuclear fuels reprocessing at the Idaho Nuclear Technology and Engineering Center (INTEC), formerly Idaho Chemical Processing Plant (ICPP). Over this time span, secondary radioactive wastes have also been collected and stored as liquid from decontamination, laboratory activities, and fuel-storage activities. These liquid wastes are collectively called sodium-bearing wastes (SBW). About 5.7 million liters of these wastes are temporarily stored in stainless steel tanks at the Idaho National Engineering and Environmental Laboratory (INEEL). Vitrification is being considered as an immobilization step for SBW with a number of treatment and disposal options. A systematic study was undertaken to develop a glass composition to demonstrate direct vitrification of INEEL's SBW. The objectives of this study were to show the feasibility of SBW vitrification, not a development of an optimum formulation. The waste composition is relatively high in sodium, aluminum, and sulfur. A specific composition and glass property restrictions, discussed in Section 2, were used as a basis for the development. Calculations based on first-order expansions of selected glass properties in composition and some general tenets of glass chemistry led to an additive (fit) composition (68.69 mass % SiO{sub 2}, 14.26 mass% B{sub 2}O{sub 3}, 11.31 mass% Fe{sub 2}O{sub 3}, 3.08 mass% TiO{sub 2}, and 2.67 mass % Li{sub 2}O) that meets all property restrictions when melted with 35 mass % of SBW on an oxide basis, The glass was prepared using oxides, carbonates, and boric acid and tested to confirm the acceptability of its properties. Glass was then made using waste simulant at three facilities, and limited testing was performed to test and optimize processing-related properties and confirm results of glass property testing. The measured glass properties are given in Section 4. The viscosity at 1150 C, 5 Pa{center_dot}s, is nearly ideal for waste-glass processing in a standard liquid-fed joule-heated melter. The normalized elemental releases by 7-day PCT are all well below 1 g/m{sup 2}, which is a very conservative set point used in this study. The T{sub L}, ignoring sulfate formation, is less than the 1050 C limit. Based on these observations and the reasonable waste loading of 35 mass 0/0, the SBW glass was a prime candidate for further testing. Sulfate salt segregation was observed in all test melts formed from oxidized carbonate precursors. Melts fabricated using SBW simulants suggest that the sulfate-salt segregation seen in oxide and carbonate melts was much less of a problem. The cause for the difference is likely H{sub 2}SO{sub 4} fuming during the boil-down stage of wet-slurry processing. Additionally, some crucible tests with SBW simulant were conducted at higher temperatures (1250 C), which could increase the volatility of sulfate salts. The fate of sulfate during the melting process is still uncertain and should be the topic of future studies. The properties of the simulant glass confirmed those of the oxide and carbonate glass. Corrosion tests on Inconel 690 electrodes and K-3 refractory blocks conducted at INEEL suggest that the glass is not excessively corrosive. Based on the results of this study, the authors recommend that a glass made of 35% SBW simulant (on a mass oxide and halide basis) and 65% of the additive mix (either filled or raw chemical) be used in demonstrating the direct vitrification of INEEL SBW. It is further recommended that a study be conducted to determine the fate of sulfate during glass processing and the tolerance of the chosen melter technology to sulfate salt segregation and corrosivity of the melt.

J.D. Vienna; M.J. Schweiger; D.E. Smith; H.D. Smith; J.V. Crum; D.K. Peeler; I.A. Reamer; C.A. Musick; R.D. Tillotson

1999-08-03T23:59:59.000Z

45

Glass Formulation Development for INEEL Sodium-Bearing Waste  

SciTech Connect

For about four decades, radioactive wastes have been collected and calcined from nuclear fuels reprocessing at the Idaho Nuclear Technology and Engineering Center (INTEC), formerly Idaho Chemical Processing Plant (ICPP). Over this time span, secondary radioactive wastes have also been collected and stored as liquid from decontamination, laboratory activities, and fuel-storage activities. These liquid wastes are collectively called sodium-bearing wastes (SBW). About 5.7 million liters of these wastes are temporarily stored in stainless steel tanks at the Idaho National Engineering and Environmental Laboratory (INEEL). Vitrification is being considered as an immobilization step for SBW with a number of treatment and disposal options. A systematic study was undertaken to develop a glass composition to demonstrate direct vitrification of INEEL's SBW. The objectives of this study were to show the feasibility of SBW vitrification, not a development of an optimum formulation. The waste composition is relatively high in sodium, aluminum, and sulfur. A specific composition and glass property restrictions, discussed in Section 2, were used as a basis for the development. Calculations based on first-order expansions of selected glass properties in composition and some general tenets of glass chemistry led to an additive (fit) composition (68.69 mass % SiO{sub 2}, 14.26 mass% B{sub 2}O{sub 3}, 11.31 mass% Fe{sub 2}O{sub 3}, 3.08 mass% TiO{sub 2}, and 2.67 mass % Li{sub 2}O) that meets all property restrictions when melted with 35 mass % of SBW on an oxide basis, The glass was prepared using oxides, carbonates, and boric acid and tested to confirm the acceptability of its properties. Glass was then made using waste simulant at three facilities, and limited testing was performed to test and optimize processing-related properties and confirm results of glass property testing. The measured glass properties are given in Section 4. The viscosity at 1150 C, 5 Pa{center_dot}s, is nearly ideal for waste-glass processing in a standard liquid-fed joule-heated melter. The normalized elemental releases by 7-day PCT are all well below 1 g/m{sup 2}, which is a very conservative set point used in this study. The T{sub L}, ignoring sulfate formation, is less than the 1050 C limit. Based on these observations and the reasonable waste loading of 35 mass 0/0, the SBW glass was a prime candidate for further testing. Sulfate salt segregation was observed in all test melts formed from oxidized carbonate precursors. Melts fabricated using SBW simulants suggest that the sulfate-salt segregation seen in oxide and carbonate melts was much less of a problem. The cause for the difference is likely H{sub 2}SO{sub 4} fuming during the boil-down stage of wet-slurry processing. Additionally, some crucible tests with SBW simulant were conducted at higher temperatures (1250 C), which could increase the volatility of sulfate salts. The fate of sulfate during the melting process is still uncertain and should be the topic of future studies. The properties of the simulant glass confirmed those of the oxide and carbonate glass. Corrosion tests on Inconel 690 electrodes and K-3 refractory blocks conducted at INEEL suggest that the glass is not excessively corrosive. Based on the results of this study, the authors recommend that a glass made of 35% SBW simulant (on a mass oxide and halide basis) and 65% of the additive mix (either filled or raw chemical) be used in demonstrating the direct vitrification of INEEL SBW. It is further recommended that a study be conducted to determine the fate of sulfate during glass processing and the tolerance of the chosen melter technology to sulfate salt segregation and corrosivity of the melt.

J.D. Vienna; M.J. Schweiger; D.E. Smith; H.D. Smith; J.V. Crum; D.K. Peeler; I.A. Reamer; C.A. Musick; R.D. Tillotson

1999-08-03T23:59:59.000Z

46

Treatment of organic waste  

DOE Patents (OSTI)

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

Grantham, LeRoy F. (Calabasas, CA)

1979-01-01T23:59:59.000Z

47

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

SciTech Connect

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

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

2002-09-26T23:59:59.000Z

48

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

SciTech Connect

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

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

2001-09-01T23:59:59.000Z

49

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

50

Integrated Waste Treatment Facility Fact Sheet | Department of...  

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

Waste Management Tank Waste and Waste Processing Integrated Waste Treatment Facility Fact Sheet Integrated Waste Treatment Facility Fact Sheet Waste Management Nuclear...

51

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

SciTech Connect

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

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

2001-02-01T23:59:59.000Z

52

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

SciTech Connect

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

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

2001-05-21T23:59:59.000Z

53

Independent Oversight Review, Advanced Mixed Waste Treatment...  

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

Review, Advanced Mixed Waste Treatment Project - April 2013 Independent Oversight Review, Advanced Mixed Waste Treatment Project - April 2013 April 2013 Review of Radiation...

54

Treatment of Light Metal Wastes - TMS  

Science Conference Proceedings (OSTI)

... for the Treatment and Minimization of Wastes: Treatment of Light Metal Wastes ... A Decade of Gestation: S. Street, G. Brooks and H.K. Worner, Materials Eng.

55

Independent Oversight Review, Waste Treatment and Immobilization...  

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

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

56

Independent Oversight Review, Waste Treatment and Immobilization...  

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

57

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

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

Independent Activity Report, Hanford Waste Treatment Plant - February 2011 February 2011 Hanford Waste Treatment Plant Construction Quality Assurance Review ARPT-WTP-2011-002...

58

Independent Oversight Review, Waste Treatment and Immobilization...  

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

Waste Treatment and Immobilization Plant - October 2012 October 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U. S....

59

Independent Oversight Review, Waste Treatment and Immobilization...  

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

60

Independent Oversight Review, Waste Treatment and Immobilization...  

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

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

Note: This page contains sample records for the topic "bearing waste treatment" 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

Independent Oversight Review, Waste Treatment and Immobilization...  

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

Oversight Review, Waste Treatment and Immobilization Plant - August 2011 August 2011 Hanford Waste Treatment and Immobilization Plant Construction Quality The Office of Safety...

62

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

63

Treatment of mercury containing waste  

DOE Patents (OSTI)

A process is provided for the treatment of mercury containing waste in a single reaction vessel which includes a) stabilizing the waste with sulfur polymer cement under an inert atmosphere to form a resulting mixture and b) encapsulating the resulting mixture by heating the mixture to form a molten product and casting the molten product as a monolithic final waste form. Additional sulfur polymer cement can be added in the encapsulation step if needed, and a stabilizing additive can be added in the process to improve the leaching properties of the waste form.

Kalb, Paul D. (Wading River, NY); Melamed, Dan (Gaithersburg, MD); Patel, Bhavesh R (Elmhurst, NY); Fuhrmann, Mark (Babylon, NY)

2002-01-01T23:59:59.000Z

64

Froth flotation of oil-bearing metal sulfide wastes  

SciTech Connect

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

Miller, R.L. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Atwood, R.L.; Ye, Yi [Advanced Processing Technologies, Inc., Salt Lake City, UT (United States)

1991-12-01T23:59:59.000Z

65

Froth flotation of oil-bearing metal sulfide wastes  

SciTech Connect

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

Miller, R.L. (Idaho National Engineering Lab., Idaho Falls, ID (United States)); Atwood, R.L.; Ye, Yi (Advanced Processing Technologies, Inc., Salt Lake City, UT (United States))

1991-01-01T23:59:59.000Z

66

8-Waste treatment and disposal A. Responsibility for waste management  

E-Print Network (OSTI)

8- Waste treatment and disposal A. Responsibility for waste management 1. Each worker is responsible for correctly bagging and labeling his/her own waste. 2. A BSL3 technician will be responsible for transporting and autoclaving the waste. Waste will be autoclaved once or twice per day, depending on use

67

TRAITEMENT DES EFFLUENTS WASTE TREATMENT  

E-Print Network (OSTI)

TRAITEMENT DES EFFLUENTS WASTE TREATMENT Anaerobic digestion of pig manure B. DE LA FARGE Michèle properties of the methanized effluemt are preserved. A trial on anaerobic digestion of untreated pig manure technique du Porc, Station expérimentale, Les Cabrière.l, 12200 Villefranche-de-Rouer/(ue Frctnce Anaerobic

Recanati, Catherine

68

Animal Waste Treatment System Loan Program (Missouri)  

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

The purpose of the Animal Waste Treatment System Loan Program is to finance animal waste treatment systems for independent livestock and poultry producers at below conventional interest rates. Loan...

69

Geothermal waste treatment biotechnology  

DOE Green Energy (OSTI)

Technical feasibility of a biotechnology based on biochemical reactions for detoxification of geothermal brines has been demonstrated. Laboratory-scale studies have shown that the emerging biotechnology is versatile and is applicable to a variety of geothermal sludges and materials with similar geochemical properties. Materials suitable for treatment are those which may contain few or many metals in concentrations exceeding those allowed by regulatory agencies. Comparison of several possible types of bioreactors and processes have led to the conclusion that a number of variables have to be considered in the design and development of a biochemical plant for the detoxification of geothermal type sludges. These include reactor size, effects of agitation, mixed cultures, state of the biomass, pH and dissolved oxygen, concentration of residual sludge, residence time, and temperature. Under optimum conditions, high rates of metal removal can be achieved. Some recent studies, dealing with the process variables and their optimization, will be discussed. 6 refs., 3 figs.

Premuzic, E.T.; Lin, M.S.

1991-05-01T23:59:59.000Z

70

Scanned Treatment of Mixed Incin. Waste  

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

Treatment of Mixed Incinerable Treatment of Mixed Incinerable Waste DOE/IG-0588 March 2003 Page 17 Page 18 Use of Treatment Resources Details of Finding ........................................................................1 Recommendations and Comments ............................................6 Appendices Prior Reports ...............................................................................8 Objective, Scope, and Methodology ...........................................9 Management Comments ...........................................................11 TREATMENT OF MIXED INCINERABLE WASTE TABLE OF CONTENTS Page 1 Waste Stored Rather Than Treated We found the Department of Energy (Department) was not treating its mixed incinerable solid waste expeditiously or cost-effectively.

71

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

72

ADVANCED MIXED WASTE TREATMENT PROJECT (AMWTP)  

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

ADVANCED MIXED WASTE TREATMENT PROJECT Idaho Treatment Group, LLC (ITG) Contract No. DE-EM0001467 You are here: DOE-ID Home > Contracts, Financial Assistance & Solicitations >...

73

Thermal Treatment of Solid Wastes Using the Electric Arc Furnace  

Science Conference Proceedings (OSTI)

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

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

1999-09-01T23:59:59.000Z

74

Waste Treatment and Immobilation Plant HLW Waste Vitrification...  

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

compounds VSL Vitreous State Laboratory of the Catholic University of America WESP Wet Electrostatic Precipitator WGI Washington Group International WTP Waste Treatment and...

75

DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at...  

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

Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed Waste Treatment Project: Contract will continue cleanup and waste operations at the Idaho Site DOE...

76

Mixed waste characterization, treatment & disposal focus area  

Science Conference Proceedings (OSTI)

The mission of the Mixed Waste Characterization, Treatment, and Disposal Focus Area (referred to as the Mixed Waste Focus Area or MWFA) is to provide treatment systems capable of treating DOE`s mixed waste in partnership with users, and with continual participation of stakeholders, tribal governments, and regulators. The MWFA deals with the problem of eliminating mixed waste from current and future storage in the DOE complex. Mixed waste is waste that contains both hazardous chemical components, subject to the requirements of the Resource Conservation and Recovery Act (RCRA), and radioactive components, subject to the requirements of the Atomic Energy Act. The radioactive components include transuranic (TRU) and low-level waste (LLW). TRU waste primarily comes from the reprocessing of spent fuel and the use of plutonium in the fabrication of nuclear weapons. LLW includes radioactive waste other than uranium mill tailings, TRU, and high-level waste, including spent fuel.

NONE

1996-08-01T23:59:59.000Z

77

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

78

DOE mixed waste treatment capacity analysis  

SciTech Connect

This initial DOE-wide analysis compares the reported national capacity for treatment of mixed wastes with the calculated need for treatment capacity based on both a full treatment of mixed low-level and transuranic wastes to the Land Disposal Restrictions and on treatment of transuranic wastes to the WIPP waste acceptance criteria. The status of treatment capacity is reported based on a fifty-element matrix of radiation-handling requirements and functional treatment technology categories. The report defines the classifications for the assessment, describes the models used for the calculations, provides results from the analysis, and includes appendices of the waste treatment facilities data and the waste stream data used in the analysis.

Ross, W.A.; Wehrman, R.R.; Young, J.R.; Shaver, S.R.

1994-06-01T23:59:59.000Z

79

Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank  

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

ETR Tank Waste Treatment and Immobilization Plant - Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Full Document and Summary Versions are available for download Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Summary - Flowsheet for the Hanford Waste Treatment Plant More Documents & Publications Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility

80

Water Discharge from Waste Treatment - TMS  

Science Conference Proceedings (OSTI)

Oct 29, 1996 ... TMS Logo. About the 1996 International Symposium on Extraction and Processing for the Treatment and Minimization of Wastes ...

Note: This page contains sample records for the topic "bearing waste treatment" 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

Independent Oversight Activity Report, Hanford Waste Treatment...  

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

(VSL). Bechtel National, Inc. (BNI) is the contractor responsible for the design and construction of the Hanford Site Waste Treatment and Immobilization Plant (WTP) for the...

82

Hanford Waste Treatment and Immobilization Plant Construction...  

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

conducted an independent review of selected aspects of construction quality at the Hanford Waste Treatment and Immobilization Project (WTP). The review, which was performed May...

83

Hanford Waste Treatment Plant Construction Quality Review  

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

ARPT-WTP-2011-002 Site: DOE Hanford Waste Treatment Plant Subject: Office of Independent Oversight's Office of Environment, Safety and Health Evaluations Activity Report for the...

84

DURABILITY TESTING OF FLUIDIZED BED STEAM REFORMER WASTE FORMS FOR SODIUM BEARING WASTE AT IDAHO NATIONAL LABORATORY  

SciTech Connect

Fluidized Bed Steam Reforming (FBSR) processing of Sodium Bearing Waste simulants was performed in December 2006 by THOR{sup sm} Treatment Technologies LLC (TTT) The testing was performed at the Hazen Research Inc. (HRI) pilot plant facilities in Golden, CO. FBSR products from these pilot tests on simulated waste representative of the SBW at the Idaho Nuclear Technology and Engineering Center (INTEC) were subsequently transferred to the Savannah River National Laboratory (SRNL) for characterization and leach testing. Four as-received Denitration and Mineralization Reformer (DMR) granular/powder samples and four High Temperature Filter (HTF) powder samples were received by SRNL. FBSR DMR samples had been taken from the ''active'' bed, while the HTF samples were the fines collected as carryover from the DMR. The process operated at high fluidizing velocities during the mineralization test such that nearly all of the product collected was from the HTF. Active bed samples were collected from the DMR to monitor bed particle size distribution. Characterization of these crystalline powder samples shows that they are primarily Al, Na and Si, with > 1 wt% Ca, Fe and K. The DMR samples contained less than 1 wt% carbon and the HTF samples ranged from 13 to 26 wt% carbon. X-ray diffraction analyses show that the DMR samples contained significant quantities of the Al{sub 2}O{sub 3} startup bed. The DMR samples became progressively lower in starting bed alumina with major Na/Al/Si crystalline phases (nepheline and sodium aluminosilicate) present as cumulative bed turnover occurred but 100% bed turnover was not achieved. The HTF samples also contained these major crystalline phases. Durability testing of the DMR and HTF samples using the ASTM C1285 Product Consistency Test (PCT) 7-day leach test at 90 C was performed along with several reference glass samples. Comparison of the normalized leach rates for the various DMR and HTF components was made with the reference glasses and the Low Activity Waste (LAW) specification for the Hanford Waste Treatment and Vitrification Plant (WTP). Normalized releases from the DMR and HTF samples were all less than 1 g/m{sup 2}. For comparison, normalized release from the High-Level Waste (HLW) benchmark Environmental Assessment (EA) glass for Si, Li, Na and B ranges from 2 to 8 g/m{sup 2}. The normalized release specification for LAW glass for the Hanford WTP is 2 g/m{sup 2}. The Toxicity Characteristic Leach Test (TCLP) was performed on DMR and HTF as received samples and the tests showed that these products meet the criteria for the EPA RCRA Universal Treatment Standards for all of the constituents contained in the starting simulants such as Cr, Pb and Hg (RCRA characteristically hazardous metals) and Ni and Zn (RCRA metals required for listed wastes).

Crawford, C; Carol Jantzen, C

2007-08-27T23:59:59.000Z

85

Independent Oversight Review, Waste Treatment and Immobilization Plant- December 2012  

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

Review of the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity

86

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

87

Waste Disposition Update by Doug Tonkay  

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

for disposal operations over next decade Planned Waste-Related Accomplishments * Begin treatment of Idaho's sodium bearing waste * Begin full operations of the DUF6 Conversion...

88

Alternative TRUEX-Based Pretreatment Processing of INEEL Sodium Bearing Waste  

SciTech Connect

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

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

2000-09-27T23:59:59.000Z

89

Converting Simulated Sodium-bearing Waste into a Single Solid Waste Form by Evaporation: Laboratory- and Pilot-Scale Test Results on Recycling Evaporator Overheads  

SciTech Connect

Conversion of Idaho National Engineering and Environmental Laboratory radioactive sodium-bearing waste into a single solid waste form by evaporation was demonstrated in both flask-scale and pilot-scale agitated thin film evaporator tests. A sodium-bearing waste simulant was adjusted to represent an evaporator feed in which the acid from the distillate is concentrated, neutralized, and recycled back through the evaporator. The advantage to this flowsheet is that a single remote-handled transuranic waste form is produced in the evaporator bottoms without the generation of any low-level mixed secondary waste. However, use of a recycle flowsheet in sodium-bearing waste evaporation results in a 50% increase in remote-handled transuranic volume in comparison to a non-recycle flowsheet.

Griffith, D.; D. L. Griffith; R. J. Kirkham; L. G. Olson; S. J. Losinski

2004-01-01T23:59:59.000Z

90

Treatment of Wastes Containing Arsenic, Selenium and Mercury I  

Science Conference Proceedings (OSTI)

TMS Logo. About the 1996 International Symposium on Extraction and Processing for the Treatment and Minimization of Wastes: Treatment of Wastes ...

91

Advanced Mixed Waste Treatment Project Achieves Impressive Safety...  

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

Advanced Mixed Waste Treatment Project Achieves Impressive Safety and Production Marks Advanced Mixed Waste Treatment Project Achieves Impressive Safety and Production Marks June...

92

Independent Activity Report, Hanford Waste Treatment Plant - February 2011  

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

Activity Report, Hanford Waste Treatment Plant - Activity Report, Hanford Waste Treatment Plant - February 2011 Independent Activity Report, Hanford Waste Treatment Plant - February 2011 February 2011 Hanford Waste Treatment Plant Construction Quality Assurance Review [ARPT-WTP-2011-002] The purpose of the visit was to perform a review of construction quality assurance at the Waste Treatment Plant (WTP) site activities concurrently with the Department of Energy (DOE) WTP staff. One focus area for this visit was piping and pipe support installations. Independent Activity Report, Hanford Waste Treatment Plant - February 2011 More Documents & Publications Independent Oversight Review, Waste Treatment and Immobilization Plant - August 2011 Independent Oversight Review, Waste Treatment and Immobilization Plant -

93

Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility...  

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

Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility August 18, 2011 - 12:00pm Addthis Idaho...

94

Idaho Waste Treatment Facility Improves Worker Safety and Efficiency...  

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

Waste Treatment Facility Improves Worker Safety and Efficiency, Saves Taxpayer Dollars Idaho Waste Treatment Facility Improves Worker Safety and Efficiency, Saves Taxpayer Dollars...

95

Idaho Waste Treatment Facility Startup Testing Suspended To Evaluate...  

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

Idaho Waste Treatment Facility Startup Testing Suspended To Evaluate System IDAHO FALLS, ID- On Saturday, June 16, startup testing was suspended at the Integrated Waste Treatment...

96

Independent Oversight Review, Hanford Waste Treatment and Immobilizati...  

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

Waste Treatment and Immobilization Plant - December 2013 December 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report...

97

Independent Oversight Review, Hanford Site Waste Treatment and...  

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

Waste Treatment and Immobilization Plant, August 2013 Independent Oversight Review, Hanford Site Waste Treatment and Immobilization Plant, August 2013 August 2013 Review of the...

98

Review of the Hanford Site Waste Treatment and Immobilization...  

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

WTP Waste Treatment and Immobilization Plant ii Independent Oversight Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality 1.0 PURPOSE The U....

99

Hanford Tank Waste Treatment and Immobilization Plan Project...  

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

Hanford Tank Waste Treatment and Immobilization Plan Project PIA, Richland Operations Office Hanford Tank Waste Treatment and Immobilization Plan Project PIA, Richland Operations...

100

Review of the Hanford Site Waste Treatment and Immobilization...  

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

WTP Waste Treatment and Immobilization Plant ii Independent Oversight Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality 1.0 PURPOSE The...

Note: This page contains sample records for the topic "bearing waste treatment" 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

Review of the Hanford Site Waste Treatment and Immobilization...  

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

Waste Treatment and Immobilization Plant Project 1 Independent Oversight Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality 1.0...

102

Chemical aspects of nuclear waste treatment  

SciTech Connect

The chemical aspects of the treatment of gaseous, liquid, and solid wastes are discussed in overview. The role of chemistry and the chemical reactions in waste treatment are emphasized. Waste treatment methods encompass the chemistry of radioactive elements from every group of the periodic table. In most streams, the radioactive elements are present in relatively low concentrations and are often associated with moderately large amounts of process reagents, or materials. In general, it is desirable that waste treatment methods are based on chemistry that is selective for the concentration of radionuclides and does not require the addition of reagents that contribute significantly to the volume of the treated waste. Solvent extraction, ion exchange, and sorbent chemistry play a major role in waste treatment because of the high selectivity provided for many radionuclides. This paper deals with the chemistry of the onsite treatment methods that is typically used at nuclear installations and is not concerned with the chemistry of the various alternative materials proposed for long-term storage of nuclear wastes. The chemical aspects are discussed from a generic point of view in which the chemistry of important radionuclides is emphasized.

Bond, W.D.

1980-01-01T23:59:59.000Z

103

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

104

Drilling Waste Management Fact Sheet: Thermal Treatment  

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

range from 75 to 150ton (Bansal and Sugiarto 1999). Many factors can impact treatment costs, including oil and moisture content of the waste, particle size distribution of the...

105

Independent Oversight Review, Waste Treatment and Immobilization...  

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

2013 January 2013 Review of the Hanford Waste Treatment and Immobilization Plant Black-Cell and Hard-To-Reach Pipe Spools Procurement Process and the Office of River...

106

ENVIRONMENTAL ASSESSMENT FOR WASTE WATER TREATMENT MODIFICATIONS  

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

WASTE WATER TREATMENT MODIFICATIONS WASTE WATER TREATMENT MODIFICATIONS FOR IMPROVED EFFLUENT COMPLIANCE BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK BROOKHAVEN SITE OFFICE JUNE 24, 2011 DOE/EA-1854 i Table of Contents 1.0 INTRODUCTION ............................................................................................................... 1 2.0 SUMMARY ........................................................................................................................ 1 3.0 PURPOSE AND NEED ....................................................................................................17 4.0 ALTERNATIVES ..............................................................................................................17 4.1 Alternative 1 - Groundwater Recharge System (Preferred Alternative) .............. 17

107

NORDIC WASTE WATER TREATMENT SLUDGE TREATMENT  

E-Print Network (OSTI)

biogas, electricity and fertilizer from 30 000 tons of annually waste. The plant was opened in March 2008 together it an- nually produces 18,9 GWh biogas and around 10 GWh of elec- tricity. The Cambi THP ­process

108

Waste Treatment and Immobilization Plant (WTP) Analytical Laboratory (LAB),  

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

Immobilization Plant (WTP) Analytical Immobilization Plant (WTP) Analytical Laboratory (LAB), Balance of Facilities (BOF) and Low-Activity Waste Vitrification Facilities (LAW) Waste Treatment and Immobilization Plant (WTP) Analytical Laboratory (LAB), Balance of Facilities (BOF) and Low-Activity Waste Vitrification Facilities (LAW) Full Document and Summary Versions are available for download Waste Treatment and Immobilization Plant (WTP) Analytical Laboratory (LAB), Balance of Facilities (BOF) and Low-Activity Waste Vitrification Facilities (LAW) Summary - WTP Analytical Lab, BOF and LAW Waste Vitrification Facilities More Documents & Publications Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility Waste Treatment and Immobilation Plant Pretreatment Facility Compilation of TRA Summaries

109

Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank  

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

- Tank Waste Treatment and Immobilization Plant - - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report This is a comprehensive review ofthe Hanford WTP estimate at completion - assessing the project scope, contract requirements, management execution plant, schedule, cost estimates, and risks. Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report More Documents & Publications TBH-0042 - In the Matter of Curtis Hall

110

TREATMENT OF FISSION PRODUCT WASTE  

DOE Patents (OSTI)

A pyrogenic method of separating nuclear reactor waste solutions containing aluminum and fission products as buring petroleum coke in an underground retort, collecting the easily volatile gases resulting as the first fraction, he uminum chloride as the second fraction, permitting the coke bed to cool and ll contain all the longest lived radioactive fission products in greatly reduced volume.

Huff, J.B.

1959-07-28T23:59:59.000Z

111

THE TREATMENT OF LOW ACTIVITY AQUEOUS WASTES  

SciTech Connect

The equipment and treatment methods for processing low-activity aqueous wastes at the Latina nuclear power station are discussed. The effluent treatment plant serves two purposes: purification of cooling pond water and decontamination of aqueous wastes from such outlets as regenerant solutions, active laundry and change houses, decontamination center, coffin washing, and charge machine washing. The treatment process consists of chemical precipitation followed by filtration of the sludges thus produced. The process is then followed by ion exchange on a natural inorganic material such as vermiculite and evaporation. This process produces a decontamination factor of l0/sup 3/ to 10/ sup 4/. (N.W.R.)

Cartwright, A.C.

1962-01-01T23:59:59.000Z

112

Pre-Decisional Sodium Bearing Waste Technology Development Roadmap FY-01 Update  

SciTech Connect

This report provides an update to the Sodium Bearing Waste (SBW) Technology Development Roadmap generated a year ago. It outlines progress made to date and near-term plans for the technology development work necessary to support processing SBW. In addition, it serves as a transition document to the Risk Management Plan (RMP) required by the Project per DOE Order 413.3, “Program and Project Management for the Acquisition of Capital Assets.” Technical uncertainties have been identified as design basis elements (DBEs) and captured in a technical baseline database. As the risks are discovered, assessed, and mitigated, the status of the DBEs in the database will be updated and tracked to closure.

Mc Dannel, Gary Eidson

2001-09-01T23:59:59.000Z

113

Glass Formulation Development for INEEL Sodium -Bearing Waste (FY2001 WM-180)  

SciTech Connect

A systematic study was undertaken to develop a glass composition to demonstrate the vitrification flowsheet of the Idaho National Engineering and Environmental Laboratory's sodium bearing waste (SBW) using the latest WM-180 tank composition. Although the previous study did not restrict waste loadings (WLs) based on the potential to form a segregated salt layer, avoiding its development in a melter is beneficial and was the primary focus from the glass-formulation perspective. The testing results described in this report were aimed at providing a candidate glass composition for use in a scaled melter demonstration of direct vitrification of WM-180 in the Research Scale Melter (RSM) at Pacific Northwest National Laboratory and the EV-16 melter at the Clemson Environmental Technology Laboratory.

Peeler, D.K.

2001-09-21T23:59:59.000Z

114

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

SciTech Connect

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

Kirkham, Robert John; Herbst, Alan Keith

2000-09-01T23:59:59.000Z

115

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

E-Print Network (OSTI)

The Advanced Fuel Cycle Initiative (AFCI) is a Department of Energy (DOE) program, that has been investigating technologies to improve fuel cycle sustainability and proliferation resistance. One of the program's goals is to reduce the amount of radioactive waste requiring repository disposal. Cesium and strontium are two primary heat sources during the first 300 years of spent nuclear fuel's decay, specifically isotopes Cs-137 and Sr-90. Removal of these isotopes from spent nuclear fuel will reduce the activity of the bulk spent fuel, reducing the heat given off by the waste. Once the cesium and strontium are separated from the bulk of the spent nuclear fuel, the isotopes must be immobilized. This study is focused on a method to immobilize a cesium- and strontium-bearing radioactive liquid waste stream. While there are various schemes to remove these isotopes from spent fuel, this study has focused on a nitric acid based liquid waste. The waste liquid was mixed with the bentonite, dried then sintered. To be effective sintering temperatures from 1100 to 1200 degrees C were required, and waste concentrations must be at least 25 wt%. The product is a leach resistant ceramic solid with the waste elements embedded within alumino-silicates and a silicon rich phase. The cesium is primarily incorporated into pollucite and the strontium into a monoclinic feldspar. The simulated waste was prepared from nitrate salts of stable ions. These ions were limited to cesium, strontium, barium and rubidium. Barium and rubidium will be co-extracted during separation due to similar chemical properties to cesium and strontium. The waste liquid was added to the bentonite clay incrementally with drying steps between each addition. The dry powder was pressed and then sintered at various temperatures. The maximum loading tested is 32 wt. percent waste, which refers to 13.9 wt. percent cesium, 12.2 wt. percent barium, 4.1 wt. percent strontium, and 2.0 wt. percent rubidium. Lower loadings of waste were also tested. The final solid product was a hard dense ceramic with a density that varied from 2.12 g/cm3 for a 19% waste loading with a 1200 degrees C sintering temperature to 3.03 g/cm3 with a 29% waste loading and sintered at 1100 degrees C. Differential Scanning Calorimetry and Thermal Gravimetric Analysis (DSC-TGA) of the loaded bentonite displayed mass loss steps which were consistent with water losses in pure bentonite. Water losses were complete after dehydroxylation at ~650 degrees C. No mass losses were evident beyond the dehydroxylation. The ceramic melts at temperatures greater than 1300 degrees C. Light flash analysis found heat capacities of the ceramic to be comparable to those of strontium and barium feldspars as well as pollucite. Thermal conductivity improved with higher sintering temperatures, attributed to lower porosity. Porosity was minimized in 1200 degrees C sinterings. Ceramics with waste loadings less than 25 wt% displayed slump, the lowest waste loading, 15 wt% bloated at a 1200 degrees C sintering. Waste loading above 25 wt% produced smooth uniform ceramics when sintered >1100 degrees C. Sintered bentonite may provide a simple alternative to vitrification and other engineered radioactive waste-forms.

Ortega, Luis H.

2009-12-01T23:59:59.000Z

116

Energy-Efficient Industrial Waste Treatment Technologies  

Science Conference Proceedings (OSTI)

Rising energy costs coupled with the continuing need for effective environmental treatment methods have stimulated interest in advanced energy-efficient technologies. EPRI has reviewed a wide variety of electricity-based processes for industrial air pollution control, wastewater treatment, and solid waste treatment along with some closely related competing technologies. These technologies ranged from untested concepts to well-established ones. While most offer process cost savings and improvements over e...

2007-10-31T23:59:59.000Z

117

Hanford Waste Treatment Plant Construction Quality Review  

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

ARPT-WTP-2011-002 ARPT-WTP-2011-002 Site: DOE Hanford Waste Treatment Plant Subject: Office of Independent Oversight's Office of Environment, Safety and Health Evaluations Activity Report for the Hanford Waste Treatment Plant Construction Quality Review Dates of Activity 02/14/2011 - 02/17/2011 Report Preparer Joseph Lenahan Activity Description/Purpose: The purpose of the visit was to perform a review of construction quality assurance at the Waste Treatment Plant (WTP) site activities concurrently with the Department of Energy (DOE) WTP staff. One focus area for this visit was piping and pipe support installations. The Office of Health, Safety and Security (HSS) attended several Bechtel National Incorporated (BNI) project meetings, reviewed the WTP project quality assurance program, reviewed DOE-WTP inspection reports completed by the DOE-WTP

118

Independent Activity Report, Waste Treatment and Immobilization Plant- March 2013  

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

Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review [HIAR-WTP-2013-03-18

119

Activity Report for Waste Treatment and Immobilizationi Plant...  

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

and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Waste Treatment and Immobilization Plant Low Activity Waste Melter Off-gas Process...

120

Audit Report Waste Treatment Plans at the Idaho National Engineering...  

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

Waste Reduction Plans for the Advanced Mixed Waste TreatmentProject at the Idaho National Engineering and EnvironmentalLaboratory, IG-0611 Energy.gov Careers & Internships Hotline...

Note: This page contains sample records for the topic "bearing waste treatment" 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

WASTE TREATMENT BUILDING VENTILATION SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect

The Waste Treatment Building Ventilation System provides heating, ventilation, and air conditioning (HVAC) for the contaminated, potentially contaminated, and uncontaminated areas of the Monitored Geologic Repository's (MGR) Waste Treatment Building (WTB). In the uncontaminated areas, the non-confinement area ventilation system maintains the proper environmental conditions for equipment operation and personnel comfort. In the contaminated and potentially contaminated areas, in addition to maintaining the proper environmental conditions for personnel comfort and equipment operation, the contamination confinement area ventilation system directs potentially contaminated air away from personnel in the WTB and confines the contamination within high-efficiency particulate air (HEPA) filtration units. The contamination confinement area ventilation system creates airflow paths and pressure zones to minimize the potential for spreading contamination with the building. The contamination confinement ventilation system also protects the environment and the public by limiting airborne releases of radioactive or other hazardous contaminants from the WTB. The Waste Treatment Building Ventilation System confines the radioactive and hazardous material within the building such that the release rates comply with regulatory limits, The system design, operations, and maintenance activities incorporate ALARA (as low as is reasonably achievable) principles to maintain personnel radiation doses to all occupational workers below regulatory limits and as low as is reasonably achievable. The system provides status of important system parameters and equipment operation, and provides audible and/or visual indication of off-normal conditions and equipment failures. The Waste Treatment Building Ventilation System interfaces with the Waste Treatment Building System by being located in the WTB, and by maintaining specific pressure, temperature, and humidity environments within the building. The system also depends on the WTB for normal electric power supply and the required supply of water for heating, cooling, and humidification. Interface with the Waste Treatment Building System includes the WTB fire protection subsystem for detection of fire and smoke. The Waste Treatment Building Ventilation System interfaces with the Site Radiological Monitoring System for continuous monitoring of the exhaust air and key areas within the WTB, the Monitored Geologic Repository Operations Monitoring and Control System for monitoring and control of system operations, and the Site Generated Radiological Waste Handling System and Site Generated Hazardous, Non-Hazardous & Sanitary Waste Disposal System for routing of pretreated toxic, corrosive, and radiologically contaminated effluent from process equipment to the HEPA filter exhaust ductwork and air-cleaning unit.

P.A. Kumar

2000-06-22T23:59:59.000Z

122

Biological treatment of refinery wastes  

SciTech Connect

A detailed study of the treatment situation at a Thai refinery that used an API separator with no equalization tank, followed by an activated-sludge system, showed that only 42% of the total COD and 57% of the soluble COD was degradable. In a study of the possibility of additional treatments, an aerated lagoon showed promising results. The wastewater composition of the three main Thai refineries was surveyed.

Mahmud, Z.; Thanh, N.C.

1978-01-01T23:59:59.000Z

123

Medical waste treatment and decontamination system  

DOE Patents (OSTI)

The invention discloses a tandem microwave system consisting of a primary chamber in which hybrid microwave energy is used for the controlled combustion of materials. A second chamber is used to further treat the off-gases from the primary chamber by passage through a susceptor matrix subjected to additional hybrid microwave energy. The direct microwave radiation and elevated temperatures provide for significant reductions in the qualitative and quantitative emissions of the treated off gases. The tandem microwave system can be utilized for disinfecting wastes, sterilizing materials, and/or modifying the form of wastes to solidify organic or inorganic materials. The simple design allows on-site treatment of waste by small volume waste generators.

Wicks, George G. (Aiken, SC); Schulz, Rebecca L. (Aiken, SC); Clark, David E. (Gainesville, FL)

2001-01-01T23:59:59.000Z

124

Treatment of Radioactive Reactive Mixed Waste  

Science Conference Proceedings (OSTI)

PacificEcoSolutions, Inc. (PEcoS) has installed a plasma gasification system that was recently modified and used to destroy a trimethyl-aluminum mixed waste stream from Los Alamos National Laboratory (LANL.) The unique challenge in handling reactive wastes like trimethyl-aluminum is their propensity to flame instantly on contact with air and to react violently with water. To safely address this issue, PacificEcoSolutions has developed a new feed system to ensure the safe containment of these radioactive reactive wastes during transfer to the gasification unit. The plasma gasification system safely processed the radioactively contaminated trimethyl-metal compounds into metal oxides. The waste stream came from LANL research operations, and had been in storage for seven years, pending treatment options. (authors)

Colby, S.; Turner, Z.; Utley, D. [Pacific EcoSolutions, Inc., 2025 Battelle Boulevard, Richland, Washington 99354 (United States); Duy, C. [Los Alamos National Laboratory - LA-UR-05-8410, Post Office Box 1663 MS J595, Los Alamos, New Mexico 97545 (United States)

2006-07-01T23:59:59.000Z

125

Land Disposal Restrictions Treatment Standards: Compliance Strategies for Four Types of Mixed Wastes  

Science Conference Proceedings (OSTI)

This paper describes the unique challenges involved in achieving compliance with the Resource Conservation and Recovery Act (Public Law 94-580) Land Disposal Restrictions (LDR) treatment standards for four types of mixed wastes generated throughout the U.S. Department of Energy (DOE) complex: (1) radioactively contaminated lead acid batteries; (2) radioactively contaminated cadmium-, mercury-, and silver-containing batteries; (3) mercury-bearing mixed wastes; and (4) radioactive lead solids. For each of these mixed waste types, the paper identifies the strategy pursued by DOE's Office of Pollution Prevention and Resource Conservation Policy and Guidance (EH-43) in coordination with other DOE elements and the U.S. Environmental Protection Agency (EPA) to meet the compliance challenge. Specifically, a regulatory interpretation was obtained from EPA agreeing that the LDR treatment standard for wastes in the D008 'Radioactive Lead Solids' sub-category applies to radioactively contaminated lead acid batteries. For cadmium-, mercury-, and silver-containing batteries, generically applicable treatability variances were obtained from EPA approving macro-encapsulation as the alternative LDR treatment standard for all three battery types. Joint DOE/EPA technology demonstrations were pursued for mercury-bearing mixed wastes in an effort to justify revising the LDR treatment standards, which focus on thermal recovery of mercury for reuse. Because the demonstrations failed to produce enough supporting data for a rulemaking, however, EPA has recommended site-specific treatability variances for particular mercury-bearing mixed waste streams. Finally, DOE has filed an application for a determination of equivalent treatment requesting approval of container-based macro-encapsulation technologies as an alternative LDR treatment standard for radioactive lead solids. Information is provided concerning the length of time required to implement each of these strategies, and suggestions for obtaining variances from the LDR treatment standards at the site-specific level are also discussed. (authors)

Fortune, W.B. [U.S, Department of Energy, Office of Pollution Prevention and Resource Conservation (EH-43), 1000 Independence Ave., S.W., Washington, DC 20585 (United States); Ranek, N.L. [Argonne National Laboratory, Environmental Science Division, 955 L'Enfant Plaza North, Suite 6000, Washington, DC 20024 (United States)

2006-07-01T23:59:59.000Z

126

IDAHO SITE TO PROVIDE WASTE TREATMENT FOR OTHER DOE SITES  

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

March 7, 2008 IDAHO SITE TO PROVIDE WASTE TREATMENT FOR OTHER DOE SITES Plan won't impact DOE commitment to removing all stored waste from Idaho Site Idaho's Advanced Mixed Waste...

127

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

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

Carbon Reduction Reformer CWI CH2M-WG Idaho, LLC DMR Denitration Mineralization Reformer DOE U.S. Department of Energy DOE-ID DOE Idaho Operations Office D-ORR DOE Operational...

128

Idaho Site Launches Startup of Waste Treatment Facility Following Federal  

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

Launches Startup of Waste Treatment Facility Following Launches Startup of Waste Treatment Facility Following Federal Inspection, DOE Milestone Idaho Site Launches Startup of Waste Treatment Facility Following Federal Inspection, DOE Milestone April 23, 2012 - 12:00pm Addthis A controlled, phased startup of the Integrated Waste Treatment Unit began today after the facility passed a federal inspection. A controlled, phased startup of the Integrated Waste Treatment Unit began today after the facility passed a federal inspection. A view of the interior of the Integrated Waste Treatment Unit. A view of the interior of the Integrated Waste Treatment Unit. A controlled, phased startup of the Integrated Waste Treatment Unit began today after the facility passed a federal inspection. A view of the interior of the Integrated Waste

129

Idaho Site Launches Startup of Waste Treatment Facility Following Federal  

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

Idaho Site Launches Startup of Waste Treatment Facility Following Idaho Site Launches Startup of Waste Treatment Facility Following Federal Inspection, DOE Milestone Idaho Site Launches Startup of Waste Treatment Facility Following Federal Inspection, DOE Milestone April 23, 2012 - 12:00pm Addthis A controlled, phased startup of the Integrated Waste Treatment Unit began today after the facility passed a federal inspection. A controlled, phased startup of the Integrated Waste Treatment Unit began today after the facility passed a federal inspection. A view of the interior of the Integrated Waste Treatment Unit. A view of the interior of the Integrated Waste Treatment Unit. A controlled, phased startup of the Integrated Waste Treatment Unit began today after the facility passed a federal inspection. A view of the interior of the Integrated Waste

130

Idaho Site Launches Corrective Actions Before Restarting Waste Treatment  

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

Corrective Actions Before Restarting Waste Corrective Actions Before Restarting Waste Treatment Facility Idaho Site Launches Corrective Actions Before Restarting Waste Treatment Facility September 13, 2012 - 12:00pm Addthis Pictured here is the Integrated Waste Treatment Unit's off-gas filter following the June incident. Pictured here is the Integrated Waste Treatment Unit's off-gas filter following the June incident. A view of the process piping installations prior to startup of the Integrated Waste Treatment Unit. A view of the process piping installations prior to startup of the Integrated Waste Treatment Unit. Pictured here is the Integrated Waste Treatment Unit's off-gas filter following the June incident. A view of the process piping installations prior to startup of the Integrated Waste Treatment Unit.

131

Plutonium Finishing Plan (PFP) Treatment and Storage Unit Waste Analysis Plan  

Science Conference Proceedings (OSTI)

The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Plutonium Finishing Plant Treatment and Storage Unit (PFP Treatment and Storage Unit) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (4)(a) and (5). The PFP Treatment and Storage Unit is an interim status container management unit for plutonium bearing mixed waste radiologically managed as transuranic (TRU) waste. TRU mixed (TRUM) waste managed at the PFP Treatment and Storage Unit is destined for the Waste Isolation Pilot Plant (WIPP) and therefore is not subject to land disposal restrictions [WAC 173-303-140 and 40 CFR 268]. The PFP Treatment and Storage Unit is located in the 200 West Area of the Hanford Facility, Richland Washington (Figure 1). Because dangerous waste does not include 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.

PRIGNANO, A.L.

2000-07-01T23:59:59.000Z

132

Composition and Simulation of Tank WM-180 Sodium Bearing Waste at INTEC  

SciTech Connect

The 1-million liters of sodium-bearing waste in the WM-180 tank at the Idaho Nuclear Technology and Engineering Center has been concentrated and will be the first to be processed, at its current composition, by vitrification to prepare the radioactive waste for disposition. The waste has been sampled and analyzed for cations, anions, and radionuclides in the liquid and in the small amount of solids that were entrained with the liquid during sampling. The analytical results have been evaluated and a non-radioactive simulant composition and preparation procedure developed and demonstrated to result in a clear solution. 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. The solids entrained from the tank with the liquid sample amount to 0.06% of the dissolved solids in the liquid. While their elemental and radionuclide composition was determined, qualitative characterization using x-ray diffraction was not possible. Because of the interest in the properties of solids that may be in the bottom of the WM-180 tank, for tank closure activities, thermodynamic modeling was performed of potential precipitates that may be in equilibrium with the solution. The results were used to derive a possible chemical composition of the solids.

Christian, Jerry Dale

2001-04-01T23:59:59.000Z

133

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

Science Conference Proceedings (OSTI)

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

134

Advanced Mixed Waste Treatment: Results of Mixed Waste Treatment at the M-4 Facility  

Science Conference Proceedings (OSTI)

Processing alternatives for commercial nuclear plant mixed wastes are limited. In order to expand potential treatment options, EPRI entered a collaborative research agreement to process mixed wastes at an environmental facility. This report documents the success of that effort to date.

1997-12-31T23:59:59.000Z

135

RETRIEVAL & TREATMENT OF HANFORD TANK WASTE  

SciTech Connect

The Hanford Tank Farms contain 53 million gal of radioactive waste accumulated during over 50 years of operations. The waste is stored in 177 single-shell and double-shell tanks in the Hanford 200 Areas. The single-shell tanks were put into operation from the early 1940s through the 1960s with wastes received from several generations of processing facilities for the recovery of plutonium and uranium, and from laboratories and other ancillary facilities. The overall hanford Tank Farm system represents one of the largest nuclear legacies in the world driving towards completion of retrieval and treatment in 2028 and the associated closure activity completion by 2035. Remote operations, significant radiation/contamination levels, limited access, and old facilities are just some of the challenges faced by retrieval and treatment systems. These systems also need to be able to successfully remove 99% or more of the waste, and support waste treatment, and tank closure. The Tank Farm retrieval program has ramped up dramatically in the past three years with design, fabrication, installation, testing, and operations ongoing on over 20 of the 149 single-shell tanks. A variety of technologies are currently being pursued to retrieve different waste types, applications, and to help establish a baseline for recovery/operational efficiencies. The paper/presentation describes the current status of retrieval system design, fabrication, installation, testing, readiness, and operations, including: (1) Saltcake removal progress in Tanks S-102, S-109, and S-112 using saltcake dissolution, modified sluicing, and high pressure water lancing techniques; (2) Sludge vacuum retrieval experience from Tanks C-201, C-202, C-203, and C-204; (3) Modified sluicing experience in Tank C-103; (4) Progress on design and installation of the mobile retrieval system for sludge in potentially leaking single-shell tanks, particularly Tank C-101; and (5) Ongoing installation of various systems in the next generation of tanks to be retrieved.

EACKER, J.A.; SPEARS, J.A.; STURGES, M.H.; MAUSS, B.M.

2006-01-20T23:59:59.000Z

136

Biological treatment of hazardous aqueous wastes  

Science Conference Proceedings (OSTI)

Studies were conducted with a rotating biological conractor (RBC) to evaluate the treatability of leachates from the Stringfellow and New Lyme hazardous-waste sites. The leachates were transported from the waste sites to Cincinnati at the United States Environmental Protection Agency's Testing and Evaluation Facility. A series of batches were run with primary effluent from Cincinnati's Mill Creek Sewage Treatment Facility. The paper reports on the results from these experiments and the effectiveness of an RBC to adequately treat leachates from Superfund sites.

Opatken, E.J.; Howard, H.K.; Bond, J.J.

1987-06-01T23:59:59.000Z

137

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

SciTech Connect

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

Wood, Richard Arthur

2001-09-01T23:59:59.000Z

138

Steam Reforming Technology Demonstration for Conversion of DOE Sodium-Bearing Tank Wastes at Idaho National Laboratory into a Leach-Resistant Alkali Aluminosilicate Waste Form  

Science Conference Proceedings (OSTI)

The patented THOR{sup R} fluidized-bed steam reforming (FBSR) technology was selected by the U.S. Department of Energy (DOE) for treatment of sodium-bearing waste (SBW) in the Integrated Waste Treatment Unit (IWTU), currently under construction at the Idaho National Laboratory (INL) Site.1 SBW is an acidic waste created primarily from cleanup of the fuel reprocessing equipment at the Idaho Nuclear Technology and Engineering Center (INTEC) at the INL. The SBW contains high concentrations of nitric acid, and alkali and aluminum nitrates, along with many other inorganic compounds, including substantial levels of radionuclides. As part of the implementation of the THOR{sup R} process at INTEC, an engineering-scale technology demonstration (ESTD) was conducted using a specially designed pilot plant located at Hazen Research, Inc. in Golden Colorado. This ESTD confirmed the efficacy of the THOR{sup R} FBSR process to convert the SBW into a granular carbonate-based waste form suitable for disposal at the Waste Isolation Pilot Plant (WIPP). DOE authorized, as a risk reduction measure, the performance of an additional ESTD to demonstrate the production of an insoluble mineralized product, in the event that an alternate disposition path is required. The additional ESTD was conducted at the Hazen Research facility using the THOR{sup R} process and the same SBW simulant employed previously. An alkali aluminosilicate mineral product was produced that exhibited excellent leach resistance and chemical durability. The demonstration established general system operating parameters for a full-scale facility; provided process off-gas data that confirmed operation within regulatory limits; determined that the mineralized product exhibits superior leach resistance and durability, compared to Environmental Assessment (EA) and Low-activity Reference Material (LRM) glasses, as indicated by the Product Consistency Test (PCT); ascertained that Cs and Re (a surrogate for Tc) were non-volatile and were retained in the mineral product; and showed that heavy metals were converted into mineral forms that were not leachable, as determined by the Toxicity Characteristic Leaching Procedure (TCLP) test. (authors)

Ryan, K.; Bradley Mason, J.; Evans, B.; Vora, V. [THOR Treatment Technologies, LLC, Aiken, SC (United States); Olson, A. [CH2M-WG Idaho, LLC, Idaho Falls, ID (United States)

2008-07-01T23:59:59.000Z

139

WASTE TREATMENT TECHNOLOGY PROCESS DEVELOPMENT PLAN FOR HANFORD WASTE TREATMENT PLANT LOW ACTIVITY WASTE RECYCLE  

SciTech Connect

The purpose of this Process Development Plan is to summarize the objectives and plans for the technology development activities for an alternative path for disposition of the recycle stream that will be generated in the Hanford Waste Treatment Plant Low Activity Waste (LAW) vitrification facility (LAW Recycle). This plan covers the first phase of the development activities. The baseline plan for disposition of this stream is to recycle it to the WTP Pretreatment Facility, where it will be concentrated by evaporation and returned to the LAW vitrification facility. Because this stream contains components that are volatile at melter temperatures and are also problematic for the glass waste form, they accumulate in the Recycle stream, exacerbating their impact on the number of LAW glass containers. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and reducing the halides in the Recycle is a key component of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, this stream does not have a proven disposition path, and resolving this gap becomes vitally important. This task seeks to examine the impact of potential future disposition of this stream in the Hanford tank farms, and to develop a process that will remove radionuclides from this stream and allow its diversion to another disposition path, greatly decreasing the LAW vitrification mission duration and quantity of glass waste. The origin of this LAW Recycle stream will be from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover or precipitates of scrubbed components (e.g. carbonates). The soluble components are mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet, and will not be available until the WTP begins operation, causing uncertainty in its composition, particularly the radionuclide content. This plan will provide an estimate of the likely composition and the basis for it, assess likely treatment technologies, identify potential disposition paths, establish target treatment limits, and recommend the testing needed to show feasibility. Two primary disposition options are proposed for investigation, one is concentration for storage in the tank farms, and the other is treatment prior to disposition in the Effluent Treatment Facility. One of the radionuclides that is volatile and expected to be in high concentration in this LAW Recycle stream is Technetium-99 ({sup 99}Tc), a long-lived radionuclide with a half-life of 210,000 years. Technetium will not be removed from the aqueous waste in the Hanford Waste Treatment and Immobilization Plant (WTP), and will primarily end up immobilized in the LAW glass, which will be disposed in the Integrated Disposal Facility (IDF). Because {sup 99}Tc has a very long half-life and is highly mobile, it is the largest dose contributor to the Performance Assessment (PA) of the IDF. Other radionuclides that are also expected to be in appreciable concentration in the LAW Recycle are {sup 129}I, {sup 90}Sr, {sup 137}Cs, and {sup 241}Am. The concentrations of these radionuclides in this stream will be much lower than in the LAW, but they will still be higher than limits for some of the other disposition pathways currently available. Although the baseline process will recycle this stream to the Pretreatment Facility, if the LAW facility begins operation first, this stream will not have a disposition path internal to WTP. One potential solution is to return the stream to the tank farms where it can be evaporated in the 242- A evaporator, or perhaps deploy an auxiliary evaporator to concentrate it prior to return to the tank farms. In either case, testing is needed to evalua

McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.

2013-08-29T23:59:59.000Z

140

Integrated Waste Treatment Unit GFSI Risk Management Plan  

SciTech Connect

This GFSI Risk Management Plan (RMP) describes the strategy for assessing and managing project risks for the Integrated Waste Treatment Unit (IWTU) that are specifically within the control and purview of the U.S. Department of Energy (DOE), and identifies the risks that formed the basis for the DOE contingency included in the performance baseline. DOE-held contingency is required to cover cost and schedule impacts of DOE activities. Prior to approval of the performance baseline (Critical Decision-2) project cost contingency was evaluated during a joint meeting of the Contractor Management Team and the Integrated Project Team for both contractor and DOE risks to schedule and cost. At that time, the contractor cost and schedule risk value was $41.3M and the DOE cost and schedule risk contingency value is $39.0M. The contractor cost and schedule risk value of $41.3M was retained in the performance baseline as the contractor's management reserve for risk contingency. The DOE cost and schedule risk value of $39.0M has been retained in the performance baseline as the DOE Contingency. The performance baseline for the project was approved in December 2006 (Garman 2006). The project will continue to manage to the performance baseline and change control thresholds identified in PLN-1963, ''Idaho Cleanup Project Sodium-Bearing Waste Treatment Project Execution Plan'' (PEP).

W. A. Owca

2007-06-21T23:59:59.000Z

Note: This page contains sample records for the topic "bearing waste treatment" 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

Integrated Waste Treatment Unit GFSI Risk Management Plan  

SciTech Connect

This GFSI Risk Management Plan (RMP) describes the strategy for assessing and managing project risks for the Integrated Waste Treatment Unit (IWTU) that are specifically within the control and purview of the U.S. Department of Energy (DOE), and identifies the risks that formed the basis for the DOE contingency included in the performance baseline. DOE-held contingency is required to cover cost and schedule impacts of DOE activities. Prior to approval of the performance baseline (Critical Decision-2) project cost contingency was evaluated during a joint meeting of the Contractor Management Team and the Integrated Project Team for both contractor and DOE risks to schedule and cost. At that time, the contractor cost and schedule risk value was $41.3M and the DOE cost and schedule risk contingency value is $39.0M. The contractor cost and schedule risk value of $41.3M was retained in the performance baseline as the contractor's management reserve for risk contingency. The DOE cost and schedule risk value of $39.0M has been retained in the performance baseline as the DOE Contingency. The performance baseline for the project was approved in December 2006 (Garman 2006). The project will continue to manage to the performance baseline and change control thresholds identified in PLN-1963, ''Idaho Cleanup Project Sodium-Bearing Waste Treatment Project Execution Plan'' (PEP).

W. A. Owca

2007-06-21T23:59:59.000Z

142

Department of Energy Idaho - Advanced Mixed Waste Treatment Project...  

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

> AMWTP Contract Idaho Treatment Group, LLC (ITG) Advanced Mixed Waste Treatment Project Contract Basic Contract Contract Modifications Documents Related to the AMWTP Contract Last...

143

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

Science Conference Proceedings (OSTI)

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

144

Waste Treatment and Immobilation Plant Pretreatment Facility  

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

7 7 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) Pretreatment Facility L. Holton D. Alexander M. Johnson H. Sutter August 2007 Prepared by the U.S. Department of Energy Office of River Protection Richland, Washington, 99352 07-DESIGN-047 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) Pretreatment Facilities L. Holton D. Alexander M. Johnson H. Sutter August 2007 Prepared by the U.S. Department of Energy Office of River Protection under Contract DE-AC05-76RL01830 07-DESIGN-047 iii Summary The U.S. Department of Energy (DOE), Office of River Protection (ORP) and the DOE Office of Environmental Management (EM), Office of Project Recovery has completed a Technology Readiness

145

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

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

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework 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 High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

146

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

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

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework 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 High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

147

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

148

Waste management system alternatives for treatment of wastes from spent fuel reprocessing  

SciTech Connect

This study was performed to help identify a preferred TRU waste treatment alternative for reprocessing wastes with respect to waste form performance in a geologic repository, near-term waste management system risks, and minimum waste management system costs. The results were intended for use in developing TRU waste acceptance requirements that may be needed to meet regulatory requirements for disposal of TRU wastes in a geologic repository. The waste management system components included in this analysis are waste treatment and packaging, transportation, and disposal. The major features of the TRU waste treatment alternatives examined here include: (1) packaging (as-produced) without treatment (PWOT); (2) compaction of hulls and other compactable wastes; (3) incineration of combustibles with cementation of the ash plus compaction of hulls and filters; (4) melting of hulls and failed equipment plus incineration of combustibles with vitrification of the ash along with the HLW; (5a) decontamination of hulls and failed equipment to produce LLW plus incineration and incorporation of ash and other inert wastes into HLW glass; and (5b) variation of this fifth treatment alternative in which the incineration ash is incorporated into a separate TRU waste glass. The six alternative processing system concepts provide progressively increasing levels of TRU waste consolidation and TRU waste form integrity. Vitrification of HLW and intermediate-level liquid wastes (ILLW) was assumed in all cases.

McKee, R.W.; Swanson, J.L.; Daling, P.M.; Clark, L.L.; Craig, R.A.; Nesbitt, J.F.; McCarthy, D.; Franklin, A.L.; Hazelton, R.F.; Lundgren, R.A.

1986-09-01T23:59:59.000Z

149

Idaho's Advanced Mixed Waste Treatment Project Details 2013  

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

Idaho's Advanced Mixed Waste Treatment Project Details 2013 Idaho's Advanced Mixed Waste Treatment Project Details 2013 Accomplishments Idaho's Advanced Mixed Waste Treatment Project Details 2013 Accomplishments December 24, 2013 - 12:00pm Addthis IDAHO FALLS, Idaho - EM and its contractor, Idaho Treatment Group (ITG), safely and compliantly met all of their production and shipping targets in the Advanced Mixed Waste Treatment Project (AMWTP) at the Idaho site in 2013. AMWTP's purpose is to safely process and dispose of transuranic (TRU) and mixed low-level waste (MLLW). The defense-related TRU waste is sent to the Waste Isolation Pilot Plant in New Mexico, and the MLLW is sent to other federal and commercial disposal sites. AMWTP is the largest shipper of contact-handled TRU waste to WIPP. In 2013, AMWTP sent 2,444.69 cubic

150

Idaho's Advanced Mixed Waste Treatment Project Details 2013  

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

Idaho's Advanced Mixed Waste Treatment Project Details 2013 Idaho's Advanced Mixed Waste Treatment Project Details 2013 Accomplishments Idaho's Advanced Mixed Waste Treatment Project Details 2013 Accomplishments December 24, 2013 - 12:00pm Addthis IDAHO FALLS, Idaho - EM and its contractor, Idaho Treatment Group (ITG), safely and compliantly met all of their production and shipping targets in the Advanced Mixed Waste Treatment Project (AMWTP) at the Idaho site in 2013. AMWTP's purpose is to safely process and dispose of transuranic (TRU) and mixed low-level waste (MLLW). The defense-related TRU waste is sent to the Waste Isolation Pilot Plant in New Mexico, and the MLLW is sent to other federal and commercial disposal sites. AMWTP is the largest shipper of contact-handled TRU waste to WIPP. In 2013, AMWTP sent 2,444.69 cubic

151

Waste treatment by selective mineral ion exchanger  

Science Conference Proceedings (OSTI)

STMI, subsidiary company of the AREVA Group with over 40 years in the D and D business, has been continuously innovating and developing new decontamination techniques, with the objectives of achieving more efficient decontaminations on a growing spectrum of media. In the field of liquid waste treatment, STMI manufactures uses and commercialises selective inorganic ion exchangers (RAN). These are hydrated synthetic inorganic compounds prepared from very pure raw materials. Different types of RANs (POLYAN, OXTAIN, Fe-Cu, Fe-CoK, Si-Fe-CoK) can be used to trap a large number of radioactive elements in contaminated effluents. Different implementations could be applied depending on technical conditions. STMI's offers consist in building global solution and preliminary design of installation either in dispersed form (batch) or in column (cartridge filtration). Those products are used all over the world not only in the nuclear business (Canada, US, Belgium, France...) but also in other fields. Indeed, it provides competitive solutions to many domains of application especially water pollution control, liquid waste treatment in the nuclear business by decreasing the activity level of waste. The following paper will focus on the theoretical principle of the mineral exchanger, its implementation and the feed back collected by STMI. (author)

Polito, Aurelie [Areva NC - BUA STMI, 1 route de la Noue - 91196 Gif sur Yvette, Cedex (France)

2007-07-01T23:59:59.000Z

152

Analysis of waste treatment requirements for DOE mixed wastes: Technical basis  

SciTech Connect

The risks and costs of managing DOE wastes are a direct function of the total quantities of 3wastes that are handled at each step of the management process. As part of the analysis of the management of DOE low-level mixed wastes (LLMW), a reference scheme has been developed for the treatment of these wastes to meet EPA criteria. The treatment analysis in a limited form was also applied to one option for treatment of transuranic wastes. The treatment requirements in all cases analyzed are based on a reference flowsheet which provides high level treatment trains for all LLMW. This report explains the background and basis for that treatment scheme. Reference waste stream chemical compositions and physical properties including densities were established for each stream in the data base. These compositions are used to define the expected behavior for wastes as they pass through the treatment train. Each EPA RCRA waste code was reviewed, the properties, chemical composition, or characteristics which are of importance to waste behavior in treatment were designated. Properties that dictate treatment requirements were then used to develop the treatment trains and identify the unit operations that would be included in these trains. A table was prepared showing a correlation of the waste physical matrix and the waste treatment requirements as a guide to the treatment analysis. The analysis of waste treatment loads is done by assigning wastes to treatment steps which would achieve RCRA compliant treatment. These correlation`s allow one to examine the treatment requirements in a condensed manner and to see that all wastes and contaminant sets are fully considered.

1995-02-01T23:59:59.000Z

153

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

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

Treatment and Immobilization Treatment and Immobilization Plant - November 2011 Independent Oversight Review, Waste Treatment and Immobilization Plant - November 2011 November 2011 Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality The Office of Enforcement and Oversight (Independent Oversight) within the Office of Health, Safety and Security conducted an independent review of selected aspects of construction quality at the Hanford Waste Treatment and Immobilization Plant Project (WTP). The independent oversight review, which was performed September 12-15, 2011, was the latest in a series of ongoing quarterly assessments of construction quality at the WTP construction site. Independent Oversight Review, Waste Treatment and Immobilization Plant -

154

TRUEX flowsheet development as applied to ICPP sodium-bearing waste using centrifugal contactors  

SciTech Connect

Previous lab-scale work using batch contacts with sodium- bearing waste (SEW) simulant and samples of radioactive SEW from tank WM-185 suggested a potential flowsheet for partitioning actinides using solvent extraction (the TRUEX process). The suggested baseline flowsheet includes: an extraction section to remove actinides from liquid SEW into the TRUEX solvent (0.2 M CMP01 1.4 M TBP in Isopar-L); a dilute nitric acid scrub (0.07- 0.2 M HNO{sub 3}) to back extract co-extracted matrix materials (primarily Fe, Zr, and HNO{sub 3}) from the loaded solvent; thermally unstable complexants (TUCS) to back extract actinides; and a carbonate wash section for solvent cleanup. The purpose of the flowsheet development studies was to test and develop the baseline TRUEX flowsheet for ICPP SEW under continuous, countercurrent conditions using centrifugal contactors. All testing was performed using non-radioactive SEW simulant. Potential flowsheets were evaluated with regards to the behavior of the non-radioactive components known to be extracted by the TRUEX solvent. In general, the behavior of the individual components closely paralleled that anticipated from batch testing. The results indicate that eight extraction stages are more than sufficient to reduce the actinide content in the SEW to levels well below the NRC Class A LLW criteria of 10 nCi/g. Iron was effectively scrubbed from the organic and 5% ended up in the high-activity waste (HAW) fraction. Zirconium scrubbing was not as effective and as much as 60% of the Zr in the feed could end up in the HAW fraction. The TUCS strip was effective at quantitatively stripping all metals except mercury from the TRUEX solvent. Carbonate washing effectively back extracted mercury from the stripped solvent, resulting in 99.4% of the mercury selectively partitioned from the SEW.

Law, J.D.; Herbst, R.S.

1995-02-01T23:59:59.000Z

155

Sulfur Partitioning During Vitrification of INEEL Sodium Bearing Waste: Status Report  

SciTech Connect

The sodium bearing tank waste (SBW) at Idaho National Engineering and Environmental Laboratory (INEEL) contains high concentrations of sulfur (roughly 5 mass% of SO3 on a nonvolatile oxide basis). The amount of sulfur that can be feed to the melter will ultimately determine the loading of SBW in glass produced by the baseline (low-temperature, joule-heated, liquid-fed, ceramic-lined) melter. The amount of sulfur which can be fed to the melter is determined by several major factors including: the tolerance of the melter for an immiscible salt layer accumulation, the solubility of sulfur in the glass melt, the fraction of sulfur removed to the off-gas, and the incorporation of sulfur into the glass up to it?s solubility limit. This report summarizes the current status of testing aimed at determining the impacts of key chemical and physical parameters on the partitioning of sulfur between the glass, a molten salt, and the off-gas.

Darab, John G.; Graham, Dennis D.; Macisaac, Brett D.; Russell, Renee L.; Smith, Harry D.; Vienna, John D.; Peeler, David K.

2001-07-31T23:59:59.000Z

156

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

157

Independent Activity Report, Waste Treatment and Immobilization Plant -  

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

Waste Treatment and Immobilization Waste Treatment and Immobilization Plant - March 2013 Independent Activity Report, Waste Treatment and Immobilization Plant - March 2013 March 2013 Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review [HIAR-WTP-2013-03-18] The Office of Health, Safety and Security (HSS) staff observed a limited portion of the restart of the Hazard Analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) System. The primary purpose of this HSS field activity, on March 18-21, 2013, was to observe and understand the revised approach implemented by Bechtel National, Inc. (BNI), the contractor responsible for the design and construction of WTP for the U.S. Department of Energy (DOE) Office of

158

Independent Oversight Activity Report, Hanford Waste Treatment and  

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

Hanford Waste Treatment and Hanford Waste Treatment and Immobilization Plant - June 2013 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - June 2013 June 2013 Hanford Waste Treatment and Immobilization Plant Low Activity Waste Melter Off-gas Process System Hazards Analysis Activity Observation [HIAR-WTP-2013-05-13] This Independent Activity Report documents an oversight activity conducted by the Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations from May 13 - June 28, 2013, at the Hanford Waste Treatment and Immobilization Plant (WTP). The activity consisted of HSS staff observing a limited portion of the start of the hazard analysis (HA) for WTP Low Activity Waste (LAW) Primary Off-gas System. The primary purpose of this HSS field activity was to observe and

159

Independent Oversight Activity Report, Hanford Waste Treatment and  

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

Waste Treatment and Waste Treatment and Immobilization Plant - July 2013 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - July 2013 July 2013 Operational Awareness of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity [HIAR-WTP-2013-07-31] This Independent Activity Report documents an oversight activity conducted by the Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations from July 31 - August 5, 2013, at the Hanford Waste Treatment and Immobilization Plant (WTP). The activity consisted of HSS staff observing a limited portion of the hazards analysis (HA) for WTP Low Activity Waste (LAW) Melter Process system. The primary purpose of this HSS field activity was to observe and

160

Mixed and low-level waste treatment facility project. Volume 3, Waste treatment technologies (Draft)  

SciTech Connect

The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

1992-04-01T23:59:59.000Z

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161

Waste treatment at the La Hague and Marcoule sites  

SciTech Connect

In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema`s plants.

1995-04-01T23:59:59.000Z

162

Mixed waste characterization, treatment, and disposal focus area. Technology summary  

Science Conference Proceedings (OSTI)

This paper presents details about the technology development programs of the Department of Energy. In this document, waste characterization, thermal treatment processes, non-thermal treatment processes, effluent monitors and controls, development of on-site innovative technologies, and DOE business opportunities are applied to environmental restoration. The focus areas for research are: contaminant plume containment and remediation; mixed waste characterization, treatment, and disposal; high-level waste tank remediation; landfill stabilization; and decontamination and decommissioning.

NONE

1995-06-01T23:59:59.000Z

163

Mixed and Low-Level Waste Treatment Facility project  

SciTech Connect

Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. The engineering studies, initiated in July 1991, identified 37 mixed waste streams, and 55 low-level waste streams. This report documents the waste stream information and potential treatment strategies, as well as the regulatory requirements for the Department of Energy-owned treatment facility option. The total report comprises three volumes and two appendices. This report consists of Volume 1, which explains the overall program mission, the guiding assumptions for the engineering studies, and summarizes the waste stream and regulatory information, and Volume 2, the Waste Stream Technical Summary which, encompasses the studies conducted to identify the INEL's waste streams and their potential treatment strategies.

1992-04-01T23:59:59.000Z

164

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

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

March 2013 March 2013 Independent Oversight 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. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security, conducted an independent review of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Plant (WTP). The review, which was performed November 26-30, 2012, was the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP construction site. Independent Oversight Review, Waste Treatment and Immobilization Plant - March 2013

165

DOE intends to extend the Advanced Mixed Waste Treatment Project...  

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

DOE intends to extend the Advanced Mixed Waste Treatment Project contract for four months as competition for long-term contract continues. Scene from inside the Advanced Mixed...

166

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

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

October 2012 October 2012 Independent Oversight Review, Waste Treatment and Immobilization Plant - October 2012 October 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U. S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security, conducted an independent review of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Plant (WTP). The review, which was performed August 6-10, 2012, was the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP construction site. Independent Oversight Review, Waste Treatment and Immobilization Plant -

167

Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford...  

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

(the percentage of actual operating time). 1 Comprehensive Review of the Hanford Waste Treatment Plant Flowsheet and Throughput Specifically, the following questions were...

168

REWAS 2008: Global Symposium on Recycling, Waste Treatment ...  

Science Conference Proceedings (OSTI)

Oct 20, 2008 ... REWAS 2008: Global Symposium on Recycling, Waste Treatment and ... on the Recovery of Materials and Energy for Resource Efficiency.

169

Advanced Mixed Waste Treatment Project Achieves Impressive Safety and  

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

Advanced Mixed Waste Treatment Project Achieves Impressive Safety Advanced Mixed Waste Treatment Project Achieves Impressive Safety and Production Marks Advanced Mixed Waste Treatment Project Achieves Impressive Safety and Production Marks June 26, 2013 - 12:00pm Addthis Only the 620 employees at EM’s Advanced Mixed Waste Treatment Project earned the right to this vanity plate after working more than 14 million hours without a lost-time injury and safely and compliantly shipping more than 50,000 cubic meters of transuranic and mixed low-level radioactive waste for disposal. Only the 620 employees at EM's Advanced Mixed Waste Treatment Project earned the right to this vanity plate after working more than 14 million hours without a lost-time injury and safely and compliantly shipping more than 50,000 cubic meters of transuranic and mixed low-level radioactive

170

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

171

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

172

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

173

Hanford Site waste treatment/storage/disposal integration  

SciTech Connect

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

MCDONALD, K.M.

1999-02-24T23:59:59.000Z

174

Production of metal waste forms from spent fuel treatment  

Science Conference Proceedings (OSTI)

Treatment of spent nuclear fuel at Argonne National Laboratory consists of a pyroprocessing scheme in which the development of suitable waste forms is being advanced. Of the two waste forms being proposed, metal and mineral, the production of the metal waste form utilizes induction melting to stabilize the waste product. Alloying of metallic nuclear materials by induction melting has long been an Argonne strength and thus, the transition to metallic waste processing seems compatible. A test program is being initiated to coalesce the production of the metal waste forms with current induction melting capabilities.

Westphal, B.R.; Keiser, D.D.; Rigg, R.H.; Laug, D.V.

1995-02-01T23:59:59.000Z

175

Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility |  

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

Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility August 18, 2011 - 12:00pm Addthis Idaho State Patrol Troopers Rick Stouse and Tony Anderson inspected the TRUPACTS, containers which contain TRU waste, and trailer containing the final shipment of Hanford offsite waste. The Idaho State Patrol officers have played an important role in AMWTP's success by inspecting every one of AMWTP's nearly 3,900 shipments. Idaho State Patrol Troopers Rick Stouse and Tony Anderson inspected the TRUPACTS, containers which contain TRU waste, and trailer containing the final shipment of Hanford offsite waste. The Idaho State Patrol officers have played an important role in AMWTP's success by inspecting every one of

176

Summary - Flowsheet for the Hanford Waste Treatment Plant  

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

Waste Treatment Plant Waste Treatment Plant ETR Report Date: March 2006 ETR-1 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Flowsheet for the Hanford Waste Treatment Plant (WTP) Why DOE-EM Did This Review The Hanford Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 53 million gallons of radioactive waste, separate it into high- and low-activity fractions, and produce canisters of high-level (HLW) glass (left) and containers of low-activity waste (LAW) glass (right). At the time of this review, the Plant was at approximately 70% design and 30% construction completion. The external review objective was to determine how well the WTP would meet its throughput capacities based on the current design,

177

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

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

Waste Treatment and Immobilization Waste Treatment and Immobilization Plant - August 2012 Independent Oversight Review, Waste Treatment and Immobilization Plant - August 2012 August 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U. S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security, conducted independent reviews of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Project (WTP). The reviews for this report were performed on site during February 6-10, 2012 and April 30 - May 4, 2012, and were the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP.

178

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

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

Oversight Review, Waste Treatment and Immobilization Oversight Review, Waste Treatment and Immobilization Plant - August 2011 Independent Oversight Review, Waste Treatment and Immobilization Plant - August 2011 August 2011 Hanford Waste Treatment and Immobilization Plant Construction Quality The Office of Safety and Emergency Management Evaluations (Independent Oversight) within the Office of Health, Safety and Security (HSS) conducted an independent review of selected aspects of construction quality at the Hanford Waste Treatment and Immobilization Project (WTP). The review, which was performed May 9-12, 2011, was the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP construction site. HSS determined that construction quality at WTP was adequate in the areas

179

Independent Oversight Review, Hanford Waste Treatment and Immobilization  

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

Waste Treatment and Waste Treatment and Immobilization Plant - December 2013 Independent Oversight Review, Hanford Waste Treatment and Immobilization Plant - December 2013 December 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report documents the results of an independent oversight review of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Plant (WTP). The review, which was performed September 9-13, 2013, was the latest in a series of ongoing quarterly assessments of construction quality performed by the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS). The scope of this quarterly assessment of construction quality review included observations

180

Independent Oversight Review, Advanced Mixed Waste Treatment Project -  

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

Review, Advanced Mixed Waste Treatment Review, Advanced Mixed Waste Treatment Project - April 2013 Independent Oversight Review, Advanced Mixed Waste Treatment Project - April 2013 April 2013 Review of Radiation Protection Program Implementation at the Advanced Mixed Waste Treatment Project of the Idaho Site This report documents an independent review of activity-level radiation protection program (RPP) implementation at the Advanced Mixed Waste Treatment Project (AMWTP) of the Idaho Site, as conducted by the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight) within the Office of Health, Safety and Security (HSS). The review was performed by the HSS Office of Safety and Emergency Management Evaluations. The purpose of this Independent Oversight targeted review

Note: This page contains sample records for the topic "bearing waste treatment" 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

Independent Oversight Assessment, Waste Treatment and Immobilization Plant  

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

Waste Treatment and Waste Treatment and Immobilization Plant - January 2012 Independent Oversight Assessment, Waste Treatment and Immobilization Plant - January 2012 January 2012 Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant 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 at the DOE Waste Treatment and Immobilization Plant (WTP) to evaluate the current status of the nuclear safety culture and the effectiveness of DOE and contractor management in addressing nuclear safety concerns at WTP. This assessment provides DOE management with a follow-up on the October 2010 HSS review of the WTP

182

Independent Oversight Review, Waste Treatment and Immobilization Plant  

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

Waste Treatment and Immobilization Waste Treatment and Immobilization Plant Project - October 2010 Independent Oversight Review, Waste Treatment and Immobilization Plant Project - October 2010 October 2010 Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project The U.S. Department of Energy (DOE) Office of Health, Safety and Security (HSS) conducted an independent review of the nuclear safety culture at the Waste Treatment and Immobilization Plant (WTP) project at the Hanford Site during August and September 2010. The HSS team performed the review in response to a request in a July 30, 2010, memorandum from the Assistant Secretary for the DOE Headquarters Office of Environmental Management (EM), which referred to nuclear safety concerns raised by a contractor employee

183

Independent Oversight Review, Hanford Site Waste Treatment and  

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

Waste Treatment and Waste Treatment and Immobilization Plant, August 2013 Independent Oversight Review, Hanford Site Waste Treatment and Immobilization Plant, August 2013 August 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality 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 review of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Plant (WTP). The review, which was performed June 10-14, 2013, was the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP construction site. The scope of this quarterly assessment of construction quality review

184

300 Area waste acid treatment system closure plan  

SciTech Connect

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOERL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion includes closure plan documentation submitted for individual, treatment, storage, and/or disposal units undergoing closure, such as the 300 Area Waste Acid Treatment System. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Whenever appropriate, 300 Area Waste Acid Treatment System documentation makes cross-reference to the General Information Portion, rather than duplicating text. This 300 Area Waste Acid Treatment System Closure Plan (Revision 2) includes a Hanford Facility Dangerous Waste Permit Application, Part A, Form 3. Information provided in this closure plan is current as of April 1999.

LUKE, S.N.

1999-05-17T23:59:59.000Z

185

Independent Oversight Review, Advanced Mixed Waste Treatment Project -  

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

Advanced Mixed Waste Treatment Advanced Mixed Waste Treatment Project - April 2013 Independent Oversight Review, Advanced Mixed Waste Treatment Project - April 2013 April 2013 Review of Radiation Protection Program Implementation at the Advanced Mixed Waste Treatment Project of the Idaho Site This report documents an independent review of activity-level radiation protection program (RPP) implementation at the Advanced Mixed Waste Treatment Project (AMWTP) of the Idaho Site, as conducted by the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight) within the Office of Health, Safety and Security (HSS). The review was performed by the HSS Office of Safety and Emergency Management Evaluations. The purpose of this Independent Oversight targeted review

186

Method for aqueous radioactive waste treatment  

DOE Patents (OSTI)

Plutonium, strontium, and cesium found in aqueous waste solutions resulting from nuclear fuel processing are removed by contacting the waste solutions with synthetic zeolite incorporating up to about 5 wt % titanium as sodium titanate in an ion exchange system. More than 99.9% of the plutonium, strontium, and cesium are removed from the waste solutions. 3 figures.

Bray, L.A.; Burger, L.L.

1994-03-29T23:59:59.000Z

187

Method for aqueous radioactive waste treatment  

DOE Patents (OSTI)

Plutonium, strontium, and cesium found in aqueous waste solutions resulting from nuclear fuel processing are removed by contacting the waste solutions with synthetic zeolite incorporating up to about 5 wt % titanium as sodium titanate in an ion exchange system. More than 99.9% of the plutonium, strontium, and cesium are removed from the waste solutions.

Bray, Lane A. (Richland, WA); Burger, Leland L. (Richland, WA)

1994-01-01T23:59:59.000Z

188

Feasibility of using biological degradation for the on-site treatment of mixed wastes  

E-Print Network (OSTI)

2002. EPA’s Radiation Protection Program: Mixed Waste.http://www.epa.gov/radiation/mixed-waste/.ON-SITE TREATMENT OF MIXED WASTES William T. Stringfellow (

Stringfellow, William T.; Komada, Tatsuyuki; Chang, Li-Yang

2004-01-01T23:59:59.000Z

189

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

190

Idaho waste treatment facility startup testing suspended to evaluate system  

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

waste treatment facility startup testing suspended to waste treatment facility startup testing suspended to evaluate system response Idaho waste treatment facility startup testing suspended to evaluate system response June 20, 2012 - 12:00pm Addthis Media Contacts Brad Bugger 208-526-0833 Danielle Miller 208-526-5709 IDAHO FALLS, ID- On Saturday, June 16, startup testing was suspended at the Integrated Waste Treatment Unit (IWTU) located at the U.S. Department of Energy's Idaho Site. Testing and plant heat-up was suspended to allow detailed evaluation of a system pressure event observed during testing on Saturday. Facility startup testing has been ongoing for the past month, evaluating system and component operation and response during operating conditions. No radioactive or hazardous waste has been introduced into the facility,

191

Waste treatment facility passes federal inspection, completes final  

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

23, 2012 23, 2012 Media Contact: Danielle Miller, 208-526-5709 Erik Simpson, 208-390-9464 Waste treatment facility passes federal inspection, completes final milestone, begins startup The Idaho site today initiated the controlled, phased startup of a new waste treatment facility scheduled to begin treating 900,000 gallons of radioactive liquid waste stored in underground tanks at a former Cold War spent nuclear fuel reprocessing facility next month. An exterior view of the Integrated Waste Treatment Unit A U.S. Department of Energy (DOE) operational readiness review team (made up of Subject Matter Experts across the country) in early April identified a dozen issues for the cleanup contractor CH2M-WG Idaho, LLC (CWI) to resolve before the 53,000-square-foot Integrated Waste Treatment Unit

192

Waste Treatment Facility Passes Federal Inspection, Completes Final  

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

Waste Treatment Facility Passes Federal Inspection, Completes Final Waste Treatment Facility Passes Federal Inspection, Completes Final Milestone, Begins Startup Waste Treatment Facility Passes Federal Inspection, Completes Final Milestone, Begins Startup April 23, 2012 - 12:00pm Addthis Media Contact Erik Simpson, 208-390-9464 Danielle Miller, 208-526-5709 The Idaho site today initiated the controlled, phased startup of a new waste treatment facility scheduled to begin treating 900,000 gallons of radioactive liquid waste stored in underground tanks at a former Cold War spent nuclear fuel reprocessing facility next month. A U.S. Department of Energy (DOE) operational readiness review team (made up of Subject Matter Experts across the country) in early April identified a dozen issues for the cleanup contractor CH2M-WG Idaho, LLC (CWI) to

193

Independent Activity Report, Office of River Protection Waste Treatment  

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

Office of River Protection Waste Office of River Protection Waste Treatment Plant and Tank Farms - February 2013 Independent Activity Report, Office of River Protection Waste Treatment Plant and Tank Farms - February 2013 February 2013 Site Familiarization and Introduction of New Office of Safety and Emergency Management Evaluations Site Lead for the Office of River Protection Waste Treatment Plant and Tank Farms [HIAR-HANFORD-2013-02-25] The Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations (HS-45) assigned a new Site Lead to provide continuous oversight of activities at the Office of River Protection (ORP) Waste Treatment Plant (WTP) and tank farms. To gain familiarity with the site programs and personnel, the new Site Lead made two trips to the site, which included tours of the WTP construction site

194

Nuclear waste treatment program: Annual report for FY 1987  

SciTech Connect

Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs.

Brouns, R.A.; Powell, J.A. (comps.)

1988-09-01T23:59:59.000Z

195

Treatment of plutonium-bearing solutions: A brief survey of the DOE complex  

SciTech Connect

With the abrupt shutdown of some DOE facilities, a significant volume of in-process material was left in place and still requires treatment for interim storage. Because the systems containing these process streams have deteriorated since shutdown, a portable system for treating the solutions may be useful. A brief survey was made of the DOE complex on the need for a portable treatment system to treat plutonium-bearing solutions. A survey was completed to determine (1) the compositions and volumes of solutions and heels present, (2) the methods that have been used to treat these solutions and heels in the past, and (3) the potential problems that exist in removing and treating these solutions. Based on the surveys and on the Defense Nuclear Facilities Safety Board Recommendation 94-1, design criteria for a portable treatment system were generated.

Conner, C.; Chamberlain, D.B.; Chen, L.; Vandegrift, G.F.

1995-03-01T23:59:59.000Z

196

Microsoft PowerPoint - EM SSAB Chairs Webinar - Marcinowski Waste...  

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

from the Moab project to Crescent Junction for disposal * Idaho: Start treatment of sodium bearing waste, continue CH and RH TRU projects * Los Alamos: Work toward completion...

197

Independent Oversight Activity Report, Hanford Waste Treatment and  

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

October 2013 October 2013 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - October 2013 October 2013 Observation of Waste Treatment and Immobilization Plant Low Activity Waste Melter and Melter Off-gas Process System Hazards Analysis Activities [HIAR-WTP-2013-10-21] This Independent Activity Report documents an oversight activity conducted by the Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations from October 21-31, 2013, at the Hanford Waste Treatment and Immobilization Plant (WTP). The activity consisted of HSS staff reviewing the Insight software hazard evaluation (HE) tables for hazard analysis (HA) generated to date for the WTP Low Activity Waste (LAW) Melter and Off-gas systems, observed a limited portion of the HA for the

198

FY-97 operations of the pilot-scale glass melter to vitrify simulated ICPP high activity sodium-bearing waste  

SciTech Connect

A 3.5 liter refractory-lined joule-heated glass melter was built to test the applicability of electric melting to vitrify simulated high activity waste (HAW). The HAW streams result from dissolution and separation of Idaho Chemical Processing Plant (ICPP) calcines and/or radioactive liquid waste. Pilot scale melter operations will establish selection criteria needed to evaluate the application of joule heating to immobilize ICPP high activity waste streams. The melter was fabricated with K-3 refractory walls and Inconel 690 electrodes. It is designed to be continuously operated at 1,150 C with a maximum glass output rate of 10 lbs/hr. The first set of tests were completed using surrogate HAW-sodium bearing waste (SBW). The melter operated for 57 hours and was shut down due to excessive melt temperatures resulting in low glass viscosity (< 30 Poise). Due to the high melt temperature and low viscosity the molten glass breached the melt chamber. The melter has been dismantled and examined to identify required process improvement areas and successes of the first melter run. The melter has been redesigned and is currently being fabricated for the second run, which is scheduled to begin in December 1997.

Musick, C.A.

1997-11-01T23:59:59.000Z

199

Demonstration of a SREX flowsheet for the partitioning of strontium and lead from actual ICPP sodium-bearing waste  

SciTech Connect

Laboratory experimentation has indicated that the SREX process is effective for partitioning {sup 90}Sr and Pb from acidic radioactive waste solutions located at the Idaho Chemical Processing Plant. Previous countercurrent flowsheet testing of the SREX process with simulated waste resulted in 99.98% removal of Sr and 99.9% removal of Pb. Based on the results of these studies, a demonstration of the SREX flowsheet was performed. The demonstration consisted of (1) countercurrent flowsheet testing of the SREX process using simulated sodium-bearing waste spiked with {sup 85}Sr and (2) countercurrent flowsheet testing of the SREX process using actual waste from tank WM-183. All testing was performed using 24 stages of 2-cm diameter centrifugal contactors which are installed in the Remote Analytical Laboratory hot cell. The flowsheet tested consisted of an extraction section (0. 15 M 4`,4`(5)-di-(tert-butyldicyclohexo)-18-crown-6 and 1.5 M TBP in Isopar-L{reg_sign}), a 2.0 MHNO{sub 3} scrub section to remove extracted K from the SREX solvent, a 0.05 M HNO{sub 3} strip section for the removal of Sr from the SREX solvent, a 0.1 M ammonium citrate strip section for the removal of Pb from the SREX solvent, and a 3.0 M HNO{sub 3} equilibration section. The behavior of {sup 90}Sr, Pb, Na, K, Hg, H{sup +}, the actinides, and numerous other non-radioactive elements was evaluated. The described flowsheet successfully extracted and selectively stripped Sr and Ph from the SBW simulant and the actual tank waste. For the testing with actual tank waste (WM - 183), removal efficiencies of 99.995 % and >94% were obtained for {sup 90}Sr and Pb, respectively.

Law, J.D.; Wood, D.J.; Olson, L.G.; Todd, T.A.

1997-08-01T23:59:59.000Z

200

Mixed Waste Storage and Treatment: Regulatory Compliance Manual  

Science Conference Proceedings (OSTI)

The management and storage of mixed wastes represents one of the most challenging regulatory issues currently facing NRC licensees. This report provides instructions and guidance regarding the on-site storage and treatment of mixed waste in compliance with Resource Conservation and Recovery Act (RCRA) requirements.

1994-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "bearing waste treatment" 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

300 Area waste acid treatment system closure plan. Revision 1  

SciTech Connect

This section provides a description of the Hanford Site, identifies the proposed method of 300 Area Waste Acid Treatment System (WATS) closure, and briefly summarizes the contents of each chapter of this plan.

NONE

1996-03-01T23:59:59.000Z

202

Office of River Protection Waste Treatment and Immobilizatin...  

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

and Review of the Office of River Protection Waste Treatment and Immobilization Project Construction Site, November 16-18, 2010 The U.S. Department of Energy Office of...

203

Summary - System Planning for Low-Activity Waste Treatment at...  

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

(DOE-EM) External Technical Review of System Planning for Low-Activity Waste Treatment at Hanford Why DOE-EM Did This Review Construction of the facilities of the Hanford site's...

204

DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at...  

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

doe logo Media Contact: Brad Bugger (208) 526-0833 For Immediate Release: Friday, May 27, 2011 DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed...

205

Hanford Waste Treatment Plant Support Task Order Modified | Department of  

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

Waste Treatment Plant Support Task Order Modified Waste Treatment Plant Support Task Order Modified Hanford Waste Treatment Plant Support Task Order Modified March 11, 2013 - 12:00pm Addthis Media Contact Lynette Chafin, 513-246-0461 Lynette.Chafin@emcbc.doe.gov Cincinnati - The Department of Energy (DOE) today awarded a modification to a task order to Aspen Resources Limited, Inc. of Boulder, Colorado for support of the Waste Treatment and Immobilization Plant (WTP) at the Hanford Site. The modification increased the value of the task order to $1.6 million from $833,499. The task order modification has a one-year performance period and two one-year option periods. The Task Order was awarded under an Indefinite Delivery/Indefinite Quantity (ID/IQ) master Contract. Aspen Resources Limited, Inc. is a small-disadvantaged business under the Small Business Administration's

206

Biological treatment of concentrated hazardous, toxic, and radionuclide mixed wastes without dilution  

E-Print Network (OSTI)

Report. DOE/MWIP-26. Mixed Waste Integrated Program, U. S.Trial burn activities for a mixed waste incinerator. WasteBiological Treatment of Mixed Wastes Containing Acetonitrile

Stringfellow, William T.; Komada, Tatsuyuki; Chang, Li-Yang

2004-01-01T23:59:59.000Z

207

Waste Treatment Plant and Tank Farm Program  

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

This photo shows the Pretreatment Facility control room building pad at the Office of River Protection at the Hanford site. The Low-Activity Waste Facility is in the background.

208

Treatment of Mixed Incinerable Waste, IG-0588  

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

We found the Department of Energy (Department) was not treating its mixed incinerable solid waste expeditiously or cost-effectively. Specifically, the Department: • Did not fully utilize the Toxic...

209

Idaho Waste Treatment Facility Improves Worker Safety and Efficiency, Saves  

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

Waste Treatment Facility Improves Worker Safety and Waste Treatment Facility Improves Worker Safety and Efficiency, Saves Taxpayer Dollars Idaho Waste Treatment Facility Improves Worker Safety and Efficiency, Saves Taxpayer Dollars August 27, 2013 - 12:00pm Addthis The box retrieval forklift carriage is used to lift a degraded box as retrieval personnel monitor progress. The box retrieval forklift carriage is used to lift a degraded box as retrieval personnel monitor progress. The new soft-sided overpack is placed for shipment for treatment and repackaging. The new soft-sided overpack is placed for shipment for treatment and repackaging. The box retrieval forklift carriage is used to lift a degraded box as retrieval personnel monitor progress. The new soft-sided overpack is placed for shipment for treatment and repackaging.

210

Performance estimates for waste treatment pyroprocesses in ATW  

SciTech Connect

The author has identified several pyrometallurgical processes for the conceptual ATW waste treatment cycle. These processes include reductive extraction, electrowinning and electrorefining, which constitute some versatile treatment cycles for liquid-metal based and molten-salt based waste forms when they are properly integrated. This paper examines the implementation of these processes and the achievable separations for some typical species. The author also presents a simple analysis of the processing rates limited by mass diffusion through a thin hydrodynamic boundary layer. It is shown that these processes can be realized with compact and efficient devices to meet the ATW demand for the periodic feeding and cleaning of the waste.

Li, N.

1997-05-01T23:59:59.000Z

211

Magnetic Adsorption Method for the Treatment of Metal Contaminated Aqueous Waste  

SciTech Connect

There have been many recent developments in separation methods used for treating radioactive and non-radioactive metal bearing liquid wastes. These methods have included adsorption, ion exchange, solvent extraction and other chemical and physical techniques. To date very few, if any, of these processes can provide a low cost and environmentally benign solution. Recent research into the use of magnetite for wastewater treatment indicates the potential for magnetite both cost and environment drivers. A brief review of recent work in using magnetite as a sorbent is presented as well as recent work performed in our laboratory using supported magnetite in the presence of an external magnetic field. The application to groundwater and other aqueous waste streams is discussed. Recent research has focused on supporting magnetite in an economical (as compared to the magnetic polymine-epichlorohydrine resin) and inert (non-reactive, chemically or otherwise) environment that promotes both adsorption and satisfactory flow characteristics.

G. B. Cotten (Parsons); J. D. Navratil (INEEL); H. B. Eldredge (U of Idaho)

1999-03-01T23:59:59.000Z

212

Waste Treatment Facility Saves Taxpayers Nearly $20 Million | Department of  

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

Waste Treatment Facility Saves Taxpayers Nearly $20 Million Waste Treatment Facility Saves Taxpayers Nearly $20 Million Waste Treatment Facility Saves Taxpayers Nearly $20 Million December 11, 2012 - 1:40pm Addthis A new enclosure for processing radioactive casks has put Oak Ridge on a path to finishing cleanup work two years ahead of schedule, saving nearly $20 million. | Photo courtesy of the Office of Environmental Management. A new enclosure for processing radioactive casks has put Oak Ridge on a path to finishing cleanup work two years ahead of schedule, saving nearly $20 million. | Photo courtesy of the Office of Environmental Management. Erin Szulman Erin Szulman Special Assistant, Office of Environmental Management What Are The Two Types of Waste? One is contact-handled, which has lower radioactivity and can be

213

Waste Treatment Facility Saves Taxpayers Nearly $20 Million | Department of  

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

Waste Treatment Facility Saves Taxpayers Nearly $20 Million Waste Treatment Facility Saves Taxpayers Nearly $20 Million Waste Treatment Facility Saves Taxpayers Nearly $20 Million December 11, 2012 - 1:40pm Addthis A new enclosure for processing radioactive casks has put Oak Ridge on a path to finishing cleanup work two years ahead of schedule, saving nearly $20 million. | Photo courtesy of the Office of Environmental Management. A new enclosure for processing radioactive casks has put Oak Ridge on a path to finishing cleanup work two years ahead of schedule, saving nearly $20 million. | Photo courtesy of the Office of Environmental Management. Erin Szulman Erin Szulman Special Assistant, Office of Environmental Management What Are The Two Types of Waste? One is contact-handled, which has lower radioactivity and can be

214

Radioactive Liquid Waste Treatment Facility: Environmental Information Document  

Science Conference Proceedings (OSTI)

At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R&D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R&D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action.

Haagenstad, H.T.; Gonzales, G.; Suazo, I.L. [Los Alamos National Lab., NM (United States)

1993-11-01T23:59:59.000Z

215

Mixed and Low-Level Waste Treatment Facility Project  

SciTech Connect

Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report documents those studies so the project can continue with an evaluation of programmatic options, system tradeoff studies, and the conceptual design phase of the project. This report, appendix B, comprises the engineering design files for this project study. The engineering design files document each waste steam, its characteristics, and identified treatment strategies.

1992-04-01T23:59:59.000Z

216

Reliability analysis of common hazardous waste treatment processes  

Science Conference Proceedings (OSTI)

Five hazardous waste treatment processes are analyzed probabilistically using Monte Carlo simulation to elucidate the relationships between process safety factors and reliability levels. The treatment processes evaluated are packed tower aeration, reverse osmosis, activated sludge, upflow anaerobic sludge blanket, and activated carbon adsorption.

Waters, R.D. [Vanderbilt Univ., Nashville, TN (United States)

1993-05-01T23:59:59.000Z

217

SRS Tank 48H Waste Treatment Project Technology Readiness Assessment  

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

Savannah River Site Tank 48H Savannah River Site Tank 48H Waste Treatment Project Technology Readiness Assessment Harry D. Harmon Joan B. Berkowitz John C. DeVine, Jr. Herbert G. Sutter Joan K. Young SPD-07-195 July 31, 2007 Prepared by the U.S. Department of Energy Aiken, South Carolina SRS Tank 48H Waste Treatment Project SPD-07-195 Technology Readiness Assessment July 31, 2007 Signature Page 7/31/07 ___________________________ _________________________ John C. DeVine, Jr., Team Member Date SRS Tank 48H Waste Treatment Project SPD-07-195 Technology Readiness Assessment July 31, 2007 Executive Summary The purpose of this assessment was to determine the technology maturity level of the candidate Tank 48H treatment technologies that are being considered for implementation at DOE's

218

Report: EM Tank Waste Subcommittee Full Report for Waste Treatment Plant  

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

U.S. DEPARTMENT OF ENERGY U.S. DEPARTMENT OF ENERGY 1000 INDEPENDENCE AVENUE SW WASHINGTON DC 20585 September 30, 2010 Dr. Inés R. Triay Assistant Secretary for Environmental Management 1000 Independence Avenue SW Washington, DC 20585 Dear Dr. Triay: As discussed during our September 15th public meeting, enclosed please find the Environmental Management Advisory Board EM Tank Waste Subcommittee Report for Waste Treatment Plant; Report Number EMAB EM-TWS WTP-001, September 30, 2010, in accordance with the Work Plan directive dated May 10, 2010. This report covers the work plan observations and recommendations concerning the Waste Treatment and Immobilization Plant at Hanford (WTP). The charge is summarized below. Charge 1: Verification of closure of Waste Treatment and Immobilization

219

Treatment and Recycling of Solid Slag/Wastes - Programmaster.org  

Science Conference Proceedings (OSTI)

Mar 15, 2012... industrial solid wastes, such as titanium-bearing blast furnace slag, high-silicon iron tailing and boron-enriched slag as well as oil shale.

220

Mixed and Low-Level Waste Treatment Facility project  

SciTech Connect

Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report, Appendix A, Environmental Regulatory Planning Documentation, identifies the regulatory requirements that would be imposed on the operation or construction of a facility designed to process the INEL's waste streams. These requirements are contained in five reports that discuss the following topics: (1) an environmental compliance plan and schedule, (2) National Environmental Policy Act requirements, (3) preliminary siting requirements, (4) regulatory justification for the project, and (5) health and safety criteria.

1992-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "bearing waste treatment" 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

Process development for remote-handled mixed-waste treatment  

SciTech Connect

The Oak Ridge National Laboratory (ORNL) is developing a treatment process for remote-handled (RH) liquid transuranic mixed waste governed by the concept of minimizing the volume of waste requiring disposal. This task is to be accomplished by decontaminating the bulk components so the process effluent can be disposed with less risk and expense. Practical processes have been demonstrated on the laboratory scale for removing cesium 137 and strontium 90 isotopes from the waste, generating a concentrated waste volume, and rendering the bulk of the waste nearly radiation free for downstream processing. The process is projected to give decontamination factors of 10{sup 4} for cesium and 10{sup 3} for strontium. Because of the extent of decontamination, downstream processing will be contact handled. The transuranic, radioactive fraction of the mixed waste stream will be solidified using a thin-film evaporator and/or microwave solidification system. Resultant solidified waste will be disposed at the Waste Isolation Pilot Plant (WIPP). 8 refs., 2 figs., 3 tabs.

Berry, J.B.; Campbell, D.O.; Lee, D.D.; White, T.L.

1990-01-01T23:59:59.000Z

222

Results of HWVP transuranic process waste treatment laboratory and pilot-scale filtration tests using specially ground zeolite  

SciTech Connect

Process waste streams from the Hanford Waste Vitrification Plant (HWVP) may require treatment for cesium, strontium, and transuranic (TRU) element removal in order to meet criteria for incorporation in grout. The approach planned for cesium and strontium removal is ion exchange using a zeolite exchanger followed by filtration. Filtration using a pneumatic hydropulse filter is planned to remove TRU elements which are associated with process solids and to also remove zeolite bearing the cesium and strontium. The solids removed during filtration are recycled to the melter feed system to be incorporated into the HWVP glass product. Fluor Daniel, Inc., the architect-engineering firm for HWVP, recommended a Pneumatic Hydropulse (PHP) filter manufactured by Mott Metallurgical Corporation for use in the HWVP. The primary waste streams considered for application of zeolite contact and filtration are melter off-gas condensate from the submerged bed scrubber (SBS), and equipment decontamination solutions from the Decontamination Waste Treatment Tank (DWTT). Other waste streams could be treated depending on TRU element and radionuclide content. Laboratory and pilot-scale filtration tests were conducted to provide a preliminary assessment of the adequacy of the recommended filter for application to HWVP waste treatment.

Eakin, D.E.

1996-03-01T23:59:59.000Z

223

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

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

January 2013 January 2013 Independent Oversight Review, Waste Treatment and Immobilization Plant - January 2013 January 2013 Review of the Hanford Waste Treatment and Immobilization Plant Black-Cell and Hard-To-Reach Pipe Spools Procurement Process and the Office of River Protection Audit of That Process The Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted a concurrent independent review with the U.S. Department of Energy (DOE) Office of River Protection (ORP) of selected aspects of the Bechtel National, Inc. (BNI) Hanford Site Waste Treatment and Immobilization Plant (WTP) procurement processes for WTP black-cell (BC) and hard-to-reach (HtR) pipe spools. The Independent Oversight review was performed by the HSS Office of Safety and

224

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

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

August 2012 August 2012 Independent Oversight Review, Waste Treatment and Immobilization Plant - August 2012 August 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U. S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security, conducted independent reviews of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Project (WTP). The reviews for this report were performed on site during February 6-10, 2012 and April 30 - May 4, 2012, and were the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP. Independent Oversight determined that construction quality at WTP is

225

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

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

2 2 Independent Oversight Review, Waste Treatment and Immobilization Plant - March 2012 March 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality The U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security, conducted an independent review of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Plant (WTP). The review, which was performed November 14-17, 2011, was the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP construction site. Independent Oversight determined that construction quality at WTP was adequate in the areas reviewed. BNI Engineering has developed appropriate

226

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

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

January 2013 January 2013 Independent Oversight Review, Waste Treatment and Immobilization Plant - January 2013 January 2013 Review of the Hanford Waste Treatment and Immobilization Plant Black-Cell and Hard-To-Reach Pipe Spools Procurement Process and the Office of River Protection Audit of That Process The Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted a concurrent independent review with the U.S. Department of Energy (DOE) Office of River Protection (ORP) of selected aspects of the Bechtel National, Inc. (BNI) Hanford Site Waste Treatment and Immobilization Plant (WTP) procurement processes for WTP black-cell (BC) and hard-to-reach (HtR) pipe spools. The Independent Oversight review was performed by the HSS Office of Safety and

227

Independent Oversight Activity Report, Hanford Waste Treatment and  

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

November 2013 November 2013 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - November 2013 December 2013 Catholic University of America Vitreous State Laboratory Tour and Discussion of Experiments Conducted in Support of Hanford Site Waste Treatment and Immobilization Plant Select Systems Design [HIAR-VSL-2013-11-18] This Independent Activity Report documents an oversight activity conducted by the Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations on November 18, 2013, at the Catholic University of America Vitreous State Laboratory (VSL). Bechtel National, Inc. (BNI) is the contractor responsible for the design and construction of the Hanford Site Waste Treatment and Immobilization Plant (WTP) for the

228

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

SciTech Connect

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

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

2003-09-01T23:59:59.000Z

229

Radiological, physical, and chemical characterization of additional alpha contaminated and mixed low-level waste for treatment at the advanced mixed waste treatment project  

SciTech Connect

This document provides physical, chemical, and radiological descriptive information for a portion of mixed waste that is potentially available for private sector treatment. The format and contents are designed to provide treatment vendors with preliminary information on the characteristics and properties for additional candidate portions of the Idaho National Engineering Laboratory (INEL) and offsite mixed wastes not covered in the two previous characterization reports for the INEL-stored low-level alpha-contaminated and transuranic wastes. This report defines the waste, provides background information, briefly reviews the requirements of the Federal Facility Compliance Act (P.L. 102-386), and relates the Site Treatment Plans developed under the Federal Facility Compliance Act to the waste streams described herein. Each waste is summarized in a Waste Profile Sheet with text, charts, and tables of waste descriptive information for a particular waste stream. A discussion of the availability and uncertainty of data for these waste streams precedes the characterization descriptions.

Hutchinson, D.P.

1995-07-01T23:59:59.000Z

230

Treatment of Mixed Wastes via Fixed Bed Gasification  

SciTech Connect

This report outlines the details of research performed under USDOE Cooperative Agreement DE-FC21-96MC33258 to evaluate the ChemChar hazardous waste system for the destruction of mixed wastes, defined as those that contain both RCRA-regulated haz- ardous constituents and radionuclides. The ChemChar gasification system uses a granular carbonaceous char matrix to immobilize wastes and feed them into the gasifier. In the gasifier wastes are subjected to high temperature reducing conditions, which destroy the organic constituents and immobilize radionuclides on the regenerated char. Only about 10 percent of the char is consumed on each pass through the gasifier, and the regenerated char can be used to treat additional wastes. When tested on a 4-inch diameter scale with a continuous feed unit as part of this research, the ChemChar gasification system was found to be effective in destroying RCRA surrogate organic wastes (chlorobenzene, dichloroben- zene, and napht.halene) while retaining on the char RCRA heavy metals (chromium, nickel, lead, and cadmium) as well as a fission product surrogate (cesium) and a plutonium surrogate (cerium). No generation of harmful byproducts was observed. This report describes the design and testing of the ChemChar gasification system and gives the operating procedures to be followed in using the system safely and effectively for mixed waste treatment.

None

1998-10-28T23:59:59.000Z

231

Environment Canada research on land treatment of petroleum wastes  

Science Conference Proceedings (OSTI)

The purpose of the studies presented in this book is to identify wastes which can be applied to land in an environmentally acceptable manner and to provide information on which to base guidelines for the proper application of such wastes to land. The information which has been collected to date has focused on the persistence and fate of oil and toxic constituents of petroleum wastes when applied to soil, potential environmental impacts and risk to human health associated with application to land, and site managements techniques which enhance treatment of organic constituents of wastes while protecting environmental quality. The potential for contamination of groundwater, the accumulation of hazardous substances in soil and effects on plant growth have undergone the most intensive investigation to date. Impingement on air quality has received limited study.

Bulman, T.L.; Scroggins, R.P. (Wastewater Technolgy Centre, Burlington, Ontario (CA))

1988-01-01T23:59:59.000Z

232

Low-level liquid waste treatment system start-up  

Science Conference Proceedings (OSTI)

Following removal of Cs-137 by ion exchange in the Supernatant Treatment System immediately upstream, the radioactive liquid waste is volume-reduced by evaporation. Trace amounts of Cs-137 in the resulting distillate are removed by ion exchange, then the distillate is discharged to the existing plant water treatment system. The concentrated product, 37 to 41 percent solids (by weight), is encapsulated in cement, producing a stable low-level waste form. This report provides a summary of work performed to test the Liquid Waste Treatment System following construction turnover and prior to radioactive operation. All mechanical and electrical components, piping, valves, pumps, tanks, controls, and instrumentation required to operate the system were tested; first with water, then with simulated waste. Subsystems (individual tanks, pumps, and control loops) were tested individually, then as a complete system. Finally, the system began a controlled start-up phase, which included the first four months of radioactive operation. Components were tested for operability then for performance data to verify the system`s ability to produce an acceptable waste form at design feed rates.

Baker, M.N.; Gessner, R.F.

1989-07-01T23:59:59.000Z

233

Mixed and low-level waste treatment facility project  

SciTech Connect

The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

Not Available

1992-04-01T23:59:59.000Z

234

Physical/chemical treatment of mixed waste soils  

Science Conference Proceedings (OSTI)

This report discusses the results and findings of the demonstration testing of a physical/chemical treatment technology for mixed wastes. The principal objective of the tests was to demonstrate the capability of the low temperature thermal separation (LTTS) technology for rendering PCB-contaminated mixed waste soils as nonhazardous and acceptable for low level radioactive waste disposal. The demonstration testing of this technology was a jointly-conducted project by the US Department of Energy (DOE), the Martin Marietta Energy Systems (Energy Systems) Waste Management Technology Center at the Oak Ridge National Laboratory, and IT Corporation. This pilot-scale demonstration program testing of IT's thermal separator technology in Oak Ridge was conducted as part of the DOE Model Program. This program has private industry, regulators, and universities helping to solve DOE waste management problems. Information gained from the DOE Model is shared with the participating organizations, other federal agencies, and regulatory agencies. The following represent the most significant findings from these demonstration tests: Thermal separation effectively separated PCB contamination from a mixed waste to enable the treated soil to be managed as low level radioactive waste. At the same operating conditions, mercury contamination of 0.8 ppM was reduced to less than 0.1 ppM. The majority of uranium and technetium in the waste feeds oil remained in the treated soil. Radionuclide concentration in cyclone solids is due to carry-over of entrained particles in the exit gas and not due to volatilization/condensation. Thermal separation also effectively treated all identified semi-volatile contaminants in the waste soil to below detection limits with the exception of di-n-butylphthalate in one of the two runs. 4 refs., 1 fig., 6 tabs.

Morris, M.I. (Oak Ridge National Lab., TN (USA)); Alperin, E.S.; Fox, R.D. (IT Corp., Knoxville, TN (USA))

1991-01-01T23:59:59.000Z

235

Pilot studies to achieve waste minimization and enhance radioactive liquid waste treatment at the Los Alamos National Laboratory Radioactive Liquid Waste Treatment Facility  

SciTech Connect

The Radioactive and Industrial Wastewater Science Group manages and operates the Radioactive Liquid Waste Treatment Facility (RLWTF) at the Los Alamos National Laboratory (LANL). The RLWTF treats low-level radioactive liquid waste generated by research and analytical facilities at approximately 35 technical areas throughout the 43-square-mile site. The RLWTF treats an average of 5.8 million gallons (21.8-million liters) of liquid waste annually. Clarifloculation and filtration is the primary treatment technology used by the RLWTF. This technology has been used since the RLWTF became operable in 1963. Last year the RLWTF achieved an average of 99.7% removal of gross alpha activity in the waste stream. The treatment process requires the addition of chemicals for the flocculation and subsequent precipitation of radionuclides. The resultant sludge generated during this process is solidified in drums and stored or disposed of at LANL.

Freer, J.; Freer, E.; Bond, A. [and others

1996-07-01T23:59:59.000Z

236

PMB-Waste: An analysis of fluidized bed thermal treatment  

SciTech Connect

A fluidized bed treatment process was evaluated for solid waste from plastic media blasting of aircraft protective coating. The treatment objective is to decompose and oxidize all organic components, and concentrate all the hazardous metals in the ash. The reduced volume and mass are expected to reduce disposal cost. A pilot test treatment was done in an existing fluidized bed equipped with emissions monitors, and emissions within regulatory requirements were demonstrated. A economic analysis of the process is inconclusive due to lack of reliable cost data of disposal without thermal treatment.

Gat, U.; Kass, M.D.; Lloyd, D.B.

1995-07-01T23:59:59.000Z

237

Mixed and Low-Level Treatment Facility Project. Appendix B, Waste stream engineering files, Part 1, Mixed waste streams  

SciTech Connect

This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

1992-04-01T23:59:59.000Z

238

Hanford Waste Treatment and Immobilization Plant Construction Quality, August 2011  

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

Independent Review Report Independent Review Report Waste Treatment and Immobilization Plant Construction Quality May 2011 August 2011 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope .................................................................................................................................................... 1 4.0 Results .................................................................................................................................................. 2

239

Principles of biotechnological treatment of industrial wastes  

Science Conference Proceedings (OSTI)

This review includes current information on biodegradation processes of pollutants, digestor biocenosis and bioadditives, sludge production, measurement of pollution, and advances regarding biotechnological treatment of a series of specific industrial effluents. It was foreseen in 1980 that biotechnology would foster the creation of new industries with low energy requirements. This is because the growth of microorganisms provides a renewable source of energy.

Roig, M.G.; Martin Rodriguez, M.J.M.; Cachaza, J.M. (Univ. de Salamanca, Salamanca (Spain). Dept. de Quimica Fisica); Mendoza Sanchez, L. (C/Sol Oriente, Salamanca (Spain). Estudios y Proyectos); Kennedy, J.F. (Univ. of Birmingham, Birmingham (United Kingdom). Research Lab. for the Chemistry of Bioactive Carbohydrates and Proteins)

1993-07-01T23:59:59.000Z

240

CMP flowsheet development for the separation of actinides from ICPP sodium-bearing waste using centrifugal contactors  

Science Conference Proceedings (OSTI)

Previous results of lab-scale batch contacts with sodium-bearing waste (SBW) simulant suggested a potential flowsheet for partitioning actinides using solvent extraction with dihexyl-N,N-diethylcarbamoylmethyl phosphonate (DHDECMP or simply CMP) as the extractant. The suggested baseline flowsheet includes: an extraction section to remove actinides from liquid SBW into the CMP solvent (0.75 M CMP, 1.0 M TBP in Isopar-L{reg_sign}); a thermally unstable complexant (TUCS) strip section to back-extract actinides; a sodium carbonate wash section for solvent cleanup; and a dilute HNO{sub 3} rinse section to re-acidify the solvent. The purpose of these studies was to test and develop a baseline CMP flowsheet for Idaho Chemical Processing Plant (ICPP) SBW under continuous, countercurrent conditions using centrifugal contactors. This flowsheet was tested in two experiments using the Centrifugal Contactor Mockup which consists of sixteen stages of 5.5 cm diameter centrifugal contactors (procured from Oak Ridge National Laboratory). All testing was performed using non-radioactive SBW simulant. Potential flowsheets were evaluated with regard to the behavior of the non-radioactive components potentially extracted by the CMP solvent. Specifically, the behavior of the matrix components, including Fe, Hg, and Zr, was studied. In addition, Nd was added to the SBW simulant as a surrogate for {sup 241}Am. In general, the behavior of the individual components closely paralleled that anticipated from batch testing. Based on the assumption that the behavior of Am will be very similar to the behavior of the Nd surrogate, eight extraction stages are more than sufficient to reduce the actinide content in the SBW to levels well below the NRC Class A LLW criteria of 10 nCi/g. Very little Fe or Zr were extracted from the SBW simulant, resulting in only 1% of the Fe and 4% of the Zr exiting in the high-activity waste (HAW) fraction.

Law, J.D.; Herbst, R.S.; Rodriguez, A.M.

1995-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "bearing waste treatment" 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

Progress in geothermal waste treatment biotechnology  

SciTech Connect

Studies directed at the development of an environmentally acceptable technology for the treatment and disposal of geothermal sludges have shown that a biotechnology based on microbial biochemical processes is technically and economically feasible. Process designs for the emerging biotechnology have to take several variables into consideration. In the present paper some of these variables will be discussed in terms of their effect on the cost and efficiency of potential processes. 7 refs., 4 figs., 4 tabs.

Premuzic, E.T.; Lin, M.S. (Brookhaven National Lab., Upton, NY (USA)); Kang, Sun Ki (Oregon State Univ., Corvallis, OR (USA). Dept. of Chemical Engineering)

1991-05-01T23:59:59.000Z

242

Mixed Waste Focus Area Mercury Working Group: An integrated approach to mercury waste treatment and disposal  

SciTech Connect

In May 1996, the US Department of Energy (DOE) Mixed Waste Focus Area (MWFA) initiated the Mercury Working Group (HgWG). The HgWG was established to address and resolve the issues associated with mercury contaminated mixed wastes. During the MWFA`s initial technical baseline development process, three of the top four technology deficiencies identified were related to the need for amalgamation, stabilization, and separation removal technologies for the treatment of mercury and mercury contaminated mixed waste. The HgWG is assisting the MWFA in soliciting, identifying, initiating, and managing efforts to address these areas. The focus of the HgWG is to better establish the mercury related treatment technologies at the DOE sites, refine the MWFA technical baseline as it relates to mercury treatment, and make recommendations to the MWFA on how to most effectively address these needs. Based on the scope and magnitude of the mercury mixed waste problem, as defined by HgWG, solicitations and contract awards have been made to the private sector to demonstrate both the amalgamation and stabilization processes using actual mixed wastes. Development efforts are currently being funded that will address DOE`s needs for separation removal processes. This paper discusses the technology selection process, development activities, and the accomplishments of the HgWG to date through these various activities.

Conley, T.B.; Morris, M.I.; Osborne-Lee, I.W.

1998-01-01T23:59:59.000Z

243

DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced  

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

Chooses Idaho Treatment Group, LLC to Disposition Waste at the Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed Waste Treatment Project: Contract will continue cleanup and waste operations at the Idaho Site DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed Waste Treatment Project: Contract will continue cleanup and waste operations at the Idaho Site May 27, 2011 - 12:00pm Addthis Media Contact Brad Bugger (208) 526-0833 Idaho Falls - In order to further meet the U.S. Department of Energy's commitments to the citizens of the state of Idaho, the DOE today announced that it has selected Idaho Treatment Group, LLC (ITG) to perform waste processing at the Advanced Mixed Waste Treatment Project (AMWTP) at DOE's Idaho Site near Idaho Falls. The contract is estimated at approximately

244

Radiological Monitoring of Waste Treatment Plant  

Science Conference Proceedings (OSTI)

Scheduled waste in West Malaysia is handled by Concession Company and is stored and then is incinerated. It is known that incineration process may result in naturally occurring radioactive materials (NORM) to be concentrated. In this study we have measured three samples consist of by-product from the operation process such as slag, filter cake and fly ash. Other various environmental media such as air, surface water, groundwater and soil within and around the plant have also been analysed for their radioactivity levels. The concentration of Ra-226, Ac-228 and K-40 in slag are 0.062 Bq/g, 0.016 Bq/g and 0.19 Bq/g respectively. The total activity (Ra{sub eq}) in slag is 99.5 Bq/kg. The concentration in fly ash is 0.032 Bq/g, 0.16 Bq/g and 0.34 Bq/g for Ra-226, Ac-228 and K-40 respectively resulting in Raeq of 287.0 Bq/kg. For filter cake, the concentration is 0.13 Bq/g, 0.031 Bq/g and 0.33 Bq/g for Ra-226, Ac-228 and K-40 respectively resulting in Raeq of 199.7 Bq/kg. The external radiation level ranges from 0.08 {mu}Sv/h (Administrative building) to 0.35 {mu}Sv/h (TENORM storage area). The concentration level of radon and thoron progeny varies from 0.0001 to 0.0016 WL and 0.0006 WL to 0.002 WL respectively. For soil samples, the activity ranges from 0.11 Bq/g to 0.29 Bq/g, 0.06 Bq/g to 0.18 Bq/g and 0.065 Bq/g to 0.38 Bq/g for Ra-226, Ac-228 and K-40 respectively. While activity in water, except for a trace of K-40, it is non-detectable.

Amin, Y. M. [Physics Dept, University of Malaya, 50603 Kuala Lumpur (Malaysia); Nik, H. W. [Asialab (Malaysia) Sdn Bhd, 14 Jalan Industri USJ 1, 47600 Subang Jaya (Malaysia)

2011-03-30T23:59:59.000Z

245

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

246

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

247

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 2. Alternatives for waste treatment  

DOE Green Energy (OSTI)

Volume II of the five-volume report is devoted to the description of alternatives for waste treatment. The discussion is presented under the following section titles: fuel reprocessing modifications; high-level liquid waste solidification; treatment and immobilization of chop-leach fuel bundle residues; treatment of noncombustible solid wastes; treatment of combustible wastes; treatment of non-high-level liquid wastes; recovery of transuranics from non-high-level wastes; immobilization of miscellaneous non-high-level wastes; volatile radioisotope recovery and off-gas treatment; immobilization of volatile radioisotopes; retired facilities (decontamination and decommissioning); and, modification and use of selected fuel reprocessing wastes. (JGB)

Not Available

1976-05-01T23:59:59.000Z

248

Shadow Review of the Advanced Mixed Waste Treatment Project Transuranic Storage Area Retrieval Enclosue Restrieval Restart DOE Readiness Assessment  

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

ID-2011-09-22 ID-2011-09-22 Site: Idaho Site - Idaho Cleanup Project Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Shadow Review of the Advanced Mixed Waste Treatment Project (AMWTP) Transuranic Storage Area-Retrieval Enclosure (TSA-RE) Retrieval Restart Department of Energy Readiness Assessment Dates of Activity : 09/20/2011 - 09/22/2011 Report Preparer: Aleem Boatright Activity Description/Purpose: A review of nuclear safety implementation verification review (IVR) procedures and processes was conducted at the Idaho Site from September 12-22, 2011. The scope originally included shadowing of the Department of Energy (DOE) Idaho Operations Office (DOE-ID) Idaho Cleanup Project IVR for the Sodium Bearing Waste Treatment Project (SBWTP).

249

Shadow Review of the Advanced Mixed Waste Treatment Project Transuranic Storage Area Retrieval Enclosue Restrieval Restart DOE Readiness Assessment  

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

ID-2011-09-22 ID-2011-09-22 Site: Idaho Site - Idaho Cleanup Project Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Shadow Review of the Advanced Mixed Waste Treatment Project (AMWTP) Transuranic Storage Area-Retrieval Enclosure (TSA-RE) Retrieval Restart Department of Energy Readiness Assessment Dates of Activity : 09/20/2011 - 09/22/2011 Report Preparer: Aleem Boatright Activity Description/Purpose: A review of nuclear safety implementation verification review (IVR) procedures and processes was conducted at the Idaho Site from September 12-22, 2011. The scope originally included shadowing of the Department of Energy (DOE) Idaho Operations Office (DOE-ID) Idaho Cleanup Project IVR for the Sodium Bearing Waste Treatment Project (SBWTP).

250

Plant for the treatment of waste  

SciTech Connect

A plant is described that is comprised of a post combustion chamber connected to the combustion chamber of a household rubbish incineration furnace whose hot gases it uses in order, by means of suitable berners to heat sewage sludges and industrial liquids and a circuit for the treatment of the smoke and residues coming from the post combustion. This circuit, which is held under vacuum by a blower, comprises a dry cooling tower employing semi-liquid sludges as cooling agent, an absorption tower employing a solution adapted to ombine the predominantly acid gases of the smoke, and a separating tower in which the liquids in suspension are removed. A recycle circuit for the solution and liquid separated and means of recovering metallic particles and compounds complete this plant.

Barkhuus, P.W.; Faldt, I.

1980-09-23T23:59:59.000Z

251

Remote handling equipment at the hanford waste treatment plant  

Science Conference Proceedings (OSTI)

Cold war plutonium production led to extensive amounts of radioactive waste stored in tanks at the Department of Energy's Hanford Waste Treatment Plant. The storage tanks could potentially leak into the ground water and into the Columbia River. The solution for this risk of the leaking waste is vitrification. Vitrification is a process of mixing molten glass with radioactive waste to form a stable condition for storage. The Department of Energy has contracted Bechtel National, Inc. to build facilities at the Hanford site to process the waste. The waste will be separated into high and low level waste. Four major systems will process the waste, two pretreatment and two high level. Due to the high radiation levels, high integrity custom cranes have been designed to remotely maintain the hot cells. Several critical design parameters were implemented into the remote machinery design, including radiation limitations, remote operations, Important to Safety features, overall equipment effectiveness, minimum wall approaches, seismic constraints, and recovery requirements. Several key pieces of equipment were designed to meet these design requirements - high integrity crane bridges, trolleys, main hoists, mast hoists, slewing hoists, a monorail hoist, and telescoping mast deployed tele-robotic manipulator arms. There were unique and challenging design features and equipment needed to provide the remotely operated high integrity crane/manipulator systems for the Hanford Waste Treatment Plant. The cranes consist of a double girder bridge with various main hoist capacities ranging from one to thirty ton and are used for performing routine maintenance. A telescoping mast mounted tele-robotic manipulator arm with a one-ton hook is deployed from the trolley to perform miscellaneous operations in-cell. A dual two-ton slewing jib hoist is mounted to the bottom of the trolley and rotates 360 degrees around the mast allowing the closest hook wall approaches. Each of the two hoists on this slewer is mounted 180 degrees opposite each other. Another system utilizes a single one-ton slewing jib hoist that can extend and retract as well as rotate 270 degrees around the mast. Yet, another system utilizes an under-hung monorail trolley with one-ton hoist capacity mounted to the bottom of the bridge girder. The main, slewer and monorail hoists each have power-rotating hooks for installing and removing equipment in the hot cell. (authors)

Bardal, M.A. [PaR Systems, Inc., Shoreview, MN, (United States); Roach, J.D. [Bechtel National, Inc., Richland, WA (United States)

2007-07-01T23:59:59.000Z

252

Recent developments in geothermal waste treatment biotechnology  

DOE Green Energy (OSTI)

Continuing studies at Brookhaven National Laboratory (BNL) have shown that cost-efficient biotechnology for the removal of toxic trace metals from geothermal sludge is feasible. Pilot-scale experiments have shown that fast rates (< 24-h) of metal removal at 55{degree}C--60{degree}C can be achieved with removal efficiencies of better than 80%, yielding a product well within the environmental regulatory limits. Recent studies have shown that radionuclides, such as radium present in low concentrations in some sludges, can also be removed by means of a secondary biotreatment. The process produces an aqueous phase which contains all of the regulatory metals in a soluble form. A follow-up technology for the treatment of the aqueous phase is concurrently being developed at BNL. Preliminary results indicate that a small volume concentrate of metals can be generated producing an aqueous phase which meets drinking water standards. In this paper the current state-of-the-biotechnology will be discussed.

Premuzic, E.T.; Lin, M.S.; Jin, J.Z.

1993-05-01T23:59:59.000Z

253

Treatment technology analysis for mixed waste containers and debris  

SciTech Connect

A team was assembled to develop technology needs and strategies for treatment of mixed waste debris and empty containers in the Department of Energy (DOE) complex, and to determine the advantages and disadvantages of applying the Debris and Empty Container Rules to these wastes. These rules issued by the Environmental Protection Agency (EPA) apply only to the hazardous component of mixed debris. Hazardous debris that is subjected to regulations under the Atomic Energy Act because of its radioactivity (i.e., mixed debris) is also subject to the debris treatment standards. The issue of treating debris per the Resource Conservation and Recovery Act (RCRA) at the same time or in conjunction with decontamination of the radioactive contamination was also addressed. Resolution of this issue requires policy development by DOE Headquarters of de minimis concentrations for radioactivity and release of material to Subtitle D landfills or into the commercial sector. The task team recommends that, since alternate treatment technologies (for the hazardous component) are Best Demonstrated Available Technology (BDAT): (1) funding should focus on demonstration, testing, and evaluation of BDAT on mixed debris, (2) funding should also consider verification of alternative treatments for the decontamination of radioactive debris, and (3) DOE should establish criteria for the recycle/reuse or disposal of treated and decontaminated mixed debris as municipal waste.

Gehrke, R.J. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Brown, C.H. [Oak Ridge National Lab., TN (United States); Langton, C.A.; Askew, N.M. [Savannah River Lab., Aiken, SC (United States); Kan, T. [Lawrence Livermore National Lab., CA (United States); Schwinkendorf, W.E. [BDM Federal, Inc., Albuquerque, NM (United States)

1994-03-01T23:59:59.000Z

254

Overview of non-thermal mixed waste treatment technologies: Treatment of mixed waste (ex situ); Technologies and short descriptions  

SciTech Connect

This compendium contains brief summaries of new and developing non- thermal treatment technologies that are candidates for treating hazardous or mixed (hazardous plus low-level radioactive) wastes. It is written to be all-encompassing, sometimes including concepts that presently constitute little more than informed ``ideas``. It bounds the universe of existing technologies being thought about or considered for application on the treatment of such wastes. This compendium is intended to be the very first step in a winnowing process to identify non-thermal treatment systems that can be fashioned into complete ``cradle-to-grave`` systems for study. The purpose of the subsequent systems paper studies is to investigate the cost and likely performance of such systems treating a representative sample of U.S. Department of Energy (DOE) mixed low level wastes (MLLW). The studies are called Integrated Non-thermal Treatment Systems (INTS) Studies and are being conducted by the Office of Science and Technology (OST) of the Environmental Management (EM) of the US Department of Energy. Similar studies on Integrated Thermal Treatment Systems have recently been published. These are not designed nor intended to be a ``downselection`` of such technologies; rather, they are simply a systems evaluation of the likely costs and performance of various non- thermal technologies that have been arranged into systems to treat sludges, organics, metals, soils, and debris prevalent in MLLW.

NONE

1995-07-01T23:59:59.000Z

255

Hanford Waste Treatment Plant Sets Massive Protective Shield door in  

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

Waste Treatment Plant Sets Massive Protective Shield door Waste Treatment Plant Sets Massive Protective Shield door in Pretreatment Facility Hanford Waste Treatment Plant Sets Massive Protective Shield door in Pretreatment Facility January 12, 2011 - 12:00pm Addthis The carbon steel doors come together to form an upside-down L-shape. The 102-ton door was set on top of the 85-ton door that was installed at the end of December. The carbon steel doors come together to form an upside-down L-shape. The 102-ton door was set on top of the 85-ton door that was installed at the end of December. The 102-ton shield door measures 52 feet wide and 15 feet tall The 102-ton shield door measures 52 feet wide and 15 feet tall The carbon steel doors come together to form an upside-down L-shape. The 102-ton door was set on top of the 85-ton door that was installed at the end of December.

256

Hazardous Waste/Mixed Waste Treatment Building Safety Information Document (SID)  

SciTech Connect

This Safety Information Document (SID) provides a description and analysis of operations for the Hazardous Waste/Mixed Waste Disposal Facility Treatment Building (the Treatment Building). The Treatment Building has been classified as a moderate hazard facility, and the level of analysis performed and the methodology used are based on that classification. Preliminary design of the Treatment Building has identified the need for two separate buildings for waste treatment processes. The term Treatment Building applies to all these facilities. The evaluation of safety for the Treatment Building is accomplished in part by the identification of hazards associated with the facility and the analysis of the facility`s response to postulated events involving those hazards. The events are analyzed in terms of the facility features that minimize the causes of such events, the quantitative determination of the consequences, and the ability of the facility to cope with each event should it occur. The SID presents the methodology, assumptions, and results of the systematic evaluation of hazards associated with operation of the Treatment Building. The SID also addresses the spectrum of postulated credible events, involving those hazards, that could occur. Facility features important to safety are identified and discussed in the SID. The SID identifies hazards and reports the analysis of the spectrum of credible postulated events that can result in the following consequences: Personnel exposure to radiation; Radioactive material release to the environment; Personnel exposure to hazardous chemicals; Hazardous chemical release to the environment; Events leading to an onsite/offsite fatality; and Significant damage to government property. The SID addresses the consequences to the onsite and offsite populations resulting from postulated credible events and the safety features in place to control and mitigate the consequences.

Fatell, L.B.; Woolsey, G.B.

1993-04-15T23:59:59.000Z

257

Newly Generated Liquid Waste Processing Alternatives Study, Volume 1  

SciTech Connect

This report identifies and evaluates three options for treating newly generated liquid waste at the Idaho Nuclear Technology and Engineering Center of the Idaho National Engineering and Environmental Laboratory. The three options are: (a) treat the waste using processing facilities designed for treating sodium-bearing waste, (b) treat the waste using subcontractor-supplied mobile systems, or (c) treat the waste using a special facility designed and constructed for that purpose. In studying these options, engineers concluded that the best approach is to store the newly generated liquid waste until a sodium-bearing waste treatment facility is available and then to co-process the stored inventory of the newly generated waste with the sodium-bearing waste. After the sodium-bearing waste facility completes its mission, two paths are available. The newly generated liquid waste could be treated using the subcontractor-supplied system or the sodium-bearing waste facility or a portion of it. The final decision depends on the design of the sodium-bearing waste treatment facility, which will be completed in coming years.

Landman, William Henry; Bates, Steven Odum; Bonnema, Bruce Edward; Palmer, Stanley Leland; Podgorney, Anna Kristine; Walsh, Stephanie

2002-09-01T23:59:59.000Z

258

Treatment of Organic-Contaminated Mixed Waste Utilizing the Oak Ridge Broad Spectrum Contracts  

SciTech Connect

To meet the requirements of the State of Tennessee's Department of Environment and Conservation Commissioner's Order for treatment of mixed low level wastes, Oak Ridge has utilized commercial treatment companies to treat and dispose mixed waste. Over the past year, Oak Ridge has shipped organic-contaminated mixed waste for treatment to meet milestones under the Site Treatment Plan. Oak Ridge has established contracts with commercial treatment companies accessible by all DOE sites for treatment of a wide range of mixed wastes. The paper will describe and summarize the activities involved in treating and disposing of organic-contaminated mixed waste utilizing DOE complex-wide contracts and the treatment and disposal activities required. This paper will describe the case history of treatment of several organic-contaminated mixed wastes from the Oak Ridge Reservation requiring treatment prior to disposal. The paper will include waste category information, implementation activities, and contract access. The paper will discuss the specifics of the mixed waste treatment including waste characteristics, treatment process and equipment utilized, and treatment results. Additional information will be provided on task order development, waste profiling, treatment pricing, and the disposal process.

Estes, C. H.; Heacker, F. K.; Cunningham, J.; Westich, B.

2003-02-25T23:59:59.000Z

259

HIGH ALUMINUM HLW (HIGH LEVEL WASTE ) GLASSES FOR HANFORDS WTP (WASTE TREATMENT PROJECT)  

Science Conference Proceedings (OSTI)

This paper presents the results of glass formulation development and melter testing to identify high waste loading glasses to treat high-Al high level waste (HLW) at Hanford. Previous glass formulations developed for this HLW had high waste loadings but their processing rates were lower that desired. The present work was aimed at improving the glass processing rate while maintaining high waste loadings. Glass formulations were designed, prepared at crucible-scale and characterized to determine their properties relevant to processing and product quality. Glass formulations that met these requirements were screened for melt rates using small-scale tests. The small-scale melt rate screening included vertical gradient furnace (VGF) and direct feed consumption (DFC) melter tests. Based on the results of these tests, modified glass formulations were developed and selected for larger scale melter tests to determine their processing rate. Melter tests were conducted on the DuraMelter 100 (DMIOO) with a melt surface area of 0.11 m{sup 2} and the DuraMelter 1200 (DMI200) HLW Pilot Melter with a melt surface area of 1.2 m{sup 2}. The newly developed glass formulations had waste loadings as high as 50 wt%, with corresponding Al{sub 2}O{sub 3} concentration in the glass of 26.63 wt%. The new glass formulations showed glass production rates as high as 1900 kg/(m{sup 2}.day) under nominal melter operating conditions. The demonstrated glass production rates are much higher than the current requirement of 800 kg/(m{sup 2}.day) and anticipated future enhanced Hanford Tank Waste Treatment and Immobilization Plant (WTP) requirement of 1000 kg/(m{sup 2}.day).

KRUGER AA; BOWAN BW; JOSEPH I; GAN H; KOT WK; MATLACK KS; PEGG IL

2010-01-04T23:59:59.000Z

260

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

Note: This page contains sample records for the topic "bearing waste treatment" 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 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

262

Waste treatment: Beverage industry. (Latest citations from Food Science & Technology Abstracts (FSTA)). Published Search  

SciTech Connect

The bibliography contains citations concerning waste treatment in the alcoholic and non-alcoholic beverage industries. Brewery effluent and wastewater management and disposal are reviewed. References cover aerobic treatment, sources of effluents, waste reduction, waste fermentation, effluent purification, and cost-effectiveness evaluation. The use of wastes for biogas production and for building material manufacture is examined. (Contains 50-250 citations and includes a subject term index and title list.)

NONE

1995-08-01T23:59:59.000Z

263

Assessment of incineration and melting treatment technologies for RWMC buried waste  

SciTech Connect

This report provides an identification, description, and ranking evaluation of the available thermal treatment technologies potentially capable of treating the Idaho National Engineering Laboratory Radioactive Waste Management Complex (RWMC) buried mixed waste. The ranking evaluation focused separately upon incinerators for treatment of combustible wastes and melters for noncombustible wastes. The highest rank incinerators are rotary kilns and controlled air furnaces, while the highest rank melters are the hearth configuration plasma torch, graphite electrode arc, and joule-heated melters. 4 refs.

Geimer, R.; Hertzler, T.; Gillins, R. (Science Applications International Corp., Idaho Falls, ID (United States)); Anderson, G.L. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

1992-02-01T23:59:59.000Z

264

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.

265

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.

266

Successful Waste Treatment Methods at Sandia National Laboratories  

SciTech Connect

During the remediation of the waste landfills at Sandia National Laboratory in Albuquerque, New Mexico nine drums of mock high explosives were generated. This mixed waste stream was proposed to several offsite vendors for treatment and prices ranged from $2.50 to $10 per gram a total cost estimated to be in excess of $2 million dollars. This cost represents more than 30 percent of the annual budget for the Sandia Waste Management Operations. Concentrated solutions of common oxidizers, such as nitrates, nitrites, and peroxides, will also act as oxidizers and will give positive results in the Hazard Categorization oxidizer test. These solutions carry an EPA Hazardous Waste Number D001, Ignitable Waste, and Oxidizer as defined in 49 CFR 173.151. Sandia decided that given budget and time constraints to meet a Federal Facilities Compliance Act milestone, a process for onsite treatment should be evaluated. Clean samples of mock high explosive materials were obtained from Pantex excess inventory and treatability studies initiated to develop a treatment formula and process. The following process was developed and implemented in the summer of 2006: - Size reduction to allow for dissolution of the barium nitrate in water; - Dissolution of the Mock HE in water; - Deactivation of the oxidizer; - Stabilization of the barium and the cadmium contamination present as an underlying hazardous constituent. This project was completed and the treatment milestone achieved for less than $300,000. The Disassembly Sanitization Operation (DSO) is a process that was implemented to support weapon disassembly and disposition using recycling and waste minimization while achieving the demilitarization mission. The Department of Energy is faced with disassembling and disposition of a huge inventory of retired weapons, components, training equipment, spare parts, and weapon maintenance equipment. Environmental regulations have caused a dramatic increase for information needed to support the disposal and handling of these parts and materials. Manufacturing information from past decades often does not meet the needs for regulatory decisions of today to assure proper management of weapons components. Huge inventories of classified weapon components were required to have long-term storage at Sandia and many other locations throughout the complex. These materials are stored because they are classified, they may also contain radiological and/or hazardous components and disposal options may not have existed for this material. Long-term storage is costly and somewhat problematic. It requires a secured storage area, monitoring, auditing and it also has the potential for loss or theft of this material. Overall recycling rates for materials sent through the DSO process have enabled 70 to 80% of these components to be recycled. These components are made to extreme standards and are made of high quality materials. Once the material has been sanitized, the demand for these metals is very high. The DSO process for the NGPF classified components established the credibility of this technique as a viable process for addressing the long-term storage requirements of classified weapons component inventory. The success of this operation has generated interest from other Sandia Organization other locations throughout the complex. Other organizations are soliciting the help of the DSO team and the DSO is responding to these solicitations by expanding its scope to include work for other projects. For example, Pantex has asked the DSO team to assist with the destruction of their classified components. The operation is full scale and continues to grow and serve SNL/NM and DoE by providing a solution to this evolving issue. On an ongoing basis, SNL has been incurring expenses for the management and storage of classified components. It is estimated that this project will save the DoE and Sandia several hundreds of thousands of dollars until the excess inventory is eliminated. This innovative approach eliminates the need for long-term storage of classified weapons components and the

Rast, D.M.; Thompson, J.J.; Cooper, T.W.; Stockham, D.J

2007-07-01T23:59:59.000Z

267

Croatian refiner meets waste water treatment standards, reduces fines  

Science Conference Proceedings (OSTI)

A new approach to waste water treatment at a refinery in Croatia produces effluent that not only meets the region`s regulations for disposal into the Adriatic Sea, but also surpasses the refinery`s specifications for recycling process water. Key to the dramatic reduction in pollutants was the installation of a Sandfloat unit developed by Krofta Engineering Corp. The Sandfloat unit is a dissolved air flotation clarifier that combines flocculation, flotation, and multilayer filtration to produce high-quality effluent. In fact, the effluent from the unit has a lower hydrocarbon concentration than water from the underground wells that supply process water to the refinery. While similar systems have been used for decades in industrial applications, this is the first time a Sandfloat unit has been installed in an oil refinery. The article describes the problem, refinery operations, treatment costs, and effluent recycling.

Meier, A.L. [Krofta Engineering Corp., Lenox, MA (United States); Nikolic, O. [INA Oil Refinery, Rijeka (Croatia)

1995-11-27T23:59:59.000Z

268

Hanford Waste Simulants Created to Support the Research and Development on the River Protection Project - Waste Treatment Plant  

Science Conference Proceedings (OSTI)

The development of nonradioactive waste simulants to support the River Protection Project - Waste Treatment Plant bench and pilot-scale testing is crucial to the design of the facility. The report documents the simulants development to support the SRTC programs and the strategies used to produce the simulants.

Eibling, R.E.

2001-07-26T23:59:59.000Z

269

Advanced Off-Gas Control System Design For Radioactive And Mixed Waste Treatment  

SciTech Connect

Treatment of radioactive and mixed wastes is often required to destroy or immobilize hazardous constituents, reduce waste volume, and convert the waste to a form suitable for final disposal. These kinds of treatments usually evolve off-gas. Air emission regulations have become increasingly stringent in recent years. Mixed waste thermal treatment in the United States is now generally regulated under the Hazardous Waste Combustor (HWC) Maximum Achievable Control Technology (MACT) standards. These standards impose unprecedented requirements for operation, monitoring and control, and emissions control. Off-gas control technologies and system designs that were satisfactorily proven in mixed waste operation prior to the implementation of new regulatory standards are in some cases no longer suitable in new mixed waste treatment system designs. Some mixed waste treatment facilities have been shut down rather than have excessively restrictive feed rate limits or facility upgrades to comply with the new standards. New mixed waste treatment facilities in the U. S. are being designed to operate in compliance with the HWC MACT standards. Activities have been underway for the past 10 years at the INL and elsewhere to identify, develop, demonstrate, and design technologies for enabling HWC MACT compliance for mixed waste treatment facilities. Some specific off-gas control technologies and system designs have been identified and tested to show that even the stringent HWC MACT standards can be met, while minimizing treatment facility size and cost.

Nick Soelberg

2005-09-01T23:59:59.000Z

270

Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report  

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

Comprehensive Review of the Hanford Tank Waste Treatment and Immobilization Plant Estimate at Completion Assessment Conducted by an Independent Team of External Experts March 2006 Comprehensive Review of the Hanford Waste Treatment Plant Estimate at Completion Page i of vi Executive Summary Following an August 2005 corporate commitment to the Secretary of Energy, Bechtel National, Inc. chartered a team of industry experts to review the technical, cost, and schedule aspects of the Waste Treatment and Immobilization Plant (WTP) project. This summary reflects the observations and recommendations of the EAC Review Team (ERT), comprised of six senior industry consultants, six retired Bechtel employees, one current Bechtel employee, three employees of Bechtel's competitors, and

271

Actinide extraction from ICPP sodium bearing waste with 0.75 M DHDECMP/TBP in Isopar L{reg_sign}  

SciTech Connect

Recent process development efforts at the Idaho Chemical Processing Plant include examination of solvent extraction technologies for actinide partitioning from sodium bearing waste (SBW) solutions. The use of 0.75 {und M} dihexyl-N, N-diethylcarbamoylmethylphosphonate (DHDECMP or simply CMP) and 1.0 {und M} tri-n-butyl phosphate (TBP) diluted in Isopar L{reg_sign} was explored for actinide removal from simulated SBW solutions. Experimental evaluations included batch contacts in radiotracer tests with simulated sodium bearing waste solution to measure the extraction and recovery efficiency of the organic solvent. The radioactive isotopes utilized for this study included Pu-238, Pu-239, Am-241, U-233, Np-239, Zr-95, Tc-99m, and Hg-203. Extraction contacts of the organic solvent with the traced SBW stimulant, strip (back-extraction) contacts of the loaded organic solvent with either a 1-hydroxyethane-1, 1-diphosphonic acid (HEDPA) in nitric acid solution or an oxalic acid in nitric acid solution, and solvent wash contacts with sodium carbonate were performed.

Herbst, R.S.; Brewer, K.N.; Garn, T.G.; Law, J.D.; Rodriguez, A.M.; Tillotson, R.T.

1996-01-01T23:59:59.000Z

272

The extraction of rare earth elements from ICPP sodium-bearing waste and dissolved zirconium calcine by CMP and TRUEX solvents  

SciTech Connect

The extraction of stable isotopes of Eu and Ce was investigated from simulated sodium-bearing waste (SBW) and dissolved zirconium calcine by TRUEX and CMP solvents at the Idaho Chemical Processing Plant (ICPP). Single batch contacts were carried out in order to evaluate the rare earth behavior in the extraction, scrub, strip and wash sections for the proposed flowsheets. It has been shown that these lanthanides are efficiently extracted from the sodium-bearing wastes into either solvent, are not scrubbed and are stripped from both of the extractants with dilute HEDPA. The extraction distribution coefficients for Ce and Eu are higher in the TRUEX solvent (D{sub Ce} = 11.7, D{sub Eu} = 14.9) compared with CMP (D{sub Ce} = 9.3, D{sub Eu} = 7.23) for SBW. The extraction distribution coefficients for Ce and Eu are considerably less in the TRUEX solvent (D{sub Ce}=1.13, D{sub Eu}=1.8) than in the CMP solvent (D{sub Ce}=7.4, D{sub Eu=}6.1) for dissolved zirconium calcine feeds. The lower distribution coefficients for the extraction of lanthanides in the TRUEX/dissolved zirconium calcine system can be explained by zirconium loading of the solvent. The data obtained also confirmed that Ce and Eu can be used as non-radioactive surrogates for Am in separation experiments with acidic solutions.

Todd, T.A.; Glagolenko, I.Y.; Herbst, R.S.; Brewer, K.N.

1995-11-01T23:59:59.000Z

273

EA-1106: Explosive Waste Treatment Facility at Site 300, Lawrence Livermore  

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

106: Explosive Waste Treatment Facility at Site 300, Lawrence 106: Explosive Waste Treatment Facility at Site 300, Lawrence Livermore National Laboratory, San Joaquin County, California EA-1106: Explosive Waste Treatment Facility at Site 300, Lawrence Livermore National Laboratory, San Joaquin County, California SUMMARY This EA evaluates the environmental impacts of the proposal to build, permit, and operate the Explosive Waste Treatment Facility to treat explosive waste at the U.S. Department of Energy's Lawrence Livermore National Laboratory Experimental Test Site, Site 300. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD April 16, 1996 EA-1106: Finding of No Significant Impact Explosive Waste Treatment Facility at Site 300, Lawrence Livermore National Laboratory April 16, 1996

274

RADIOACTIVE DEMONSTRATIONS OF FLUIDIZED BED STEAM REFORMING AS A SUPPLEMENTARY TREATMENT FOR HANFORD'S LOW ACTIVITY WASTE AND SECONDARY WASTES  

SciTech Connect

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTP's LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as Cs-137, I-129, Tc-99, Cl, F, and SO4 that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap. The current waste disposal path for the WTP-SW is to recycle it to the supplemental LAW treatment to avoid a large steady state accumulation in the pretreatment-vitrification loop. Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750 C) continuous method by which LAW and/or WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the Savannah River National Laboratory (SRNL) to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. Radioactive testing commenced in 2010 with a demonstration of Hanford's WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of I-125/129 and Tc-99 to chemically resemble WTP-SW. Ninety six grams of radioactive product were made for testing. The second campaign commenced using SRS LAW chemically trimmed to look like Hanford's LAW. Six hundred grams of radioactive product were made for extensive testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing.

Jantzen, C.; Crawford, C.; Cozzi, A.; Bannochie, C.; Burket, P.; Daniel, G.

2011-02-24T23:59:59.000Z

275

Plasma-chemical waste treatment of acid gases  

DOE Green Energy (OSTI)

The research to date has shown that a H{sub 2}S waste-treatment process based on plasma-chemical dissociation technology is compatible with refinery and high-carbon-oxide acid-gas streams. The minor amounts of impurities produced in the plasma-chemical reactor should be treatable by an internal catalytic reduction step. Furthermore, the plasma-chemical technology appears to be more efficient and more economical than the current technology. The principal key to achieving high conversions with relatively low energies of dissociation is the concept of the high-velocity, cyclonic-flow pattern in the plasma reaction zone coupled with the recycling of unconverted hydrogen sulfide. Future work will include testing the effects of components that might be carried over to the plasma reactor by ``upset`` conditions in the amine purification system of a plant and testing the plasma-chemical process on other industrial wastes streams that contain potentially valuable chemical reagents. The strategy for the commercialization of this technology is to form a Cooperative Research and Development Agreement with the Institute of Hydrogen Energy and Plasma Technology of the Russian Scientific Center/Kurchatov Institute and with an American start-up company to develop an ``American`` version of the process and to build a commercial-scale demonstration unit in the United States. The timetable proposed would involve building a ``field test`` facility which would test the plasma-chemical reactor and sulfur recovery unit operations on an industrial hydrogen sulfide waste s at a scale large enough to obtain the energy and material balance data required for a final analysis of the commercial potential of this technology. The field test would then be followed by construction of a commercial demonstration unit in two to three years. The commercial demonstration unit would be a fully integrated plant consisting of one commercial-scale module.

Harkness, J.B.L.; Doctor, R.D.; Daniels, E.J.

1993-09-01T23:59:59.000Z

276

Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants  

Science Conference Proceedings (OSTI)

This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m/sup 3//MTU for no treatment to as low as 0.02 m/sup 3//MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs.

Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

1985-07-01T23:59:59.000Z

277

WASTE TREATMENT AND DISPOSAL PROBLEMS OF THE FUTURE NUCLEAR POWER INDUSTRY  

SciTech Connect

The elements of waste treatment and disposal are assessed which are expected to become important in the development of the nuclear power industry of the future. Growth of the nuclear power economy is considered along with composition and quantities of anticipated waste. In addition, the economic implications of waste disposal are considered. It is concluded that research should be concentrated on decontaminating off-gases and on conversion of wastes to a more suitable form than liquid for storage. (J.R.D.)

Bruce, F.R.

1959-01-28T23:59:59.000Z

278

EA-1189: Non-thermal Treatment of Hanford Site Low-level Mixed Waste,  

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

9: Non-thermal Treatment of Hanford Site Low-level Mixed 9: Non-thermal Treatment of Hanford Site Low-level Mixed Waste, Richland, Washington EA-1189: Non-thermal Treatment of Hanford Site Low-level Mixed Waste, Richland, Washington SUMMARY This EA evaluates the environmental impacts for the proposal to demonstrate the feasibility of commercial treatment of contact-handled low-level mixed waste to meet existing Federal and State regulatory standards for eventual land disposal at the U.S. Department of Energy Richland Operations Office. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD September 29, 1998 EA-1189: Finding of No Significant Impact Non-thermal Treatment of Hanford Site Low-level Mixed Waste September 29, 1998 EA-1189: Final Environmental Assessment Non-thermal Treatment of Hanford Site Low-level Mixed Waste

279

Mixed Waste Focus Area mercury contamination product line: An integrated approach to mercury waste treatment and disposal  

SciTech Connect

The US Department of Energy (DOE) Mixed Waste Focus Area (MWFA) is tasked with ensuring that solutions are available for the mixed waste treatment problems of the DOE complex. During the MWFA`s initial technical baseline development process, three of the top four technology deficiencies identified were related to the need for amalgamation, stabilization, and separation/removal technologies for the treatment of mercury and mercury-contaminated mixed waste. The focus area grouped mercury-waste-treatment activities into the mercury contamination product line under which development, demonstration, and deployment efforts are coordinated to provide tested technologies to meet the site needs. The Mercury Working Group (HgWG), a selected group of representatives from DOE sites with significant mercury waste inventories, is assisting the MWFA in soliciting, identifying, initiating, and managing efforts to address these areas. Based on the scope and magnitude of the mercury mixed waste problem, as defined by HgWG, solicitations and contract awards have been made to the private sector to demonstrate amalgamation and stabilization processes using actual mixed wastes. Development efforts are currently being funded under the product line that will address DOE`s needs for separation/removal processes. This paper discusses the technology selection process, development activities, and the accomplishments of the MWFA to date through these various activities.

Hulet, G.A. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States); Conley, T.B.; Morris, M.I. [Oak Ridge National Lab., TN (United States)

1998-07-01T23:59:59.000Z

280

Constructed Wetland Treatment Systems for the Remediation of Metal-Bearing Aqueous Discharges  

Science Conference Proceedings (OSTI)

Constructed wetland treatment systems potentially offer utilities an effective, relatively low-cost option for treating aqueous discharges that contain metals. This report provides a ready source of information on these systems and their use within the electric utility industry.

1995-10-05T23:59:59.000Z

Note: This page contains sample records for the topic "bearing waste treatment" 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

WASTE TREATMENT AND DISPOSAL PROGRESS REPORT FOR AUGUST AND SEPTEMBER 1961  

SciTech Connect

Work is being carried out to develop and demonstrate on pilot plant scale integrated processes for treatment and disposal of radmoactive wastes. High-level waste calcination, low-level waste treatment, economic and hazards evaluation, engineering evaluation, disposal in deep wells, disposal in natural salt formations, Clinch River studies, fundamental studies of minerals, and White Oak Creek basin study are discussed. (M.C.G.)

Blanco, R.E.; Struxness, E.G.

1961-11-29T23:59:59.000Z

282

WASTE TREATMENT AND DISPOSAL PROGRESS REPORT FOR DECEMBER 1961 AND JANUARY 1962  

SciTech Connect

Progress in the development and demonstration on a pilot plant scale integrated processes for treatment and ultimate disposal of radioactive wastes is reported. Topics covered include: high-level waste calcination; lowlevel waste treatment; engineering, economics, and hazards evaluation; disposal ln deep wells; disposal in natural salt formations; Clinch River study; fundamental study of minerals; and White Oak Creek basin study. (M.C.G.)

Blanco, R.E.; Struxness, E.G.

1962-10-31T23:59:59.000Z

283

Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality, November 2011  

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

Hanford Site Waste Treatment and Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality May 2011 November 2011 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope .................................................................................................................................................... 1

284

Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality, November 2011  

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

Hanford Site Waste Treatment and Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality May 2011 November 2011 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope .................................................................................................................................................... 1

285

Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, August 2012  

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

Waste Treatment and Waste Treatment and Immobilization Plant Construction Quality May 2011 August 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 .................................................................................................................................................... 1

286

Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, August 2012  

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

Hanford Site Waste Treatment and Hanford Site Waste Treatment and Immobilization Plant Construction Quality May 2011 August 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 .................................................................................................................................................... 1

287

A preliminary evaluation of alternatives for treatment of INEL Low-Level Waste and low-level mixed waste  

SciTech Connect

The Mixed and Low-Level Waste Treatment Facility (MLLWTF) project was established in 1991 by the US Department of Energy Idaho Field Office to provide treatment capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This report identifies and evaluates the alternatives for treating that waste. Twelve treatment alternatives, ranging from ``no-action`` to constructing and operating the MLLWTF, are identified and evaluated. Evaluations include facility performance, environmental, safety, institutional, schedule, and rough order-of-magnitude cost comparisons. The performance of each alternative is evaluated against lists of ``musts`` and ``wants.`` Also included is a discussion of other key considerations for decision making. Analysis of results indicated further study is necessary to obtain the best estimate of future waste volumes and characteristics from the expanded INEL Decontamination and Decommissioning Program. It is also recommended that conceptual design begin as scheduled on the MLLWTF, maximum treatment alternative while re-evaluating the waste volume projections.

Smith, T.H.; Roesener, W.S.; Jorgensen-Waters, M.J.; Edinborough, C.R.

1992-06-01T23:59:59.000Z

288

Geothermal waste treatment biotechnology: Progress and advantages to the utilities  

DOE Green Energy (OSTI)

Development of biotechnology for treatment of geothermal residual waste is aimed at the application of low-cost biochemical processes for the surface treatment and disposal of residual geothermal sludges. These processes, in addition to the lowering of disposal cost, are designed to be environmentally acceptable. Recent studies at Brookhaven National Laboratory (BNL) have shown that optimization of several process variables results in fast rates (<24h) of metal removal from residual sludges at acidic pH ({minus}1--2). Optimization of the process variables also enables the removal of radioactive isotopes. In addition, the aqueous phase produced during the bioprocessing which contains solubilized metals can be further treated in a manner which precipitates out the metals and renders the aqueous effluent toxic metal free. In this paper, the various process options will be discussed in terms of biotreatment variables. Chemical composition before and after biotreatment will also be discussed in terms of long-range effects, quality assurance and potential disposal costs.

Premuzic, E.T.; Lin, M.S.; Jin, J.

1992-03-01T23:59:59.000Z

289

Geothermal Waste Treatment Biotechnology: Progress and Advantages to the Utilities  

DOE Green Energy (OSTI)

Development of biotechnology for treatment of geothermal residual waste is aimed at the application of low-cost biochemical processes for the surface treatment and disposal of residual geothermal sludges. These processes, in addition to the lowering of disposal cost, are designed to be environmentally acceptable. Recent studies at Brookhaven National Laboratory (BNL) have shown that optimization of several process variables results in fast rates (<24h) of metal removal from residual sludges at acidic pH ({approx}1-2). Optimization of the process variables also enables the removal of radioactive isotopes. In addition, the aqueous phase produced during the bioprocessing which contains solubilized metals can be further treated in a manner which precipitates out the metals and renders the aqueous effluent toxic metal free. In this paper, the various process options will be discussed in terms of biotreatment variables. Chemical composition before and after biotreatment will also be discussed in terms of long-range effects, quality assurance and potential disposal costs.

Premuzic, E.T.; Lin, M.S.; Jin, J.

1992-03-24T23:59:59.000Z

290

Followup of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process Systems Hazards Analysis Activity Review, March 2013  

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

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-03-18 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review Dates of Activity : 03/18/13 - 03/21/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff observed a limited portion of the restart of the Hazard Analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) System. The primary purpose of this HSS field activity, on March 18-21, 2013, was to observe and understand the revised approach

291

Followup of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process Systems Hazards Analysis Activity Review, March 2013  

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

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-03-18 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review Dates of Activity : 03/18/13 - 03/21/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff observed a limited portion of the restart of the Hazard Analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) System. The primary purpose of this HSS field activity, on March 18-21, 2013, was to observe and understand the revised approach

292

Pyrolysis/Steam Reforming Technology for Treatment of TRU Orphan Wastes  

SciTech Connect

Certain transuranic (TRU) waste streams within the Department of Energy (DOE) complex cannot be disposed of at the Waste Isolation Pilot Plant (WIPP) because they do not meet the shipping requirements of the TRUPACT-II or the disposal requirements of the Waste Analysis Plan (WAP) in the WIPP RCRA Part B Permit. These waste streams, referred to as orphan wastes, cannot be shipped or disposed of because they contain one or more prohibited items, such as liquids, volatile organic compounds (VOCs), hydrogen gas, corrosive acids or bases, reactive metals, or high concentrations of polychlorinated biphenyl (PCB), etc. The patented, non-incineration, pyrolysis and steam reforming processes marketed by THOR Treatment Technologies LLC removes all of these prohibited items from drums of TRU waste and produces a dry, inert, inorganic waste material that meets the existing TRUPACT-II requirements for shipping, as well as the existing WAP requirements for disposal of TRU waste at WIPP. THOR Treatment Technologies is a joint venture formed in June 2002 by Studsvik, Inc. (Studsvik) and Westinghouse Government Environmental Services Company LLC (WGES) to further develop and deploy Studsvik's patented THORSM technology within the DOE and Department of Defense (DoD) markets. The THORSM treatment process is a commercially proven system that has treated over 100,000 cu. ft. of nuclear waste from commercial power plants since 1999. Some of this waste has had contact dose rates of up to 400 R/hr. A distinguishing characteristic of the THORSM process for TRU waste treatment is the ability to treat drums of waste without removing the waste contents from the drum. This feature greatly minimizes criticality and contamination issues for processing of plutonium-containing wastes. The novel features described herein are protected by issued and pending patents.

Mason, J. B.; McKibbin, J.; Schmoker, D.; Bacala, P.

2003-02-27T23:59:59.000Z

293

RADIOACTIVE DEMONSTRATION OF FINAL MINERALIZED WASTE FORMS FOR HANFORD WASTE TREATMENT PLANT SECONDARY WASTE BY FLUIDIZED BED STEAM REFORMING USING THE BENCH SCALE REFORMER PLATFORM  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as {sup 137}Cs, {sup 129}I, {sup 99}Tc, Cl, F, and SO{sub 4} that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW. FBSR offers a moderate temperature (700-750 C) continuous method by which WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage, but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the SRNL to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. BSR testing with WTP SW waste surrogates and associated analytical analyses and tests of granular products (GP) and monoliths began in the Fall of 2009, and then was continued from the Fall of 2010 through the Spring of 2011. Radioactive testing commenced in 2010 with a demonstration of Hanford's WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of {sup 125/129}I and {sup 99}Tc to chemically resemble WTP-SW. Prior to these radioactive feed tests, non-radioactive simulants were also processed. Ninety six grams of radioactive granular product were made for testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing.

Crawford, C.; Burket, P.; Cozzi, A.; Daniel, W.; Jantzen, C.; Missimer, D.

2012-02-02T23:59:59.000Z

294

Mixed Waste Focus Area Working Group: An Integrated Approach to Mercury Waste Treatment and Disposal. Revision 1  

SciTech Connect

May 1996, the U.S. Department of Energy (DOE) Mixed Waste Focus Area (MWFA) initiated the Mercury Work Group (HgWG). The HgWG was established to address and resolve the issues associated with Mercury- contaminated mixed wastes (MWs). During the initial technical baseline development process of the MWFA, three of the top four technology deficiencies identified were related to (1) amalgamation, (2) stabilization, and (3) separation and removal for the treatment of mercury and mercury-contaminated mixed waste (MW). The HgWG is assisting the MWFA in soliciting, identifying, initiating, and managing efforts to address these needs.

Morris, M.I.; Conley, T.B.; Osborne-Lee, I.W.

1997-09-08T23:59:59.000Z

295

Strategies for the cost effective treatment of Oak Ridge legacy wastes  

Science Conference Proceedings (OSTI)

Research and development treatment strategies for treatment or elimination of several Oak Ridge plant liquid, solid, and legacy wastes are detailed in this report. Treatment strategies for volumetrically contaminated nickel; enriched uranium-contaminated alkali metal fluorides; uranium-contaminated aluminum compressor blades; large, mercury-contaminated lithium isotope separations equipment; lithium process chlorine gas streams; high-concentration aluminum nitrate wastes, and high-volume, low-level nitrate wastes are discussed. Research needed to support engineering development of treatment processes is detailed.

Compere, A.L.; Griffith, W.L.; Huxtable, W.P.; Wilson, D.F.

1998-03-01T23:59:59.000Z

296

GRR/Section 18-HI-b - RCRA - Hazardous Waste Treatment, Storage, and  

Open Energy Info (EERE)

8-HI-b - RCRA - Hazardous Waste Treatment, Storage, and 8-HI-b - RCRA - Hazardous Waste Treatment, Storage, and Disposal Permit (TSD) < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-HI-b - RCRA - Hazardous Waste Treatment, Storage, and Disposal Permit (TSD) 18HIB - RCRAHazardousWasteTreatmentStorageAndDisposalPermitTSD.pdf Click to View Fullscreen Contact Agencies Hawaii Department of Health Solid and Hazardous Waste Branch United States Environmental Protection Agency Regulations & Policies Resource Conversation and Recovery Act (42 U.S.C. 6901, et seq.) 40 CFR 270 Hawaii Administrative Rules Title 11, Chapter 261 Hawaii Administrative Rules Title 11, Chapter 265 Triggers None specified Click "Edit With Form" above to add content

297

Mixed Waste Advanced Treatment Technology: Waste Processing Products and Their Recycling Applications  

Science Conference Proceedings (OSTI)

During their operations, nuclear power plants generate mixed waste containing both hazardous and radioactive constituents. Disposal options for such mixed waste are limited and expensive. EPRI research has demonstrated that an innovative molten metal process for destroying hazardous wastes can be used effectively on nuclear power plant wastes containing both hazardous and radioactive constituents. Preliminary results of this research indicate that the destruction of the hazardous constituents is complete...

1997-12-31T23:59:59.000Z

298

Mixed and Low-Level Waste Treatment Facility Project. Appendix B, Waste stream engineering files: Part 2, Low-level waste streams  

SciTech Connect

Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report documents those studies so the project can continue with an evaluation of programmatic options, system tradeoff studies, and the conceptual design phase of the project. This report, appendix B, comprises the engineering design files for this project study. The engineering design files document each waste steam, its characteristics, and identified treatment strategies.

1992-04-01T23:59:59.000Z

299

DEMONSTRATION OF SIMULATED WASTE TRANSFERS FROM TANK AY-102 TO THE HANFORD WASTE TREATMENT FACILITY  

SciTech Connect

In support of Hanford's AY-102 Tank waste certification and delivery of the waste to the Waste Treatment and Immobilization Plant (WTP), Savannah River National Laboratory (SRNL) was tasked by the Washington River Protection Solutions (WRPS) to evaluate the effectiveness of mixing and transferring the waste in the Double Shell Tank (DST) to the WTP Receipt Tank. This work is a follow-on to the previous 'Demonstration of Internal Structures Impacts on Double Shell Tank Mixing Effectiveness' task conducted at SRNL 1. The objective of these transfers was to qualitatively demonstrate how well waste can be transferred out of a mixed DST tank and to provide insights into the consistency between the batches being transferred. Twelve (12) different transfer demonstrations were performed, varying one parameter at a time, in the Batch Transfer Demonstration System. The work focused on visual comparisons of the results from transferring six batches of slurry from a 1/22nd scale (geometric by diameter) Mixing Demonstration Tank (MDT) to six Receipt Tanks, where the consistency of solids in each batch could be compared. The simulant used in this demonstration was composed of simulated Hanford Tank AZ-101 supernate, gibbsite particles, and silicon carbide particles, the same simulant/solid particles used in the previous mixing demonstration. Changing a test parameter may have had a small impact on total solids transferred from the MDT on a given test, but the data indicates that there is essentially no impact on the consistency of solids transferred batch to batch. Of the multiple parameters varied during testing, it was found that changing the nozzle velocity of the Mixer Jet Pumps (MJPs) had the biggest impact on the amount of solids transferred. When the MJPs were operating at 8.0 gpm (22.4 ft/s nozzle velocity, U{sub o}D=0.504 ft{sup 2}/s), the solid particles were more effectively suspended, thus producing a higher volume of solids transferred. When the MJP flow rate was reduced to 5 gpm (14 ft/s nozzle velocity, U{sub o}D = 0.315 ft{sup 2}/s) to each pump, dead zones formed in the tank, resulting in fewer solids being transferred in each batch to the Receipt Tanks. The larger, denser particles were displaced (preferentially to the smaller particles) to one of the two dead zones and not re-suspended for the duration of the test. As the liquid level dropped in the MDT, re-suspending the particles became less effective (6th batch). The poor consistency of the solids transferred in the 6th batch was due to low liquid level in the MDT, thus poor mixing by the MJPs. Of the twelve tests conducted the best transfer of solids occurred during Test 6 and 8 where the MJP rotation was reduced to 1.0 rpm.

Adamson, D.; Poirier, M.; Steeper, T.

2009-12-03T23:59:59.000Z

300

Radioactive Liquid Waste Treatment Facility Discharges in 2011  

Science Conference Proceedings (OSTI)

This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one of these pathways was used; all treated water (3,352,890 liters) was fed to the effluent evaporator. The quality of treated water was established by collecting a weekly grab sample of water being fed to the effluent evaporator. Forty weekly samples were collected; each was analyzed for gross alpha, gross beta, and tritium. Weekly samples were also composited at the end of each month. These flow-weighted composite samples were then analyzed for 37 radioisotopes: nine alpha-emitting isotopes, 27 beta emitters, and tritium. These monthly analyses were used to estimate the radioactive content of treated water fed to the effluent evaporator. Table 1 summarizes this information. The concentrations and quantities of radioactivity in Table 1 are for treated water fed to the evaporator. Amounts of radioactivity discharged to the environment through the evaporator stack were likely smaller since only entrained materials would exit via the evaporator stack.

Del Signore, John C. [Los Alamos National Laboratory

2012-05-16T23:59:59.000Z

Note: This page contains sample records for the topic "bearing waste treatment" 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

Initial Selection of Supplemental Treatment Technologies for Hanford's Low-Activity Tank Waste  

Science Conference Proceedings (OSTI)

In 2002, the U.S. Department of Energy (DOE) documented a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years (DOE 2002). A key element of the accelerated cleanup plan was a strategic initiative for acceleration of the tank waste program and completion of "tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (ETP) and using supplemental technologies for waste treatment and immobilization." The plan identified specific technologies to be evaluated for supplemental treatment of as much as 70% of the low-activity waste (LAW). The objective was to complete required testing and evaluation that would "...bring an appropriate combination of the above technologies to deployment to supplement LAW treatment and immobilization in the WTP to achieve the completion of tank waste treatment by 2028." In concert with this acceleration plan, DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology have proposed to accelerate from 2012 to 2005 the Hanford Federal Facility Compliance Agreement (Tri-Party Agreement) milestone (M-62-08) associated with a final decision on treatment of the balance of tank waste that is beyond the capacity of the currently designed WTP.

Raymond, Richard E.; Powell, Roger W.; Hamilton, Dennis W.; Kitchen, William A.; Mauss, Billie M.; Brouns, Thomas M.

2004-07-15T23:59:59.000Z

302

Report: Findings, Conclusions, and Recommendations Concerning the Waste Treatment and Immobilization Project at Hanford  

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

EMAB Tank Waste Subcommittee Summary Report 1 EMAB Tank Waste Subcommittee Summary Report 1 Report of Findings, Conclusions, and Recommendations Concerning the Waste Treatment and Immobilization Project (WTP) at Hanford Submitted by the Environmental Management Advisory Board Tank Waste Subcommittee September 15, 2010 Introduction In May 2010, the Department of Energy established the Environmental Management Tank Waste Subcommittee (EM-TWS). The EM-TWS was charged with conducting an independent technical review of liquid waste capital and operations projects related to the Office of Environmental Management (EM) tank waste cleanup programs at Hanford, Washington; the Savannah River Site in South Carolina; the Idaho National Laboratory; and the West Valley Demonstration Project in New York. The EM-TWS's review focused on the facilities being

303

Record of Decision for the Department of Energy's Waste Management Program; Treatment and Storage of Transuranic Waste  

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

3630 3630 Federal Register / Vol. 63, No. 15 / Friday, January 23, 1998 / Notices to agreements DOE has entered into, such as those with States, relating to the treatment and storage of TRU waste. Future NEPA review could include, but would not necessarily be limited to, analysis of the need to supplement existing environmental reviews. DOE would conduct all such TRU waste shipments between sites in accordance with applicable transportation requirements and would coordinate these shipments with appropriate State, Tribal and local authorities. This Record of Decision was prepared in coordination with the Record of Decision issued on January 16, 1998, on disposal of DOE's TRU waste, which is based on the Waste Isolation Pilot Plant Disposal Phase Final Supplemental Environmental Impact Statement (WIPP

304

HIGH TEMPERATURE TREATMENT OF INTERMEDIATE-LEVEL RADIOACTIVE WASTES - SIA RADON EXPERIENCE  

SciTech Connect

This review describes high temperature methods of low- and intermediate-level radioactive waste (LILW) treatment currently used at SIA Radon. Solid and liquid organic and mixed organic and inorganic wastes are subjected to plasma heating in a shaft furnace with formation of stable leach resistant slag suitable for disposal in near-surface repositories. Liquid inorganic radioactive waste is vitrified in a cold crucible based plant with borosilicate glass productivity up to 75 kg/h. Radioactive silts from settlers are heat-treated at 500-700 0C in electric furnace forming cake following by cake crushing, charging into 200 L barrels and soaking with cement grout. Various thermochemical technologies for decontamination of metallic, asphalt, and concrete surfaces, treatment of organic wastes (spent ion-exchange resins, polymers, medical and biological wastes), batch vitrification of incinerator ashes, calcines, spent inorganic sorbents, contaminated soil, treatment of carbon containing 14C nuclide, reactor graphite, lubricants have been developed and implemented.

Sobolev, I.A.; Dmitriev, S.A.; Lifanov, F.A.; Kobelev, A.P.; Popkov, V.N.; Polkanov, M.A.; Savkin, A.E.; Varlakov, A.P.; Karlin, S.V.; Stefanovsky, S.V.; Karlina, O.K.; Semenov, K.N.

2003-02-27T23:59:59.000Z

305

Mixed Waste Treatment Cost Analysis for a Range of GeoMelt Vitrification Process Configurations  

Science Conference Proceedings (OSTI)

GeoMelt is a batch vitrification process used for contaminated site remediation and waste treatment. GeoMelt can be applied in several different configurations ranging from deep subsurface in situ treatment to aboveground batch plants. The process has been successfully used to treat a wide range of contaminated wastes and debris including: mixed low-level radioactive wastes; mixed transuranic wastes; polychlorinated biphenyls; pesticides; dioxins; and a range of heavy metals. Hypothetical cost estimates for the treatment of mixed low-level radioactive waste were prepared for the GeoMelt subsurface planar and in-container vitrification methods. The subsurface planar method involves in situ treatment and the in-container vitrification method involves treatment in an aboveground batch plant. The projected costs for the subsurface planar method range from $355-$461 per ton. These costs equate to 18-20 cents per pound. The projected cost for the in-container method is $1585 per ton. This cost equates to 80 cents per pound. These treatment costs are ten or more times lower than the treatment costs for alternative mixed waste treatment technologies according to a 1996 study by the US Department of Energy.

Thompson, L. E.

2002-02-27T23:59:59.000Z

306

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

307

The effect of Ca-Fe-As coatings on microbial leaching of metals in arsenic bearing mine waste  

Science Conference Proceedings (OSTI)

Globally arsenic (As) is a ubiquitous trace element derived from the natural weathering of As-bearing rock. With the onset of reducing conditions, the prevalence of aqueous As(III) may be intensified through biotic and abiotic processes. Here we evaluate the stability of arsenic bearing Ca-Fe hydroxide phases collected from exposed tailings at Ketza River mine, Yukon, Canada, during the reductive dissolution of both acid treated and untreated samples by Shewanella putrefaciens 200R and Shewanella sp. ANA-3. Samples were acid treated in order to remove Ca-Fe oxide coatings and evaluate the influence of these coatings on the rates of microbial Fe(III) and As(V) reduction. Environmental scanning electron microscope (ESEM) micrographs of the solid phase show significant differences in the chemistry and physical morphology of the material by the bacteria over time and are especially evident in the acid treated samples. Moreover, while solution chemistry showed similar As(III) respiration rates of the inoculated acid treated samples for both ANA3 and 200R at {approx}1.1 x 10{sup -6} {micro}M {center_dot} s{sup -1} {center_dot} m{sup -2}, the Fe(II) respiration rates differed at 1.4 x 10{sup -7} and 9.5 x 10{sup -8} {micro}M {center_dot} s{sup -1} {center_dot} m{sup -2} respectively, thus suggesting strain specific metal reduction metabolic pathways Additionally, the enhanced metal reduction observed in the acid treated inoculated samples suggests that the presence of the Ca-Fe hydroxide phase in the untreated samples acted as a barrier, inhibiting the bacteria from accessing the metals. This has implications for increased mobilization of metals by metal reducing bacteria within areas of increased acidity, such as acid mine drainage sites and industrial tailings ponds that can come into contact with surface and ground water sources.

Weisener, C.G.; Guthrie, J.W.; Smeaton, C.M.; Paktunc, D.; Fryer, B.J. (Windsor); (NRC)

2011-11-07T23:59:59.000Z

308

Development of an Alternative Treatment Scheme for Sr/TRU Removal: Permanganate Treatment of AN-107 Waste  

SciTech Connect

A number of Hanford tanks received waste containing organic complexants, which increase the volubility of Sr-90 and transuranic (TRU) elements. Wastes from these tanks require additional pretreatment to remove Sr-90 and TRU for immobilization as low activity waste (Waste Envelope C). The baseline pretreatment process for Sr/TRU removal was isotopic exchange and precipitation with added strontium and iron. However, studies at both Battelle and Savannah River Technology Center (SRTC) have shown that the Sr/Fe precipitates were very difficult to filter. This was a result of the formation of poor filtering iron solids. An alternate treatment technology was needed for Sr/TRU removal. Battelle had demonstrated that permanganate treatment was effective for decontaminating waste samples from Hanford Tank SY-101 and proposed that permanganate be examined as an alternative Sr/TRU removal scheme for complexant-containing tank wastes such as AW107. Battelle conducted preliminary small-scale experiments to determine the effectiveness of permanganate treatment with AN-107 waste samples that had been archived at Battelle from earlier studies. Three series of experiments were performed to evaluate conditions that provided adequate Sr/TRU decontamination using permanganate treatment. The final series included experiments with actual AN-107 diluted feed that had been obtained specifically for BNFL process testing. Conditions that provided adequate Sr/TRU decontamination were identified. A free hydroxide concentration of 0.5M provided adequate decontamination with added Sr of 0.05M and permanganate of 0.03M for archived AN-107. The best results were obtained when reagents were added in the sequence Sr followed by permanganate with the waste at ambient temperature. The reaction conditions for Sr/TRU removal will be further evaluated with a 1-L batch of archived AN-107, which will provide a large enough volume of waste to conduct crossflow filtration studies (Hallen et al. 2000a).

RT Hallen; SA Bryan; FV Hoopes

2000-08-04T23:59:59.000Z

309

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 1, Waste streams and treatment technologies  

SciTech Connect

This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

Neupauer, R.M.; Thurmond, S.M.

1992-09-01T23:59:59.000Z

310

ONE SYSTEM INTEGRATED PROJECT TEAM: RETRIEVAL AND DELIVERY OF THE HANFORD TANK WASTES FOR VITRIFICATION IN THE WASTE TREATMENT PLANT  

SciTech Connect

The One System Integrated Project Team (IPT) was formed in late 2011 as a way for improving the efficiency of delivery and treatment of highly radioactive waste stored in underground tanks at the U.S. Department of Energy's (DOE's) 586-square-mile Hanford Site in southeastern Washington State. The purpose of the One System IPT is to improve coordination and integration between the Hanford's Waste Treatment Plant (WTP) contractor and the Tank Operations Contractor (TOC). The vision statement is: One System is a WTP and TOC safety conscious team that, through integrated management and implementation of risk-informed decision and mission-based solutions, will enable the earliest start of safe and efficient treatment of Hanford's tank waste, to protect the Columbia River, environment and public. The IPT is a formal collaboration between Bechtel National, Inc. (BNI), which manages design and construction of the WTP for the U.S. Department of Energy's Office of River Protection (DOEORP), and Washington River Protection Solutions (WRPS), which manages the TOC for ORP. More than fifty-six (56) million gallons of highly radioactive liquid waste are stored in one hundred seventy-seven (177) aging, underground tanks. Most of Hanford's waste tanks - one hundred forty-nine (149) of them - are of an old single-shell tank (SST) design built between 1944 and 1964. More than sixty (60) of these tanks have leaked in the past, releasing an estimated one million gallons of waste into the soil and threatening the nearby Columbia River. There are another twenty-eight (28) new double-shelled tanks (DSTs), built from 1968 to 1986, that provide greater protection to the environment. In 1989, DOE, the U.S. Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) signed a landmark agreement that required Hanford to comply with federal and state environmental standards. It also paved the way for agreements that set deadlines for retrieving the tank wastes and for building and operating the WTP. The tank wastes are the result of Hanford's nearly fifty (50) years of plutonium production. In the intervening years, waste characteristics have been increasingly better understood. However, waste characteristics that are uncertain and will remain as such represent a significant technical challenge in terms of retrieval, transport, and treatment, as well as for design and construction ofWTP. What also is clear is that the longer the waste remains in the tanks, the greater the risk to the environment and the people of the Pacific Northwest. The goal of both projects - tank operations and waste treatment - is to diminish the risks posed by the waste in the tanks at the earliest possible date. About two hundred (200) WTP and TOC employees comprise the IPT. Individual work groups within One System include Technical, Project Integration & Controls, Front-End Design & Project Definition, Commissioning, Nuclear Safety & Engineering Systems Integration, and Environmental Safety and Health and Quality Assurance (ESH&QA). Additional functions and team members will be added as the WTP approaches the operational phase. The team has undertaken several initiatives since its formation to collaborate on issues: (1) alternate scenarios for delivery of wastes from the tank farms to WTP; (2) improvements in managing Interface Control Documents; (3) coordination on various technical issues, including the Defense Nuclear Facilities Nuclear Safety Board's Recommendation 2010-2; (4) deployment of the SmartPlant® Foundation-Configuration Management System; and (5) preparation of the joint contract deliverable of the Operational Readiness Support Plan.

HARP BJ; KACICH RM; SKWAREK RJ

2012-12-20T23:59:59.000Z

311

One System Integrated Project Team: Retrieval And Delivery Of The Hanford Tank Wastes For Vitrification In The Waste Treatment Plant  

Science Conference Proceedings (OSTI)

The One System Integrated Project Team (IPT) was formed in late 2011 as a way for improving the efficiency of delivery and treatment of highly radioactive waste stored in underground tanks at the U.S. Department of Energy's (DOE's) 586-square-mile Hanford Site in southeastern Washington State. The purpose of the One System IPT is to improve coordination and integration between the Hanford's Waste Treatment Plant (WTP) contractor and the Tank Operations Contractor (TOC). The vision statement is: One System is a WTP and TOC safety conscious team that, through integrated management and implementation of risk-informed decision and mission-based solutions, will enable the earliest start of safe and efficient treatment of Hanford's tank waste, to protect the Columbia River, environment and public. The IPT is a formal collaboration between Bechtel National, Inc. (BNI), which manages design and construction of the WTP for the U.S. Department of Energy's Office of River Protection (DOEORP), and Washington River Protection Solutions (WRPS), which manages the TOC for ORP. More than fifty-six (56) million gallons of highly radioactive liquid waste are stored in one hundred seventy-seven (177) aging, underground tanks. Most of Hanford's waste tanks - one hundred forty-nine (149) of them - are of an old single-shell tank (SST) design built between 1944 and 1964. More than sixty (60) of these tanks have leaked in the past, releasing an estimated one million gallons of waste into the soil and threatening the nearby Columbia River. There are another twenty-eight (28) new double-shelled tanks (DSTs), built from 1968 to 1986, that provide greater protection to the environment. In 1989, DOE, the U.S. Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) signed a landmark agreement that required Hanford to comply with federal and state environmental standards. It also paved the way for agreements that set deadlines for retrieving the tank wastes and for building and operating the WTP. The tank wastes are the result of Hanford's nearly fifty (50) years of plutonium production. In the intervening years, waste characteristics have been increasingly better understood. However, waste characteristics that are uncertain and will remain as such represent a significant technical challenge in terms of retrieval, transport, and treatment, as well as for design and construction ofWTP. What also is clear is that the longer the waste remains in the tanks, the greater the risk to the environment and the people of the Pacific Northwest. The goal of both projects - tank operations and waste treatment - is to diminish the risks posed by the waste in the tanks at the earliest possible date. About two hundred (200) WTP and TOC employees comprise the IPT. Individual work groups within One System include Technical, Project Integration & Controls, Front-End Design & Project Definition, Commissioning, Nuclear Safety & Engineering Systems Integration, and Environmental Safety and Health and Quality Assurance (ESH&QA). Additional functions and team members will be added as the WTP approaches the operational phase. The team has undertaken several initiatives since its formation to collaborate on issues: (1) alternate scenarios for delivery of wastes from the tank farms to WTP; (2) improvements in managing Interface Control Documents; (3) coordination on various technical issues, including the Defense Nuclear Facilities Nuclear Safety Board's Recommendation 2010-2; (4) deployment of the SmartPlant? Foundation-configuration Management System; and (5) preparation of the joint contract deliverable of the Operational Readiness Support Plan.

Harp, Benton J. [Department of Energy, Office of River Protection, Richland, Washington (United States); Kacich, Richard M. [Bechtel National, Inc., Richland, WA (United States); Skwarek, Raymond J. [Washington River Protection Solutions LLC, Richland, WA (United States)

2012-12-20T23:59:59.000Z

312

Geology of the Waste Treatment Plant Seismic Boreholes  

Science Conference Proceedings (OSTI)

In 2006, DOE-ORP initiated the Seismic Boreholes Project (SBP) to emplace boreholes at the Waste Treatment Plant (WTP) site in order to obtain direct Vs measurements and other physical property measurements in Columbia River basalt and interbedded sediments of the Ellensburg Formation. The goal was to reduce the uncertainty in the response spectra and seismic design basis, and potentially recover design margin for the WTP. The characterization effort within the deep boreholes included 1) downhole measurements of the velocity properties of the suprabasalt, basalt, and sedimentary interbed sequences, 2) downhole measurements of the density of the subsurface basalt and sediments, and 3) confirmation of the geometry of the contact between the various basalt and interbedded sediments through examination of retrieved core from the corehole and data collected through geophysical logging of each borehole. This report describes the results of the geologic studies from three mud-rotary boreholes and one cored borehole at the WTP. All four boreholes penetrated the entire Saddle Mountains Basalt and the upper part of the Wanapum Basalt where thick sedimentary interbeds occur between the lava flows. The basalt flows penetrated in Saddle Mountains Basalt included the Umatilla Member, Esquatzel Member, Pomona Member and the Elephant Mountain Member. The underlying Priest Rapids Member of the Wanapum Basalt was also penetrated. The Ellensburg Formation sediments consist of the Mabton Interbed, the Cold Creek Interbed, the Selah Interbed and the Rattlesnake Ridge Interbed; the Byron Interbed occurs between two flows of the Priest Rapids Member. The Mabton Interbed marks the contact between the Wanapum and Saddle Mountains Basalts. The thicknesses of the basalts and interbedded sediments were within expected limits. However, a small reverse fault was found in the Pomona Member flow top. This fault has three periods of movement and less than 15 feet of repeated section. Most of the movement on the fault appears to have occurred before the youngest lava flow, the 10.5 million year old Elephant Mountain Member was emplaced above the Pomona Member.

Barnett, D. BRENT; Bjornstad, Bruce N.; Fecht, Karl R.; Lanigan, David C.; Reidel, Steve; Rust, Colleen F.

2007-02-28T23:59:59.000Z

313

Biological Information Document, Radioactive Liquid Waste Treatment Facility  

SciTech Connect

This document is intended to act as a baseline source material for risk assessments which can be used in Environmental Assessments and Environmental Impact Statements. The current Radioactive Liquid Waste Treatment Facility (RLWTF) does not meet current General Design Criteria for Non-reactor Nuclear Facilities and could be shut down affecting several DOE programs. This Biological Information Document summarizes various biological studies that have been conducted in the vicinity of new Proposed RLWTF site and an Alternative site. The Proposed site is located on Mesita del Buey, a mess top, and the Alternative site is located in Mortandad Canyon. The Proposed Site is devoid of overstory species due to previous disturbance and is dominated by a mixture of grasses, forbs, and scattered low-growing shrubs. Vegetation immediately adjacent to the site is a pinyon-juniper woodland. The Mortandad canyon bottom overstory is dominated by ponderosa pine, willow, and rush. The south-facing slope was dominated by ponderosa pine, mountain mahogany, oak, and muhly. The north-facing slope is dominated by Douglas fir, ponderosa pine, and oak. Studies on wildlife species are limited in the vicinity of the proposed project and further studies will be necessary to accurately identify wildlife populations and to what extent they utilize the project area. Some information is provided on invertebrates, amphibians and reptiles, and small mammals. Additional species information from other nearby locations is discussed in detail. Habitat requirements exist in the project area for one federally threatened wildlife species, the peregrine falcon, and one federal candidate species, the spotted bat. However, based on surveys outside of the project area but in similar habitats, these species are not expected to occur in either the Proposed or Alternative RLWTF sites. Habitat Evaluation Procedures were used to evaluate ecological functioning in the project area.

Biggs, J.

1995-12-31T23:59:59.000Z

314

Mixed and Low-Level Waste Treatment Facility project. Executive summary: Volume 1, Program summary information; Volume 2, Waste stream technical summary: Draft  

SciTech Connect

Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. The engineering studies, initiated in July 1991, identified 37 mixed waste streams, and 55 low-level waste streams. This report documents the waste stream information and potential treatment strategies, as well as the regulatory requirements for the Department of Energy-owned treatment facility option. The total report comprises three volumes and two appendices. This report consists of Volume 1, which explains the overall program mission, the guiding assumptions for the engineering studies, and summarizes the waste stream and regulatory information, and Volume 2, the Waste Stream Technical Summary which, encompasses the studies conducted to identify the INEL`s waste streams and their potential treatment strategies.

1992-04-01T23:59:59.000Z

315

EA-1292: On-site Treatment of Low Level Mixed Waste, Golden, Colorado  

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

This EA evaluates the environmental impacts for the proposal to evaluate the proposed treatment of low level mixed waste at the U.S. Department of Energy's Rocky Flats Environmental Technology Site.

316

Independent Activity Report, Office of River Protection Waste Treatment Plant and Tank Farms- February 2013  

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

Site Familiarization and Introduction of New Office of Safety and Emergency Management Evaluations Site Lead for the Office of River Protection Waste Treatment Plant and Tank Farms [HIAR-HANFORD-2013-02-25

317

GRR/Section 18-HI-b - RCRA - Hazardous Waste Treatment, Storage...  

Open Energy Info (EERE)

8-HI-b - RCRA - Hazardous Waste Treatment, Storage, and Disposal Permit (TSD) < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help...

318

DOE names Bechtel BWXT Idaho and the Advanced Mixed Waste Treatment...  

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

names Bechtel BWXT Idaho and the Advanced Mixed Waste Treatment Project as a VPP Star Site Rick Provencher of DOE-ID, Jeff Mousseau of BBWI and co-safety chairs Tracy Anderson and...

319

Department of Energy treatment capabilities for greater-than-Class C low-level radioactive waste  

SciTech Connect

This report provides brief profiles for 26 low-level and high-level waste treatment capabilities available at the Idaho National Engineering Laboratory (INEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Pacific Northwest Laboratory (PNL), Rocky Flats Plant (RFP), Savannah River Site (SRS), and West Valley Demonstration Plant (WVDP). Six of the treatments have potential use for greater-than-Class C low-level waste (GTCC LLW). They include: (a) the glass ceramic process and (b) the Waste Experimental Reduction Facility incinerator at INEL; (c) the Super Compaction and Repackaging Facility and (d) microwave melting solidification at RFP; (e) the vitrification plant at SRS; and (f) the vitrification plant at WVDP. No individual treatment has the capability to treat all GTCC LLW streams. It is recommended that complete physical and chemical characterizations be performed for each GTCC waste stream, to permit using multiple treatments for GTCC LLW.

Morrell, D.K.; Fischer, D.K.

1995-01-01T23:59:59.000Z

320

Biological treatment of concentrated hazardous, toxic, andradionuclide mixed wastes without dilution  

DOE Green Energy (OSTI)

Approximately 10 percent of all radioactive wastes produced in the U. S. are mixed with hazardous or toxic chemicals and therefore can not be placed in secure land disposal facilities. Mixed wastes containing hazardous organic chemicals are often incinerated, but volatile radioactive elements are released directly into the biosphere. Some mixed wastes do not currently have any identified disposal option and are stored locally awaiting new developments. Biological treatment has been proposed as a potentially safer alternative to incineration for the treatment of hazardous organic mixed wastes, since biological treatment would not release volatile radioisotopes and the residual low-level radioactive waste would no longer be restricted from land disposal. Prior studies have shown that toxicity associated with acetonitrile is a significant limiting factor for the application of biotreatment to mixed wastes and excessive dilution was required to avoid inhibition of biological treatment. In this study, we demonstrate that a novel reactor configuration, where the concentrated toxic waste is drip-fed into a complete-mix bioreactor containing a pre-concentrated active microbial population, can be used to treat a surrogate acetonitrile mixed waste stream without excessive dilution. Using a drip-feed bioreactor, we were able to treat a 90,000 mg/L acetonitrile solution to less than 0.1 mg/L final concentration using a dilution factor of only 3.4. It was determined that the acetonitrile degradation reaction was inhibited at a pH above 7.2 and that the reactor could be modeled using conventional kinetic and mass balance approaches. Using a drip-feed reactor configuration addresses a major limiting factor (toxic inhibition) for the biological treatment of toxic, hazardous, or radioactive mixed wastes and suggests that drip-feed bioreactors could be used to treat other concentrated toxic waste streams, such as chemical warfare materiel.

Stringfellow, William T.; Komada, Tatsuyuki; Chang, Li-Yang

2004-06-15T23:59:59.000Z

Note: This page contains sample records for the topic "bearing waste treatment" 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

Review of the Hanford Site Waste Treatment and Immobilization...  

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

U.S. Department of Energy DOE-WTP ORP WTP Project Office HLW High-Level Waste Facility HVAC Heating, Ventilation, and Air Conditioning LAB Analytical Laboratory LAW Low-Activity...

322

A Database for Reviewing and Selecting Radioactive Waste Treatment Technologies and Vendors  

Science Conference Proceedings (OSTI)

Several attempts have been made in past years to collate and present waste management technologies and solutions to waste generators. These efforts have been manifested as reports, buyers' guides, and databases. While this information is helpful at the time it is assembled, the principal weakness is maintaining the timeliness and accuracy of the information over time. In many cases, updates have to be published or developed as soon as the product is disseminated. The recently developed National Low-Level Waste Management Program's Technologies Database is a vendor-updated Internet based database designed to overcome this problem. The National Low-Level Waste Management Program's Technologies Database contains information about waste types, treatment technologies, and vendor information. Information is presented about waste types, typical treatments, and the vendors who provide those treatment methods. The vendors who provide services update their own contact information, their treatment processes, and the types of wastes for which their treatment process is applicable. This information is queriable by a generator of low-level or mixed low-level radioactive waste who is seeking information on waste treatment methods and the vendors who provide them. Timeliness of the information in the database is assured using time clocks and automated messaging to remind featured vendors to keep their information current. Failure to keep the entries current results in a vendor being warned and then ultimately dropped from the database. This assures that the user is dealing with the most current information available and the vendors who are active in reaching and serving their market.

P. C. Marushia; W. E. Schwinkendorf

1999-07-01T23:59:59.000Z

323

MWIP: Surrogate formulations for thermal treatment of low-level mixed waste. Part 4, Wastewater treatment sludges  

Science Conference Proceedings (OSTI)

The category of sludges, filter cakes, and other waste processing residuals represent the largest volume of low-level mixed (hazardous and radioactive) wastes within the US Department of Energy (DOE) complex. Treatment of these wastes to minimize the mobility of contaminants, and to eliminate the presence of free water, is required under the Federal Facility Compliance Act agreements between DOE and the Environmental Protection Agency. In the text, we summarize the currently available data for several of the high priority mixed-waste sludge inventories within DOE. Los Alamos National Laboratory TA-50 Sludge and Rocky Flats Plant By-Pass Sludge are transuranic (TRU)-contaminated sludges that were isolated with the use of silica-based filter aids. The Oak Ridge Y-12 Plant West End Treatment Facility Sludge is predominantly calcium carbonate and biomass. The Oak Ridge K-25 Site Pond Waste is a large-volume waste stream, containing clay, silt, and other debris in addition to precipitated metal hydroxides. We formulate ``simulants`` for the waste streams described above, using cerium oxide as a surrogate for the uranium or plutonium present in the authentic material. Use of nonradiological surrogates greatly simplifies material handling requirements for initial treatability studies. The use of synthetic mixtures for initial treatability testing will facilitate compositional variation for use in conjunction with statistical design experiments; this approach may help to identify any ``operating window`` limitations. The initial treatability testing demonstrations utilizing these ``simulants`` will be based upon vitrification, although the materials are also amenable to testing grout-based and other stabilization procedures. After the feasibility of treatment and the initial evaluation of treatment performance has been demonstrated, performance must be verified using authentic samples of the candidate waste stream.

Bostick, W.D.; Hoffmann, D.P.; Stevenson, R.J.; Richmond, A.A. [Oak Ridge National Lab., TN (United States); Bickford, D.F. [Westinghouse Savannah River Co., Aiken, SC (United States)

1994-01-01T23:59:59.000Z

324

Summary - System Planning for Low-Activity Waste Treatment at Hanford  

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

Hanford Hanford EM Project: WTP ETR Report Date: November 2008 ETR-18 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of System Planning for Low-Activity Waste Treatment at Hanford Why DOE-EM Did This Review Construction of the facilities of the Hanford site's Waste Treatment Plant (WTP) are scheduled for completion in 2017, with radioactive waste processing scheduled to begin in 2019. An estimated 23 to 35 years will then be required to complete high-level waste (HLW) vitrification. However, vitrification of low-activity waste (LAW) may extend the WTP mission duration by decades more if supplemental LAW processing beyond the capacity of the present facility is not incorporated. The purpose of this independent review was to

325

The Radioactive Liquid Waste Treatment Facility Replacement Project at Los Alamos National Laboratory  

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

Radioactive Liquid Waste Radioactive Liquid Waste Treatment Facility Replacement Project at Los Alamos National Laboratory OAS-L-13-15 September 2013 Department of Energy Washington, DC 20585 September 26, 2013 MEMORANDUM FOR THE ASSOCIATE ADMINISTRATOR FOR ACQUISITION AND PROJECT MANAGEMENT MANAGER LOS ALAMOS FIELD OFFICE FROM: David Sedillo Western Audits Division Office of Inspector General SUBJECT: INFORMATION: Audit Report on "The Radioactive Liquid Waste Treatment Facility Replacement Project at Los Alamos National Laboratory" BACKGROUND The Department of Energy's Los Alamos National Laboratory (Los Alamos) is a Government- owned, contractor operated Laboratory that is part of the National Nuclear Security Administration's (NNSA) nuclear weapons complex. Los Alamos' primary responsibility is to

326

Sanitary Waste Water Treatment System for the Hanford Decontamination Laundry Facility  

SciTech Connect

This is an engineering report for the Decontamination Laundry Facility (DLF) which will be located in the 200 East Area of the Hanford Site. The proposed Sanitary Waste Treatment System is new and does not involve interfacing with existing sanitary waste treatment systems. It will utilize a subsurface soil absorption system (SSAS), which are frequently used to dispose of sanitary waste water from facilities at the Hanford Site, since a majority of its` facilities are located in remote areas. Construction of the DLF is scheduled to start in 1992 and startup of the DLF is planned during the summer of 1994.

Yanochko, R.M.

1992-09-01T23:59:59.000Z

327

Sanitary Waste Water Treatment System for the Hanford Decontamination Laundry Facility  

SciTech Connect

This is an engineering report for the Decontamination Laundry Facility (DLF) which will be located in the 200 East Area of the Hanford Site. The proposed Sanitary Waste Treatment System is new and does not involve interfacing with existing sanitary waste treatment systems. It will utilize a subsurface soil absorption system (SSAS), which are frequently used to dispose of sanitary waste water from facilities at the Hanford Site, since a majority of its' facilities are located in remote areas. Construction of the DLF is scheduled to start in 1992 and startup of the DLF is planned during the summer of 1994.

Yanochko, R.M.

1992-09-01T23:59:59.000Z

328

Development and demonstration of treatment technologies for the processing of US Department of Energy mixed waste  

SciTech Connect

Mixed waste is defined as waste contaminated with chemically hazardous (governed by the Resource Conservation and Recovery Act) and radioactive species [governed by US Department of Energy (DOE) orders]. The Mixed Waste Integrated Program (MWIP) is responding to the need for DOE mixed waste treatment technologies that meet these dual regulatory requirements. MWIP is developing emerging and innovative treatment technologies to determine process feasibility. Technology demonstrations will be used to determine whether processes are superior to existing technologies in reducing risk, minimizing life-cycle cost, and improving process performance. The Program also provides a forum for stakeholder and customer involvement in the technology development process. MWIP is composed of six technical areas that support a mixed-waste treatment system: (1) systems analysis, (2) materials handling, (3) chemical/physical separation, (4) waste destruction and stabilization, (5) off-gas treatment, and (6) final waste form stabilization. The status of the technical initiatives and the current research, development, and demonstration in each of these areas is described in this paper.

Berry, J.B.; Bloom, G.A. [Oak Ridge National Lab., TN (United States); Kuchynka, D.J. [Science Applications International Corp., Gaithersburg, MD (United States)

1994-06-01T23:59:59.000Z

329

Geology of the Waste Treatment Plant Seismic Boreholes  

Science Conference Proceedings (OSTI)

In 2006, the U.S. Department of Energy initiated the Seismic Boreholes Project (SBP) to emplace boreholes at the Waste Treatment Plant (WTP) site in order to obtain direct shear wave velocity (Vs) measurements and other physical property measurements in Columbia River basalt and interbedded sediments of the Ellensburg Formation. The goal was to reduce the uncertainty in the response spectra and seismic design basis, and potentially recover design margin for the WTP. The characterization effort within the deep boreholes included 1) downhole measurements of the velocity properties of the suprabasalt, basalt, and sedimentary interbed sequences, 2) downhole measurements of the density of the subsurface basalt and sediments, and 3) geologic studies to confirm the geometry of the contact between the various basalt and interbedded sediments through examination of retrieved core from the core hole and data collected through geophysical logging of each borehole. This report describes the results of the geologic studies from three mud-rotary boreholes and one cored borehole at the WTP. All four boreholes penetrated the entire Saddle Mountains Basalt and the upper part of the Wanapum Basalt where thick sedimentary interbeds occur between the lava flows. The basalt flows penetrated in Saddle Mountains Basalt included the Umatilla Member, Esquatzel Member, Pomona Member, and the Elephant Mountain Member. The underlying Priest Rapids Member of the Wanapum Basalt also was penetrated. The Ellensburg Formation sediments consist of the Mabton Interbed, the Cold Creek Interbed, the Selah Interbed, and the Rattlesnake Ridge Interbed; the Byron Interbed occurs between two flows of the Priest Rapids Member. The Mabton Interbed marks the contact between the Wanapum and Saddle Mountains Basalts. The thicknesses of the basalts and interbedded sediments were within expected limits. However, a small reverse fault was found in the Pomona Member flow top. This fault has three periods of movement and less than 15 ft of repeated section. Most of the movement on the fault appears to have occurred before the youngest lava flow, the 10.5-million-year-old Elephant Mountain Member, was emplaced above the Pomona Member.

Barnett, D. Brent; Fecht, Karl R.; Reidel, Stephen P.; Bjornstad, Bruce N.; Lanigan, David C.; Rust, Colleen F.

2007-05-11T23:59:59.000Z

330

DNFSB Recommendation 2010-2, Pulse Jet Mixing at the Waste Treatment and Immobilization Plant WTP  

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

DNFSB Rec. 2010-2, Rev.0, Nov.10, 2011 DNFSB Rec. 2010-2, Rev.0, Nov.10, 2011 i Department of Energy Plan to Address Waste Treatment and Immobilization Plant Vessel Mixing Issues Revision 0 Implementation Plan for Defense Nuclear Safety Board Recommendation 2010-2 November 10, 2011 DNFSB Rec. 2010-2, Rev.0, Nov.10, 2011 ii EXECUTIVE SUMMARY On December 17, 2010, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 2010-2, Pulse Jet Mixing at the Waste Treatment and Immobilization Plant. The recommendation addressed the need for the U.S. Department of Energy (DOE) to ensure that the Hanford Waste Treatment and Immobilization Plant (WTP), in conjunction with the Hanford tank farm waste feed delivery system, will operate safely and effectively during a

331

Idaho's Advanced Mixed Waste Treatment Project Details 2013Accomplish...  

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

Treatment Project Details 2013 Accomplishments December 24, 2013 - 12:00pm Addthis IDAHO FALLS, Idaho - EM and its contractor, Idaho Treatment Group (ITG), safely and...

332

Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility  

Science Conference Proceedings (OSTI)

The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993.

Not Available

1993-08-01T23:59:59.000Z

333

Treatment plan for aqueous/organic/decontamination wastes under the Oak Ridge Reservation FFCA Development, Demonstration, Testing, and Evaluation Program  

SciTech Connect

The U.S. Department of Energy (DOE) Oak Ridge Operations Office and the U.S. Environmental Protection Agency (EPA)-Region IV have entered into a Federal Facility Compliance Agreement (FFCA) which seeks to facilitate the treatment of low-level mixed wastes currently stored at the Oak Ridge Reservation (ORR) in violation of the Resource, Conservation and Recovery Act Land Disposal Restrictions. The FFCA establishes schedules for DOE to identify treatment for wastes, referred to as Appendix B wastes, that current have no identified or existing capacity for treatment. A development, demonstration, testing, and evaluation (DDT&E) program was established to provide the support necessary to identify treatment methods for mixed was meeting the Appendix B criteria. The Program has assembled project teams to address treatment development needs for major categories of the Appendix B wastes based on the waste characteristics and possible treatment technologies. The Aqueous, Organic, and Decontamination (A/O/D) project team was established to identify pretreatment options for aqueous and organic wastes which will render the waste acceptable for treatment in existing waste treatment facilities and to identify the processes to decontaminate heterogeneous debris waste. In addition, the project must also address the treatment of secondary waste generated by other DDT&E projects. This report details the activities to be performed under the A/O/D Project in support of the identification, selection, and evaluation of treatment processes. The goals of this plan are (1) to determine the major aqueous and organic waste streams requiring treatment, (2) to determine the treatment steps necessary to make the aqueous and organic waste acceptable for treatment in existing treatment facilities on the ORR or off-site, and (3) to determine the processes necessary to decontaminate heterogeneous wastes that are considered debris.

Backus, P.M.; Benson, C.E.; Gilbert, V.P.

1994-08-01T23:59:59.000Z

334

Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting  

SciTech Connect

The Idaho National Engineering Laboratory Advanced Mixed Waste Treatment Project sponsored a plasma are melter technical design review meeting to evaluate high-temperature melter system configurations for processing heterogeneous alpha-contaminated low-level radioactive waste (ALLW). Thermal processing experts representing Department of Energy contractors, the Environmental Protection Agency, and private sector companies participated in the review. The participants discussed issues and evaluated alternative configurations for three areas of the melter system design: plasma torch melters and graphite arc melters, offgas treatment options, and overall system configuration considerations. The Technical Advisory Committee for the review concluded that graphite arc melters are preferred over plasma torch melters for processing ALLW. Initiating involvement of stakeholders was considered essential at this stage of the design. For the offgas treatment system, the advisory committee raised the question whether to a use wet-dry or a dry-wet system. The committee recommended that the waste stream characterization, feed preparation, and the control system are essential design tasks for the high-temperature melter treatment system. The participants strongly recommended that a complete melter treatment system be assembled to conduct tests with nonradioactive surrogate waste material. A nonradioactive test bed would allow for inexpensive design and operational changes prior to assembling a system for radioactive waste treatment operations.

Eddy, T.L.; Raivo, B.D.; Soelberg, N.R.; Wiersholm, O.

1995-02-01T23:59:59.000Z

335

Integrated demonstration of molten salt oxidation with salt recycle for mixed waste treatment  

Science Conference Proceedings (OSTI)

Molten Salt Oxidation (MSO) is a thermal, nonflame process that has the inherent capability of completely destroying organic constituents of mixed wastes, hazardous wastes, and energetic materials while retaining inorganic and radioactive constituents in the salt. For this reason, MSO is considered a promising alternative to incineration for the treatment of a variety of organic wastes. Lawrence Livermore National Laboratory (LLNL) has prepared a facility and constructed an integrated pilot-scale MSO treatment system in which tests and demonstrations are performed under carefully controlled (experimental) conditions. The system consists of a MSO processor with dedicated off-gas treatment, a salt recycle system, feed preparation equipment, and equipment for preparing ceramic final waste forms. This integrated system was designed and engineered based on laboratory experience with a smaller engineering-scale reactor unit and extensive laboratory development on salt recycle and final forms preparation. In this paper we present design and engineering details of the system and discuss its capabilities as well as preliminary process demonstration data. A primary purpose of these demonstrations is identification of the most suitable waste streams and waste types for MSO treatment.

Hsu, P.C.

1997-11-01T23:59:59.000Z

336

Activated carbon: Utilization excluding industrial waste treatment. (Latest citations from the Compendex database). Published Search  

SciTech Connect

The bibliography contains citations concerning the commercial use and theoretical studies of activated carbon. Topics include performance evaluations in water treatment processes, preparation and regeneration techniques, materials recovery, and pore structure studies. Adsorption characteristics for specific materials are discussed. Studies pertaining specifically to industrial waste treatment are excluded. (Contains 250 citations and includes a subject term index and title list.)

Not Available

1993-06-01T23:59:59.000Z

337

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

SciTech Connect

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

Grutzeck, Michael W.

2005-06-27T23:59:59.000Z

338

High Level Waste Remote Handling Equipment in the Melter Cave Support Handling System at the Hanford Waste Treatment Plant  

SciTech Connect

Cold war plutonium production led to extensive amounts of radioactive waste stored in tanks at the Department of Energy's (DOE) Hanford site. Bechtel National, Inc. is building the largest nuclear Waste Treatment Plant in the world located at the Department of Energy's Hanford site to immobilize the millions of gallons of radioactive waste. The site comprises five main facilities; Pretreatment, High Level Waste vitrification, Low Active Waste vitrification, an Analytical Lab and the Balance of Facilities. The pretreatment facilities will separate the high and low level waste. The high level waste will then proceed to the HLW facility for vitrification. Vitrification is a process of utilizing a melter to mix molten glass with radioactive waste to form a stable product for storage. The melter cave is designated as the High Level Waste Melter Cave Support Handling System (HSH). There are several key processes that occur in the HSH cell that are necessary for vitrification and include: feed preparation, mixing, pouring, cooling and all maintenance and repair of the process equipment. Due to the cell's high level radiation, remote handling equipment provided by PaR Systems, Inc. is required to install and remove all equipment in the HSH cell. The remote handling crane is composed of a bridge and trolley. The trolley supports a telescoping tube set that rigidly deploys a TR 4350 manipulator arm with seven degrees of freedom. A rotating, extending, and retracting slewing hoist is mounted to the bottom of the trolley and is centered about the telescoping tube set. Both the manipulator and slewer are unique to this cell. The slewer can reach into corners and the manipulator's cross pivoting wrist provides better operational dexterity and camera viewing angles at the end of the arm. Since the crane functions will be operated remotely, the entire cell and crane have been modeled with 3-D software. Model simulations have been used to confirm operational and maintenance functional and timing studies throughout the design process. Since no humans can go in or out of the cell, there are several recovery options that have been designed into the system including jack-down wheels for the bridge and trolley, recovery drums for the manipulator hoist, and a wire rope cable cutter for the slewer jib hoist. If the entire crane fails in cell, the large diameter cable reel that provides power, signal, and control to the crane can be used to retrieve the crane from the cell into the crane maintenance area. (authors)

Bardal, M.A. [PaR Systems, Inc., Shoreview, MN (United States); Darwen, N.J. [Bechtel National, Inc., Richland, WA (United States)

2008-07-01T23:59:59.000Z

339

Development of a Waste Treatment Process to Deactivate Reactive Uranium Metal and Produce a Stable Waste Form  

SciTech Connect

This paper highlights the results of initial investigations conducted to support the development of an integrated treatment process to convert pyrophoric metallic uranium wastes to a non-pyrophoric waste that is acceptable for land disposal. Several dissolution systems were evaluated to determine their suitability to dissolve uranium metal and that yield a final waste form containing uranium specie(s) amenable to precipitation, stabilization, adsorption, or ion exchange. During initial studies, one gram aliquots of uranium metal or the uranium alloy U-2%Mo were treated with 5 to 60 mL of selected reagents. Treatment systems screened included acids, acid mixtures, and bases with and without addition of oxidants. Reagents used included hydrochloric, sulfuric, nitric, and phosphoric acids, sodium hypochlorite, sodium hydroxide and hydrogen peroxide. Complete dissolution of the uranium turnings was achieved with the H{sub 3}PO{sub 4}/HCI system at room temperature within minutes. The sodium hydroxide/hydrogen peroxide, and sodium hypochlorite systems achieved complete dissolution but required elevated temperatures and longer reaction times. A ranking system based on criteria, such as corrosiveness, temperature, dissolution time, off-gas type and amount, and liquid to solid ratio, was designed to determine the treatment systems that should be developed further for a full-scale process. The highest-ranking systems, nitric acid/sulfuric acid and hydrochloric acid/phosphoric acid, were given priority in our follow-on investigations.

Gates-Anderson, D D; Laue, C A; Fitch, T E

2002-01-17T23:59:59.000Z

340

Advanced Mixed Waste Treatment Project, Design, Construction and Start-up  

Science Conference Proceedings (OSTI)

The Advanced Mixed Waste Treatment Project (AMWTP) was awarded to BNG America in December of 1996. In 2005, following discussions between the United States (US) Department of Energy (DOE) and the United Kingdom (UK) Department of Trade and Industry (DTi) the DOE purchased the facilities. DOE awarded Bechtel B and W Idaho (BBWI) a contract to operate the facilities for one year, commencing 1 May 2005. The hand-over of AMWTP included the facility to repackage and super-compact waste (Advanced Mixed Waste Treatment Facility) and the retrieval, characterization, storage and Transuranic Package Transporter (TRUPACT) loading facility. This poster updates the progress of AMWTP from the previous presentations to Waste Management (WM) [1 and 2] to completion of the transition to BBWI in May 2005. (authors)

Dobson, A. [BNG America, 2345 Stevens Drive Suite no. 240, Richland, WA 99354 (United States); Harrop, G.; Holmes, R.G.G. [BNG America, 1920 E. 17th Street Suite no. 200, Idaho Falls, ID 83404 (United States)

2006-07-01T23:59:59.000Z

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341

Oak Ridge National Lebroatory Liquid&Gaseous Waste Treatment System Strategic Plan  

SciTech Connect

Excellence in Laboratory operations is one of the three key goals of the Oak Ridge National Laboratory (ORNL) Agenda. That goal will be met through comprehensive upgrades of facilities and operational approaches over the next few years. Many of ORNL's physical facilities, including the liquid and gaseous waste collection and treatment systems, are quite old, and are reaching the end of their safe operating life. The condition of research facilities and supporting infrastructure, including the waste handling facilities, is a key environmental, safety and health (ES&H) concern. The existing infrastructure will add considerably to the overhead costs of research due to increased maintenance and operating costs as these facilities continue to age. The Liquid Gaseous Waste Treatment System (LGWTS) Reengineering Project is a UT-Battelle, LLC (UT-B) Operations Improvement Program (OIP) project that was undertaken to develop a plan for upgrading the ORNL liquid and gaseous waste systems to support ORNL's research mission.

Van Hoesen, S.D.

2003-09-09T23:59:59.000Z

342

INITIAL SELECTION OF SUPPLEMENTAL TREATMENT TECHNOLOGIES FOR HANFORDS LOW ACTIVITY TANK WASTE  

SciTech Connect

In 2002, the U.S. Department of Energy (DOE) documented a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years. A key element of the plan was acceleration of the tank waste program and completion of ''tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (WTP) and using supplemental technologies for waste treatment and immobilization.'' The plan identified specific technologies to be evaluated for supplemental treatment of as much as 70% of the low-activity waste (LAW). In concert with this acceleration plan, DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology proposed to accelerate--from 2014 to 2006--the Hanford Federal Facility Agreement and Consent Order milestone (M-62-11) associated with a final decision on the balance of tank waste that is beyond the capacity of the WTP. The DOE Office of River Protection tank farm contractor, CH2M HILL Hanford Group, Inc. (CH2M HILL), was tasked with testing and evaluating selected supplemental technologies to support final decisions on tank waste treatment. Three technologies and corresponding vendors were selected to support an initial technology selection in 2003. The three technologies were containerized grout called cast stone (Fluor Federal Services); bulk vitrification (AMEC Earth and Environmental, Inc.); and steam reforming (THOR Treatment Technologies, LLC.). The cast stone process applies an effective grout waste formulation to the LAW and places the cement-based product in a large container for solidification and disposal. Unlike the WTP LAW treatment, which applies vitrification within continuous-fed joule-heated ceramic melters, bulk vitrification produces a glass waste form using batch melting within the disposal container. Steam reforming produces a granular denitrified mineral waste form using a high-temperature fluidized bed process. An initial supplemental technology selection was completed in December 2003, enabling DOE and CH2M HILL to focus investments in 2004 on the testing and production-scale demonstrations needed to support the 2006 milestone.

RAYMOND, R.E.

2004-02-20T23:59:59.000Z

343

TREATMENT OF METAL-LADEN HAZARDOUS WASTES WITH ADVANCED CLEAN COAL TECHNOLOGY BY-PRODUCTS  

Science Conference Proceedings (OSTI)

Metal-laden wastes can be stabilized and solidified using advanced clean coal technology by-products (CCTBs)--fluid bed combustor ash and spray drier solids. These utility-generated treatment chemicals are available for purchase through brokers, and commercial applications of this process are being practiced by treaters of metal-laden hazardous waste. A complex of regulations governs this industry, and sensitivities to this complex has discouraged public documentation of treatment of metal-laden hazardous wastes with CCTBs. This report provides a comprehensive public documentation of laboratory studies that show the efficacy of the stabilization and solidification of metal-laden hazardous wastes--such as lead-contaminated soils and sandblast residues--through treatment with CCTBs. It then describes the extensive efforts that were made to obtain the permits allowing a commercial hazardous waste treater to utilize CCTBs as treatment chemicals and to install the equipment required to do so. It concludes with the effect of this lengthy process on the ability of the treatment company to realize the practical, physical outcome of this effort, leading to premature termination of the project.

James T. Cobb, Jr.

2003-09-12T23:59:59.000Z

344

Integrated process analysis of treatment systems for mixed low level waste  

SciTech Connect

Selection of technologies to be developed for treatment of DOE`s mixed low level waste (MLLW) requires knowledge and understanding of the expected costs, schedules, risks, performance, and reliability of the total engineered systems that use these technologies. Thus, an integrated process analysis program was undertaken to identify the characteristics and needs of several thermal and nonthermal systems. For purposes of comparison, all systems were conceptually designed for a single facility processing the same amount of waste at the same rate. Thirty treatment systems were evaluated ranging from standard incineration to innovative thermal systems and innovative nonthermal chemical treatment. Treating 236 million pounds of waste in 20 years through a central treatment was found to be the least costly option with total life cycle cost ranging from $2.1 billion for a metal melting system to $3.9 billion for a nonthermal acid digestion system. Little cost difference exists among nonthermal systems or among thermal systems. Significant cost savings could be achieved by working towards maximum on line treatment time per year; vitrifying the final waste residue; decreasing front end characterization segregation and sizing requirements; using contaminated soil as the vitrifying agent; and delisting the final vitrified waste form from Resource Conservation and Recovery Act (RCRA) Land Disposal Restriction (LDR) requirements.

Cooley, C.R. [Dept. of Energy, Washington, DC (United States); Schwinkendorf, W.E. [Lockheed Martin Idaho Technology Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.]|[Sandia National Labs., Albuquerque, NM (United States); Bechtold, T.E. [Lockheed Martin Idaho Technology Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.

1997-10-01T23:59:59.000Z

345

Progress and Lessons Learned in Transuranic Waste Disposition at The Department of Energy's Advanced Mixed Waste Treatment Project  

SciTech Connect

This paper provides an overview of the Department of Energy's (DOE) Advanced Mixed Waste Treatment Project (AMWTP) located at the Idaho National Laboratory (INL) and operated by Bechtel BWXT Idaho, LLC(BBWI) It describes the results to date in meeting the 6,000-cubic-meter Idaho Settlement Agreement milestone that was due December 31, 2005. The paper further describes lessons that have been learned from the project in the area of transuranic (TRU) waste processing and waste certification. Information contained within this paper would be beneficial to others who manage TRU waste for disposal at the Waste Isolation Pilot Plant (WIPP).

J.D. Mousseau; S.C. Raish; F.M. Russo

2006-05-18T23:59:59.000Z

346

Environmental assessment for the Waste Water Treatment Facility at the West Valley Demonstration Project and finding of no significant impact  

SciTech Connect

The possible environmental impacts from the construction and operation of a waste water treatment facility for the West Valley Demonstration Project are presented. The West Valley Project is a demonstration project on the solidification of high-level radioactive wastes. The need for the facility is the result of a rise in the work force needed for the project which rendered the existing sewage treatment plant incapable of meeting the nonradioactive waste water treatment needs.

1992-12-31T23:59:59.000Z

347

The Treatment of Mixed Waste with GeoMelt In-Container Vitrification  

SciTech Connect

AMEC's GeoMelt{sup R} In-Container Vitrification (ICV){sup TM} has been used to treat diverse types of mixed low-level radioactive waste. ICV is effective in the treatment of mixed wastes containing polychlorinated biphenyls (PCBs) and other semi-volatile organic compounds, volatile organic compounds (VOCs) and heavy metals. The GeoMelt vitrification process destroys organic compounds and immobilizes metals and radionuclides in an extremely durable glass waste form. The process is flexible allowing for treatment of aqueous, oily, and solid mixed waste, including contaminated soil. In 2004, ICV was used to treat mixed radioactive waste sludge containing PCBs generated from a commercial cleanup project regulated by the Toxic Substances Control Act (TSCA), and to treat contaminated soil from Rocky Flats Environmental Technology Site. The Rocky Flats soil contained cadmium, PCBs, and depleted uranium. In 2005, AMEC completed a treatability demonstration of the ICV technology on Mock High Explosive from Sandia National Laboratories. This paper summarizes results from these mixed waste treatment projects. (authors)

Finucane, K.G.; Campbell, B.E. [AMEC Earth and Environmental, Inc., 1135 Jadwin Avenue, Richland, Washington 99352 (United States)

2006-07-01T23:59:59.000Z

348

Characterizing the transformation and transfer of nitrogen during the aerobic treatment of organic wastes and digestates  

Science Conference Proceedings (OSTI)

Highlights: Black-Right-Pointing-Pointer Ammonia emissions varied depending on the nature of wastes and the treatment conditions. Black-Right-Pointing-Pointer Nitrogen losses resulted from ammonia emissions and nitrification-denitrification. Black-Right-Pointing-Pointer Ammonification can be estimated from biodegradable carbon and carbon/nitrogen ratio. Black-Right-Pointing-Pointer Ammonification was the main process contributing to N losses. Black-Right-Pointing-Pointer Nitrification rate was negatively correlated to stripping rate of ammonia nitrogen. - Abstract: The transformation and transfer of nitrogen during the aerobic treatment of seven wastes were studied in ventilated air-tight 10-L reactors at 35 Degree-Sign C. Studied wastes included distinct types of organic wastes and their digestates. Ammonia emissions varied depending on the kind of waste and treatment conditions. These emissions accounted for 2-43% of the initial nitrogen. Total nitrogen losses, which resulted mainly from ammonia emissions and nitrification-denitrification, accounted for 1-76% of the initial nitrogen. Ammonification was the main process responsible for nitrogen losses. An equation which allows estimating the ammonification flow of each type of waste according to its biodegradable carbon and carbon/nitrogen ratio was proposed. As a consequence of the lower contribution of storage and leachate rates, stripping and nitrification rates of ammonia nitrogen were negatively correlated. This observation suggests the possibility of promotingnitrification in order to reduce ammonia emissions.

Zeng Yang, E-mail: yang.zeng@irstea.fr [Irstea, UR GERE, 17 avenue de Cucille, CS 64427, F-35044 Rennes Cedex (France); Universite Europeenne de Bretagne, F-35000 Rennes (France); Guardia, Amaury de; Daumoin, Mylene; Benoist, Jean-Claude [Irstea, UR GERE, 17 avenue de Cucille, CS 64427, F-35044 Rennes Cedex (France)

2012-12-15T23:59:59.000Z

349

Mixed-waste treatment -- What about the residuals? A comparative analysis of MSO and incineration  

SciTech Connect

This report examines the issues concerning final waste forms, or residuals, that result from the treatment of mixed waste in molten salt oxidation (MSO) and incinerator systems. MSO is a technology with the potential to treat a certain segment of the waste streams at US Department of Energy (DOE) sites. MSO was compared with incineration because incineration is the best demonstrated available technology (BDAT) for the same waste streams. The Grand Junction Projects Office (GJPO) and Oak Ridge National Laboratory (ORNL) prepared this report for the DOE Office of Environmental Restoration (OER). The goals of this study are to objectively evaluate the anticipated residuals from MSO and incineration, examine regulatory issues for these final waste forms, and determine secondary treatment options. This report, developed to address concerns that MSO residuals present unique disposal difficulties, is part of a larger effort to successfully implement MSO as a treatment technology for mixed and hazardous waste. A Peer Review Panel reviewed the MSO technology in November 1991, and the implementation effort is ongoing under the guidance of the MSO Task Force.

NONE

1993-06-01T23:59:59.000Z

350

Automated Sampling and Sample Pneumatic Transport of High Level Tank Wastes at the Hanford Waste Treatment Plant  

Science Conference Proceedings (OSTI)

This paper describes the development work, and design and engineering tasks performed, to provide a fully automated sampling system for the Waste Treatment Plant (WTP) project at the Hanford Site in southeastern Washington State, USA. WTP is being built to enable the emptying and immobilization of highly active waste resulting from processing of irradiated nuclear fuel since the 1940's. The Hanford Tank Wastes are separated into Highly Level Waste (HLW), and Low Active Waste (LAW) fractions, which are separately immobilized by vitrification into borosilicate glass. Liquid samples must be taken of the waste and Glass Forming Chemicals (GFCs) before vitrification, and analyzed to insure the glass products will comply with specifications established in the WTP contract. This paper describes the non-radioactive testing of the sampling of the HLW and LAW melter feed simulants that was performed ahead of final equipment design. These trials were essential to demonstrate the effectiveness and repeatability of the integrated sampling system to collect representative samples, free of cross-contamination. Based on existing tried and proven equipment, the system design is tailored to meet the WTP project's specific needs. The design provides sampling capabilities from 47 separate sampling points and includes a pneumatic transport system to move the samples from the 3 separate facilities to the centralized analytical laboratory. The physical and rheological compositions of the waste simulants provided additional challenges in terms of the sample delivery, homogenization, and sample capture equipment design requirements. The activity levels of the actual waste forms, specified as 486 E9 Bq/liter (Cs-137), 1.92 E9 Bq/liter (Co-60), and 9.67 E9 Bq/liter (Eu-154), influenced the degree of automation provided, and justified the minimization of manual intervention needed to obtain and deliver samples from the process facilities to the analytical laboratories. Maintaining high integrity primary and secondary confinement, including during the cross-site transportation of the samples, is a key requirement that is achieved and assured at all times. (authors)

Phillips, C.; Richardson, J. E. [BNG America, 2345 Stevens Drive, Richland, WA, 99354 (United States)

2006-07-01T23:59:59.000Z

351

The Department of Energy's $12.2 Billion Waste Treatment and Immobilization Plant - Quality Assurance Issues  

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

The Department of Energy's $12.2 Billion The Department of Energy's $12.2 Billion Waste Treatment and Immobilization Plant - Quality Assurance Issues - Black Cell Vessels DOE/IG-0863 April 2012 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 April 25, 2012 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report on "The Department of Energy's $12.2 Billion Waste Treatment and Immobilization Plant - Quality Assurance Issues - Black Cell Vessels" INTRODUCTION The Office of Inspector General received allegations concerning aspects of the quality assurance program at the Department of Energy's $12.2 billion Waste Treatment and Immobilization Plant

352

Constructed wetlands for municipal solid waste landfill leachate treatment. Final report  

SciTech Connect

In 1989, the US Geological Survey and Cornell University, in cooperation with the New York State Energy Research and Development Authority and the Tompkins County Solid Waste Department, began a three-year study at a municipal solid-waste landfill near Ithaca, New York, to test the effectiveness of leachate treatment with constructed wetlands and to examine the associated treatment processes. Specific objectives of the study were to examine: treatment efficiency as function of substrate composition and grain size, degree of plant growth, and seasonal changes in evapotranspiration rates and microbial activity; effects of leachate and plant growth on the hydraulic characteristics of the substrate; and chemical, biological, and physical processes by which nutrients, metals, and organic compounds are removed from leachate as it flows through the substrate. A parallel study at a municipal solid-waste landfill near Fenton, New York was conducted by researchers at Cornell University, Ithaca College, and Hawk Engineering (Trautmann and others, 1989). Results are described.

Peverly, J.; Sanford, W.E.; Steenhuis, T.S. [Cornell Univ., Ithaca, NY (United States)

1993-11-01T23:59:59.000Z

353

Membrane filtration waste treatment technology comes of age in battery manufacturing plants  

SciTech Connect

A new waste treatment system from MEMTEK Corporation incorporates membrane filtration, and makes possible the effective treatment of waste streams containing a number of toxic heavy metals. Using this membrane technology, MEMTEK is capable of treating the wastewater in battery manufacturing plants to meet even the strictest limits imposed by local regulatory agencies and the Environmental Protection Agency (EPA). Lead and zinc in the treated effluent are typically below 0.1 ppm. The typical battery manufacturing processes introduce metals, primarily lead, into plant effluents, especially from formation, battery wash, and laundry operation. Due to the high usage of acid in the plant, the wastewater is also usually of a low pH, typically 2 or less. The dissolved and particulate contaminants in this effluent must be removed to very low levels before the water can be released to the sewer or the environment. The waste treatment process is described.

1986-09-01T23:59:59.000Z

354

Ultrafiltration treatment for liquid laundry wastes from nuclear power stations  

SciTech Connect

The authors conduct a comprehensive analysis of the waste constituents--radioactive and organic--of the laundry water resulting from the on-site laundering and decontamination of clothing worn in nuclear power plants. The primary isotope contaminants consist of niobium and zirconium 95, manganese 54, cobalt 60, iron 59, and cesium 134 and 137. A variety of filter and adsorbent materials used in an ultrafiltration process are comparatively tested for their effectiveness in removing not only these isotopes but also the organic contaminants in the process of recycling the water. Those materials consist of copper hexacyanoferrate, polyacrylophosphonic acid, and several metal-polymer complexes.

Kichik, V.A.; Maslova, M.N.; Svittsov, A.A.; Kuleshov, N.F.

1988-03-01T23:59:59.000Z

355

CARBON BED MERCURY EMISSIONS CONTROL FOR MIXED WASTE TREATMENT  

Science Conference Proceedings (OSTI)

Mercury has had various uses in nuclear fuel reprocessing and other nuclear processes, and so is often present in radioactive and mixed (both radioactive and hazardous according tohe Resource Conservation and Recovery Act) wastes. Depending on regulatory requirements, the mercury in the off-gas must be controlled with sometimes very high efficiencies. Compliance to the Hazardous Waste Combustor (HWC) Maximum Achievable Control Technology (MACT) standards can require off-gas mercury removal efficiencies up to 99.999% for thermally treating some mixed waste streams. Several test programs have demonstrated this level of off-gas mercury control using fixed beds of granular sulfur-impregnated activated carbon. Other results of these tests include: (a) The depth of the mercury control mass transfer zone was less than 15-30 cm for the operating conditions of these tests, (b) MERSORB® carbon can sorb Hg up to 19 wt% of the carbon mass, and (c) the spent carbon retained almost all (98 – 99.99%) of the Hg; but when even a small fraction of the total Hg dissolves, the spent carbon can fail the TCLP test when the spent carbon contains high Hg concentrations. Localized areas in a carbon bed that become heated through heat of adsorption, to temperatures where oxidation occurs, are referred to as “bed hot spots.” Carbon bed hot spots must be avoided in processes that treat radioactive and mixed waste. Key to carbon bed hot spot mitigation are (a) designing for sufficient gas velocity, for avoiding gas flow maldistribution, and for sufficient but not excessive bed depth, (b) monitoring and control of inlet gas flowrate, temperature, and composition, (c) monitoring and control of in-bed and bed outlet gas temperatures, and (d) most important, monitoring of bed outlet CO concentrations. An increase of CO levels in the off-gas downstream of the carbon bed to levels about 50-100 ppm higher than the inlet CO concentration indicate CO formation in the bed, caused by carbon bed hot spots. Corrective actions must be implemented quickly if bed hot spots are detected, using a graded approach and sequence starting with corrective actions that are simple, quick, cause the least impact to the process, and are easiest to recover from. Multiple high and high-high alarm levels should be used, with appropriate corrective actions for each level.

Nick Soelberg; Joe Enneking

2010-11-01T23:59:59.000Z

356

Audit of the radioactive liquid waste treatment facility operations at the Los Alamos National Laboratory  

SciTech Connect

Los Alamos National Laboratory (Los Alamos) generates radioactive and liquid wastes that must be treated before being discharged to the environment. Presently, the liquid wastes are treated in the Radioactive Liquid Waste Treatment Facility (Treatment Facility), which is over 30 years old and in need of repair or replacement. However, there are various ways to satisfy the treatment need. The objective of the audit was to determine whether Los Alamos cost effectively managed its Treatment Facility operations. The audit determined that Los Alamos` treatment costs were significantly higher when compared to similar costs incurred by the private sector. This situation occurred because Los Alamos did not perform a complete analysis of privatization or prepare a {open_quotes}make-or-buy{close_quotes} plan for its treatment operations, although a {open_quotes}make-or-buy{close_quotes} plan requirement was incorporated into the contract in 1996. As a result, Los Alamos may be spending $2.15 million more than necessary each year and could needlessly spend $10.75 million over the next five years to treat its radioactive liquid waste. In addition, Los Alamos has proposed to spend $13 million for a new treatment facility that may not be needed if privatization proves to be a cost effective alternative. We recommended that the Manager, Albuquerque Operations Office (Albuquerque), (1) require Los Alamos to prepare a {open_quotes}make-or-buy{close_quotes} plan for its radioactive liquid waste treatment operations, (2) review the plan for approval, and (3) direct Los Alamos to select the most cost effective method of operations while also considering other factors such as mission support, reliability, and long-term program needs. Albuquerque concurred with the recommendations.

1997-11-19T23:59:59.000Z

357

Summary - Savannah River Site Tank 48H Waste Treatment Project  

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

S S Wet Air Savan contain liquid w contain potent to the option tank w Bed S condu be pur The as Techn Techn as liste * W o o The Ele Site: S roject: S P Report Date: J ited States Savanna Why DOE r Oxidation Proc nnah River Tan ning approxima waste. The wa ns tetraphenylb tially flammable tank head spa s have been id waste: Wet Air O team Reformin cted to aid in d rsued for treatin What th ssessment team ology Element ology Readine ed below: Wet Air Oxidatio Reactor sys Offgas Trea To view the full T http://www.em.doe. objective of a Tech ements (CTEs), usin Savannah Rive SRS Tank 48H Project July 2007 Departmen ah River E-EM Did This cess k 48H is a 1.3 ately 250, 000 aste is a salt so borate (TPB), w e concentration ce. Two poten dentified for this Oxidation (WAO ng (FBSR). Th deciding which ng the Tank 48

358

Comparison of costs for alternative mixed low-level waste treatment systems  

SciTech Connect

Total life cycle costs (TLCCs), including disposal costs, of thermal, nonthermal and enhanced nonthermal systems were evaluated to guide future research and development programs for the treatment of mixed low-level waste (MLLW) consisting of RCRA hazardous and low-level radioactive wastes. In these studies, nonthermal systems are defined as those systems that process waste at temperatures less than 350 C. Preconceptual designs and costs were developed for thirty systems with a capacity (2,927 lbs/hr) to treat the DOE MLLW stored inventor y(approximately 236 million pounds) in 20 years in a single, centralized facility. A limited comparison of the studies` results is presented in this paper. Sensitivity of treatment costs with respect to treatment capacity, number of treatment facilities, and system availability were also determined. The major cost element is operations and maintenance (O and M), which is 50 to 60% of the TLCC for both thermal and nonthermal systems. Energy costs constitute a small fraction (< 1%) of the TLCCs. Equipment cost is only 3 to 5% of the treatment cost. Evaluation of subsystem costs demonstrate that receiving and preparation is the highest cost subsystem at about 25 to 30% of the TLCC for both thermal and nonthermal systems. These studies found no cost incentives to use nonthermal or hybrid (combined nonthermal treatment with stabilization by vitrification) systems in place of thermal systems. However, there may be other incentives including fewer air emissions and less local objection to a treatment facility. Building multiple treatment facilities to treat the same total mass of waste as a single facility would increase the total treatment cost significantly, and improved system availability decreases unit treatment costs by 17% to 30%.

Schwinkendorf, W.E.; Harvego, L. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Cooley, C.R. [Dept. of Energy (United States); Biagi, C. [Morrison Knudsen (United States)

1996-12-31T23:59:59.000Z

359

Summary - Savannah River Site Tank 48H Waste Treatment Project  

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

Ta s Review million gal tank gal of high-lev olution that also which can relea ns of benzene v ntial treatment s organic-beari O) and Fluidize is assessment technology sho 8H...

360

Savannah River Site mixed waste Proposed Site Treatment Plan (PSTP). Volumes 1 and 2 and reference document: Revision 2  

SciTech Connect

The DOE is required by the Resource Conservation and Recovery Act to prepare site treatment plans describing the development of treatment capacities and technologies for treating mixed waste. This proposed plan contains Savannah River Site`s preferred options and schedules for constructing new facilities, and otherwise obtaining treatment for mixed wastes. The proposed plan consists of 2 volumes. Volume 1, Compliance Plan, identifies the capacity to be developed and the schedules as required. Volume 2, Background, provides a detailed discussion of the preferred options with technical basis, plus a description of the specific waste streams. Chapters are: Introduction; Methodology; Mixed low level waste streams; Mixed transuranic waste; High level waste; Future generation of mixed waste streams; Storage; Process for evaluation of disposal issues in support of the site treatment plans discussions; Treatment facilities and treatment technologies; Offsite waste streams for which SRS treatment is the Preferred Option (Naval reactor wastes); Summary information; and Acronyms and glossary. This revision does not contain the complete revised report, but only those pages that have been revised.

Helmich, E.; Noller, D.K.; Wierzbicki, K.S.; Bailey, L.L.

1995-07-13T23:59:59.000Z

Note: This page contains sample records for the topic "bearing waste treatment" 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

Conceptual Evaluation for the Installation of Treatment Capability for Mixed Low Level Waste at the Nevada National Security Site  

SciTech Connect

National Security Technologies, LLC, initiated an evaluation of treatment technologies that they would manage and operate as part of the mixed low-level waste (MLLW) disposal facilities at the Nevada National Security Site (NNSS). The NNSS Disposal Facility has been receiving radioactive waste from the U.S. Department of Energy (DOE) complex since the 1960s, and since 2005 the NNSS Disposal Facility has been receiving radioactive and MLLW for disposal only. In accordance with the Resource Conservation and Recovery Act (RCRA), all mixed waste must meet land disposal restrictions (LDRs) prior to disposal. Compliance with LDRs is attained through treatment of the waste to mitigate the characteristics of the listed waste hazard. Presently, most generators utilize commercial capacity for waste treatment prior to shipment to the NNSS Disposal Facility. The objectives of this evaluation are to provide a conceptual study of waste treatment needs (i.e., demand), identify potential waste treatment technologies to meet demand, and analyze implementation considerations for initiating MLLW treatment capacity at the NNSS Disposal Facility. A review of DOE complex waste generation forecast data indicates that current and future Departmental demand for mixed waste treatment capacity will remain steady and strong. Analysis and screening of over 30 treatment technologies narrowed the field of treatment technologies to four: • Macroencapsulation • Stabilization/microencapsulation • Sort and segregation • Bench-scale mercury amalgamation The analysis of treatment technologies also considered existing permits, current the NNSS Disposal Facility infrastructure such as utilities and procedures, and past experiences such as green-light and red-light lessons learned. A schedule duration estimate has been developed for permitting, design, and construction of onsite treatment capability at the NNSS Disposal Facility. Treatment capability can be ready in 20 months.

NSTec Environmental Management

2010-11-24T23:59:59.000Z

362

Office of River Protection Waste Treatment and Immobilizatin Project Construction Site, Nov. 16-18, 2010  

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

Tour and Review of the Office of River Tour and Review of the Office of River Protection Waste Treatment and Immobilization Project Construction Site, November 16-18, 2010 The U.S. Department of Energy Office of Independent Oversight, within the Office of Health, Safety and Security (HSS), conducted an orientation visit on November 16-18, 2010, at the Office of River Protection Waste Treatment Immobilization Project (WTP) at the Department of Energy (DOE) Hanford Site. The purposes of the visit were to plan and coordinate future HSS oversight activities and to review corrective actions to the most recent HSS review at WTP. The WTP is an industrial complex for separating and vitrifying millions of gallons of radioactive and chemical waste stored at the Hanford site. The WTP complex consists of five major

363

The Use of Transportable Processing Systems for the Treatment of Radioactive Nuclear Wastes  

Science Conference Proceedings (OSTI)

EnergySolutions has developed two major types of radioactive processing plants based on its experience in the USA and UK, and its exclusive North American access to the intellectual property and know-how developed over 50 years at the Sellafield nuclear site in the UK. Passive Secure Cells are a type of hot cell used in place of the Canyons typically used in US-designed radioactive facilities. They are used in permanent, large scale plants suitable for long term processing of large amounts of radioactive material. The more recently developed Transportable Processing Systems, which are the subject of this paper, are used for nuclear waste processing and clean-up when processing is expected to be complete within shorter timescales and when it is advantageous to be able to move the processing equipment amongst a series of geographically spread-out waste treatment sites. Such transportable systems avoid the construction of a monolithic waste processing plant which itself would require extensive decommissioning and clean-up when its mission is complete. This paper describes a range of transportable radioactive waste processing equipment that EnergySolutions and its partners have developed including: the portable MOSS drum-based waste grouting system, the skid mounted MILWPP large container waste grouting system, the IPAN skid-mounted waste fissile content non-destructive assay system, the Wiped Film Evaporator low liquid hold-up transportable evaporator system, the CCPU transportable solvent extraction cesium separation system, and the SEP mobile shielded cells for emptying radioactive debris from water-filled silos. Maximum use is made of proven, robust, and compact processing equipment such as centrifugal contactors, remote sampling systems, and cement grout feed and metering devices. Flexible, elastomer-based Hose-in-Hose assemblies and container-based transportable pump booster stations are used in conjunction with these transportable waste processing units for transferring radioactive waste from its source to the processing equipment. (authors)

Phillips, Ch.; Houghton, D.; Crawford, G. [EnergySolutions LLC., 2345 Stevens Drive, Richland, WA (United States)

2008-07-01T23:59:59.000Z

364

Analysis of accident sequences and source terms at treatment and storage facilities for waste generated by US Department of Energy waste management operations  

SciTech Connect

This report documents the methodology, computational framework, and results of facility accident analyses performed for the US Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies assessed, and the resultant radiological and chemical source terms evaluated. A personal-computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for the calculation of human health risk impacts. The WM PEIS addresses management of five waste streams in the DOE complex: low-level waste (LLW), hazardous waste (HW), high-level waste (HLW), low-level mixed waste (LLMW), and transuranic waste (TRUW). Currently projected waste generation rates, storage inventories, and treatment process throughputs have been calculated for each of the waste streams. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated, and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. Key assumptions in the development of the source terms are identified. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also discuss specific accident analysis data and guidance used or consulted in this report.

Mueller, C.; Nabelssi, B.; Roglans-Ribas, J.; Folga, S.; Policastro, A.; Freeman, W.; Jackson, R.; Mishima, J.; Turner, S.

1996-12-01T23:59:59.000Z

365

Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, May 2013  

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

Hanford Site Hanford Site Waste Treatment and Immobilization Plant Construction Quality May 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................ 1 2.0 Scope................................................................................................................................................... 1 3.0 Background ......................................................................................................................................... 1 4.0 Methodology ....................................................................................................................................... 2

366

Independent Oversight Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, December 2013  

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

Waste Treatment and Immobilization Plant Construction Quality December 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Scope .................................................................................................................................................... 1 3.0 Background .......................................................................................................................................... 1

367

Method and apparatus for treating gaseous effluents from waste treatment systems  

SciTech Connect

Effluents from a waste treatment operation are incinerated and oxidized by passing the gases through an inductively coupled plasmas arc torch. The effluents are transformed into plasma within the torch. At extremely high plasma temperatures, the effluents quickly oxidize. The process results in high temperature oxidation of the gases without addition of any mass flow for introduction of energy.

Flannery, Philip A. (Ramsey, MT); Kujawa, Stephan T. (Butte, MT)

2000-01-01T23:59:59.000Z

368

Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, October 2012  

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

Site Site Waste Treatment and Immobilization Plant Construction Quality May 2011 October 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope.................................................................................................................................................... 1 4.0 Methodology ........................................................................................................................................

369

Environmental Assessment Offsite Thermal Treatment of Low-Level Mixed Waste  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE), Richland Operations Office (RL) needs to demonstrate the economics and feasibility of offsite commercial treatment of contact-handled low-level mixed waste (LLMW), containing polychlorinated biphenyls (PCBS) and other organics, to meet existing regulatory standards for eventual disposal.

N /A

1999-05-06T23:59:59.000Z

370

Borehole Summary Report for Core Hole C4998 – Waste Treatment Plant Seismic Boreholes Project  

Science Conference Proceedings (OSTI)

Seismic borehole C4998 was cored through the upper portion of the Columbia River Basalt Group and Ellensburg Formation to provide detailed lithologic information and intact rock samples that represent the geology at the Waste Treatment Plant. This report describes the drilling of borehole C4998 and documents the geologic data collected during the drilling of the cored portion of the borehole.

Barnett, D. BRENT; Garcia, Benjamin J.

2006-12-15T23:59:59.000Z

371

CAST STONE TECHNOLOGY FOR THE TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE  

SciTech Connect

Cast stone technology is being evaluated for potential application in the treatment and immobilization of Hanford low-activity waste. The purpose of this document is to provide background information on cast stone technology. The information provided in the report is mainly based on a pre-conceptual design completed in 2003.

MINWALL HJ

2011-04-08T23:59:59.000Z

372

Surrogate formulations for thermal treatment of low-level mixed waste. Part 1: Radiological surrogates  

SciTech Connect

The evaluation and comparison of proposed thermal treatment systems for mixed wastes can be expedited by tests in which the radioactive components of the wastes are replaced by surrogate materials chosen to mimic, as far as is possible, the chemical and physical properties of the radioactive materials of concern. In this work, sponsored by the Mixed Waste Integrated Project of the US Department of Energy, the authors have examined reported experience with such surrogates and suggest a simplified standard list of materials for use in tests of thermal treatment systems. The chief radioactive nuclides of concern in the treatment of mixed wastes are {sup 239}Pu, {sup 238}U, {sup 235}U, {sup 137}Cs, {sup 103}Ru, {sup 99}Tc, and {sup 90}Sr. These nuclides are largely by-products of uranium enrichment, reactor fuel reprocessing, and weapons program activities. Cs, Ru, and Sr all have stable isotopes that can be used as perfect surrogates for the radioactive forms. Technetium exists only in radioactive form, as do plutonium and uranium. If one wishes to preclude radioactive contamination of the thermal treatment system under trial burn, surrogate elements must be chosen for these three. For technetium, the authors suggest the use of natural ruthenium, and for both plutonium and uranium, they recommend cerium. The seven radionuclides listed can therefore be simulated by a surrogate package containing stable isotopes of ruthenium, strontium, cesium, and cerium.

Stockdale, J.A.D.; Bostick, W.D.; Hoffmann, D.P. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States); Lee, H.T. [Oak Ridge Associated Universities, TN (United States)

1994-01-01T23:59:59.000Z

373

Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, October 2012  

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

Site Site Waste Treatment and Immobilization Plant Construction Quality May 2011 October 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope.................................................................................................................................................... 1 4.0 Methodology ........................................................................................................................................

374

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

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

Hanford Site Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality May 2011 March 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope .................................................................................................................................................... 1

375

Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility  

SciTech Connect

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

Bonnema, Bruce Edward

2001-09-01T23:59:59.000Z

376

RADIOACTIVE DEMONSTRATIONS OF FLUIDIZED BED STEAM REFORMING WITH ACUTAL HANFORD LOW ACTIVITY WASTES VERIFYING FBSR AS A SUPPLEMENTARY TREATMENT  

SciTech Connect

The U.S. Department of Energy's Office of River Protection is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level waste (HLW) and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the cleanup mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA). Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. Fluidized Bed Steam Reforming (FBSR) is one of the supplementary treatments being considered. FBSR offers a moderate temperature (700-750 C) continuous method by which LAW and other secondary wastes can be processed irrespective of whether they contain organics, nitrates/nitrites, sulfates/sulfides, chlorides, fluorides, and/or radio-nuclides like I-129 and Tc-99. Radioactive testing of Savannah River LAW (Tank 50) shimmed to resemble Hanford LAW and actual Hanford LAW (SX-105 and AN-103) have produced a ceramic (mineral) waste form which is the same as the non-radioactive waste simulants tested at the engineering scale. The radioactive testing demonstrated that the FBSR process can retain the volatile radioactive components that cannot be contained at vitrification temperatures. The radioactive and nonradioactive mineral waste forms that were produced by co-processing waste with kaolin clay in an FBSR process are shown to be as durable as LAW glass.

Jantzen, C.; Crawford, C.; Burket, P.; Bannochie, C.; Daniel, G.; Nash, C.; Cozzi, A.; Herman, C.

2012-01-12T23:59:59.000Z

377

Treatment of high-level wastes from the IFR fuel cycle  

SciTech Connect

The Integral Fast Reactor (IFR) is being developed as a future commercial power source that promises to have important advantages over present reactors, including improved resource conservation and waste management. The spent metal alloy fuels from an IFR will be processed in an electrochemical cell operating at 500{degree}C with a molten chloride salt electrolyte and cadmium metal anode. After the actinides have been recovered from several batches of core and blanket fuels, the salt cadmium in this electrorefiner will be treated to separate fission products from residual transuranic elements. This treatment produces a waste salt that contains the alkali metal, alkaline earth, and halide fission products; some of the rare earths; and less than 100 nCi/g of alpha activity. The treated metal wastes contain the rest of the fission products (except T, Kr, and Xe) small amounts of uranium, and only trace amounts of transuranic elements. The current concept for the salt waste form is an aluminosilicate matrix, and the concept for the metal waste form is a corrosion-resistant metal alloy. The processes and equipment being developed to treat and immobilize the salt and metal wastes are described.

Johnson, T.R.; Lewis, M.A.; Newman, A.E.; Laidler, J.J.

1992-01-01T23:59:59.000Z

378

Treatment of high-level wastes from the IFR fuel cycle  

Science Conference Proceedings (OSTI)

The Integral Fast Reactor (IFR) is being developed as a future commercial power source that promises to have important advantages over present reactors, including improved resource conservation and waste management. The spent metal alloy fuels from an IFR will be processed in an electrochemical cell operating at 500{degree}C with a molten chloride salt electrolyte and cadmium metal anode. After the actinides have been recovered from several batches of core and blanket fuels, the salt cadmium in this electrorefiner will be treated to separate fission products from residual transuranic elements. This treatment produces a waste salt that contains the alkali metal, alkaline earth, and halide fission products; some of the rare earths; and less than 100 nCi/g of alpha activity. The treated metal wastes contain the rest of the fission products (except T, Kr, and Xe) small amounts of uranium, and only trace amounts of transuranic elements. The current concept for the salt waste form is an aluminosilicate matrix, and the concept for the metal waste form is a corrosion-resistant metal alloy. The processes and equipment being developed to treat and immobilize the salt and metal wastes are described.

Johnson, T.R.; Lewis, M.A.; Newman, A.E.; Laidler, J.J.

1992-08-01T23:59:59.000Z

379

Development of the SREX process for the treatment of ICPP liquid wastes  

SciTech Connect

The removal of {sup 90}Sr from actual and simulated wastes at the Idaho Chemical Processing Plant (ICPP) at the Idaho National Engineering and Environmental Laboratory (INEEL) has been demonstrated with the SREX process. This solvent extraction process employs the extractant 4{prime},4{prime}(5{prime}) di-(t-butylcyclohexano)-18-crown-6 in 1-octanol or a mixture of tributyl phosphate and a hydrocarbon diluent called Isopar L{reg_sign}. Process flowsheets have been designed for testing in countercurrent experiments with centrifugal contractors. The flowsheets have been designed using batch contract solvent extraction methods. The extraction of Sr as well as other interfering ions has been studied. The effect of various parameters including nitric acid dependence, extractant concentration dependence, hydronium ion concentration, and interferent concentrations upon the extraction efficiency of the process has been evaluated. The radiolysis of the SREX solvent has also been investigated as a function of absorbed gamma radiation. The extraction efficiency of the solvent has been shown to be only slightly dependent upon absorbed dose in the range 0--1,000 kGy. The decontamination of actual sodium-bearing waste and dissolved calcine solutions has been accomplished in batch contact flowsheets. Decontamination factors as high as 10E3 have been obtained with sequential batch contacts. Flowsheets have been developed to accomplish decontamination of the liquid wastes with respect to {sup 90}Sr as well as the removal of Pb and Hg. Pb may be partitioned from the Sr fraction in a separate stripping procedure using ammonium citrate. This work has led to the formulation of countercurrent flowsheets which have been tested in centrifugal contractors with actual waste and reported in the document INEEL/EXT-97-00832.

Wood, D.J.; Law, J.D.; Garn, T.G.; Tillotson, R.D.; Tullock, P.A.; Todd, T.A.

1997-12-01T23:59:59.000Z

380

Development of the SREX Process for the Treatment of ICPP Liquid Wastes  

SciTech Connect

The removal of Sr-90 from actual and simulated wastes at the Idaho Chemical Processing Plant (ICPP) at the Idaho National Engineering and Environmental Laboratory (INEEL) has been demonstrated with the SREX process. This solvent extraction process employs the extractant 4',4' (5') de-(t-butylcyclohexano)-18-crown-6 in 1-octanol or a mixture of tributyl phosphate and a hydrocarbon diluent called Isopar L. This development work is based upon earlier work performed by Horwitz, et al. at Argonne National Laboratory. Process flowsheets have been designed for testing in countercurrent experiments with centrifugal contactors. The flowsheets have been designed using batch contact solvent extraction methods. The extraction of Sr as well as other interfering ions has been studied. The effect of various parameters including nitric acid dependence, extractant concentration dependence, Hydronium ion concentration, and interferent concentrations upon the extraction efficiency of the process has been evaluated. The radiolysis of the SREX solvent has also been investigated as a function of absorbed gamma radiation. The extraction efficiency of the solvent has been shown to be only slightly dependent upon absorbed dose in the range 0-1000 kGy. The decontamination of actual sodium-bearing waste and dissolved calcine solutions has been accomplished in batch contact flowsheets. Decontamination factors as high as 10E3 have been obtained with sequential batch contacts. Flowsheets have been developed to accomplish decontamination of the liquid wastes with respect to Sr-90, as well as the removal of Pb and Hg. Pb may be partitioned from the Sr fraction in a separate stripping procedure using ammonium citrate. This work has led to the formulation of countercurrent flowsheets which have been tested in centrifugal contactors with actual waste and reported in the document INEEL/EXT-97-00832.

D. J. Wood; Garn, T. G.; J. D. Law; P. A. Tullock; R. D. Tillotson; T. A. Todd

1997-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "bearing waste treatment" 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

US Department of Energy interim mixed waste inventory report: Waste streams, treatment capacities and technologies: Volume 4, Site specific---Ohio through South Carolina  

SciTech Connect

The Department of Energy (DOE) has prepared this report to provide an inventory of its mixed wastes and treatment capacities and technologies in response to Section 105(a) of the Federal Facility Compliance Act (FFCAct) of 1992 (Pub. L. No. 102-386). As required by the FFCAct-1992, this report provides site-specific information on DOE`s mixed waste streams and a general review of available and planned treatment facilities for mixed wastes at the following five Ohio facilities: Battelle Columbus Laboratories; Fernald Environmental Management Project; Mound Plant; Portsmouth Gaseous Diffusion Plant; and RMI, Titanium Company.

1993-04-01T23:59:59.000Z

382

Independent review of inappropriate identification, storage and treatment methods of polychlorinated biphenyl waste streams  

SciTech Connect

The purpose of the review was to evaluate incidents involving the inappropriate identification, storage, and treatment methods associated with polychlorinated biphenyl (PCB) waste streams originating from the V-tank system at the Test Area North (TAN). The team was instructed to perform a comprehensive review of Lockheed Martin Idaho Technologies Company (LMITCO`s) compliance programs related to these incidents to assess the adequacy and effectiveness of the management program in all respects including: adequacy of the waste management program in meeting all LMITCO requirements and regulations; adequacy of policies, plans, and procedures in addressing and implementing all federal and state requirements and regulations; and compliance status of LMITCO, LMITCO contract team members, and LMITCO contract/team member subcontractor personnel with established PCB management policies, plans, and procedures. The V-Tanks are part of an intermediate waste disposal system and are located at the Technical Support Facility (TSF) at TAN at the Idaho National Engineering and Environmental Laboratory (INEEL). The IRT evaluated how a waste was characterized, managed, and information was documented; however, they did not take control of wastes or ensure followup was performed on all waste streams that may have been generated from the V-Tanks. The team has also subsequently learned that the Environmental Restoration (ER) program is revising the plans for the decontamination and decommissioning of the intermediate waste disposal system based on new information listed and PCB wastes. The team has not reviewed those in-process changes. The source of PCB in the V-Tank is suspected to be a spill of hydraulic fluid in 1968.

1997-07-01T23:59:59.000Z

383

Unvented thermal process for treatment of hazardous and mixed wastes  

Science Conference Proceedings (OSTI)

An Unvented Thermal Process is being developed that does not release gases during the thermal treatment operation. The main unit in the process is a fluidized-bed processor containing a bed of calcined limestone (CaO), which reacts with gases given off during oxidation of organic materials. Gases that will react with CaO include CO{sub 2}, SO{sub 2}, HCI, HBr, and other acid gases. Water vapor formed during the oxidation process is carried off with the fluidizing gas and is removed in a condenser. Oxygen is added to the remaining gas (mainly nitrogen), which is recirculated to the oxidizer. The most flexible arrangement of equipment involves separating the processor into two units: An oxidizer, which may be any of a variety of types including standard incinerators, and a carbon dioxide sorber.

Nelson, P.A.; Swift, W.M.

1993-09-01T23:59:59.000Z

384

CUSHIONED BEARING  

DOE Patents (OSTI)

A vibration damping device effective to dampen vibrations occurring at the several critical speeds encountered in the operation of a high-speed centrifuge is described. A self-centering bearing mechanism is used to protect both the centrifuge shaft and the damping mechanism. The damping mechanism comprises spaced-apant, movable, and stationary sleeve members arranged concentrically of a rotating shaft with a fluid maintained between the members. The movable sleeve member is connected to the shaft for radial movement therewith.

Rushing, F.C.

1960-09-01T23:59:59.000Z

385

PERFORMANCE IMPROVEMENT OF CROSS-FLOW FILTRATION FOR HIGH LEVEL WASTE TREATMENT  

Science Conference Proceedings (OSTI)

In the interest of accelerating waste treatment processing, the DOE has funded studies to better understand filtration with the goal of improving filter fluxes in existing cross-flow equipment. The Savannah River National Laboratory (SRNL) was included in those studies, with a focus on start-up techniques, filter cake development, the application of filter aids (cake forming solid precoats), and body feeds (flux enhancing polymers). This paper discusses the progress of those filter studies. Cross-flow filtration is a key process step in many operating and planned waste treatment facilities to separate undissolved solids from supernate slurries. This separation technology generally has the advantage of self-cleaning through the action of wall shear stress created by the flow of waste slurry through the filter tubes. However, the ability of filter wall self-cleaning depends on the slurry being filtered. Many of the alkaline radioactive wastes are extremely challenging to filtration, e.g., those containing compounds of aluminum and iron, which have particles whose size and morphology reduce permeability. Unfortunately, low filter flux can be a bottleneck in waste processing facilities such as the Savannah River Modular Caustic Side Solvent Extraction Unit and the Hanford Waste Treatment Plant. Any improvement to the filtration rate would lead directly to increased throughput of the entire process. To date increased rates are generally realized by either increasing the cross-flow filter axial flowrate, limited by pump capacity, or by increasing filter surface area, limited by space and increasing the required pump load. SRNL set up both dead-end and cross-flow filter tests to better understand filter performance based on filter media structure, flow conditions, filter cleaning, and several different types of filter aids and body feeds. Using non-radioactive simulated wastes, both chemically and physically similar to the actual radioactive wastes, the authors performed several tests to demonstrate increases in filter performance. With the proper use of filter flow conditions and filter enhancers, filter flow rates can be increased over rates currently realized today.

Duignan, M.; Nash, C.; Poirier, M.

2011-01-12T23:59:59.000Z

386

Integrated municipal solid waste treatment using a grate furnace incinerator: The Indaver case  

SciTech Connect

An integrated installation for treatment of municipal solid waste and comparable waste from industrial origin is described. It consists of three grate furnace lines with flue gas treatment by half-wet scrubbing followed by wet scrubbing, and an installation for wet treatment of bottom ash. It is demonstrated that this integrated installation combines high recovery of energy (40.8% net) with high materials recovery. The following fractions were obtained after wet treatment of the bottom ash: ferrous metals, non-ferrous metals, three granulate fractions with different particle sizes, and sludge. The ferrous and non-ferrous metal fractions can both be recycled as high quality raw materials; the two larger particle size particle fractions can be applied as secondary raw materials in building applications; the sand fraction can be used for applications on a landfill; and the sludge is landfilled. For all components of interest, emissions to air are below the limit values. The integrated grate furnace installation is characterised by zero wastewater discharge and high occupational safety. Moreover, with the considered installation, major pollutants, such as PCDD/PCDF, Hg and iodine-136 are to a large extent removed from the environment and concentrated in a small residual waste stream (flue gas cleaning residue), which can be landfilled after stabilisation.

Vandecasteele, C. [Department of Chemical Engineering, Katholieke Universiteit Leuven, De Croylaan 46, 3001 Leuven (Belgium)], E-mail: carlo.vandecasteele@cit.kuleuven.be; Wauters, G. [Indaver, Dijle 17a, 2800 Mechelen (Belgium); Arickx, S. [Department of Chemical Engineering, Katholieke Universiteit Leuven, De Croylaan 46, 3001 Leuven (Belgium); Jaspers, M. [Indaver, Dijle 17a, 2800 Mechelen (Belgium); Van Gerven, T. [Department of Chemical Engineering, Katholieke Universiteit Leuven, De Croylaan 46, 3001 Leuven (Belgium)

2007-07-01T23:59:59.000Z

387

Molten Salt Oxidation: A Thermal Technology for Waste Treatment and Demilitarization  

SciTech Connect

MSO is a good alternative to incineration for the treatment of a variety of organic wastes including obsolete explosives, low-level mixed waste streams, PCB contaminated oils, spent resins and carbon. The Lawrence Livermore National Laboratory (LLNL) has demonstrated the MSO process for the effective destruction of explosives, explosives-contaminated materials, and other wastes on a 1.5 kg/hr bench-scale unit and in an integrated MSO facility capable of treating 8 kg/hr of low-level radioactive mixed wastes. LLNL, under the direction and support of the Joint Demilitarization Technology (JDT) program, is currently building an integrated MSO plant for destroying explosives, explosives-contaminated sludge and explosives-contaminated activated charcoal. In a parallel effort, LLNL also provides technical support to DOE for the implementation of the MSO technology at industrial scale at Richland, Washington. Over 30 waste streams have been demonstrated with LLNL-built MSO systems. In this paper we will present our latest experimental data, our operational experience with MSO and also discuss its process capabilities.

Hsu, P C; Watkins, B; Pruneda, C; Kwak, S

2001-08-23T23:59:59.000Z

388

SCALE UP OF CERAMIC WASTE FORMS FOR THE EBR-II SPENT FUEL TREATMENT PROCESS  

SciTech Connect

ABSTRACT SCALE UP OF CERAMIC WASTE FORMS FOR THE EBR-II SPENT FUEL TREATMENT PROCESS Matthew C. Morrison, Kenneth J. Bateman, Michael F. Simpson Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 The ceramic waste process is the intended method for disposing of waste salt electrolyte, which contains fission products from the fuel-processing electrorefiners (ER) at the INL. When mixed and processed with other materials, the waste salt can be stored in a durable ceramic waste form (CWF). The development of the CWF has recently progressed from small-scale testing and characterization to full-scale implementation and experimentation using surrogate materials in lieu of the ER electrolyte. Two full-scale (378 kg and 383 kg) CWF test runs have been successfully completed with final densities of 2.2 g/cm3 and 2.1 g/cm3, respectively. The purpose of the first CWF was to establish material preparation parameters. The emphasis of the second pre-qualification test run was to evaluate a preliminary multi-section CWF container design. Other considerations were to finalize material preparation parameters, measure the material height as it consolidates in the furnace, and identify when cracking occurs during the CWF cooldown process.

Matthew C. Morrison; Kenneth J. Bateman; Michael F. Simpson

2010-11-01T23:59:59.000Z

389

RECENT IMPROVEMENTS IN INTERFACE MANAGEMENT FOR HANFORDS WASTE TREATMENT AND IMMOBILIZATION PLANT - 13263  

SciTech Connect

The U.S. Department of Energy (DOE), Office of River Protection (ORP) is responsible for management and completion of the River Protection Project (RPP) mission, which comprises both the Hanford Site tank farms operations and the Waste Treatment and Immobilization Plant (WTP). The RPP mission is to store, retrieve and treat Hanford's tank waste; store and dispose of treated wastes; and close the tank farm waste management areas and treatment facilities by 2047. The WTP is currently being designed and constructed by Bechtel National Inc. (BNI) for DOE-ORP. BNI relies on a number oftechnical services from other Hanford contractors for WTP's construction and commissioning. These same services will be required of the future WTP operations contractor. The WTP interface management process has recently been improved through changes in organization and technical issue management documented in an Interface Management Plan. Ten of the thirteen active WTP Interface Control Documents (ICDs) have been revised in 2012 using the improved process with the remaining three in progress. The value of the process improvements is reflected by the ability to issue these documents on schedule.

ARM ST; PELL MJ; VAN MEIGHEM JS; DUNCAN GM; HARRINGTON C

2012-11-20T23:59:59.000Z

390

Oak Ridge National Lebroatory Liquid&Gaseous Waste Treatment System Strategic Plan  

SciTech Connect

Excellence in Laboratory operations is one of the three key goals of the Oak Ridge National Laboratory (ORNL) Agenda. That goal will be met through comprehensive upgrades of facilities and operational approaches over the next few years. Many of ORNL's physical facilities, including the liquid and gaseous waste collection and treatment systems, are quite old, and are reaching the end of their safe operating life. The condition of research facilities and supporting infrastructure, including the waste handling facilities, is a key environmental, safety and health (ES&H) concern. The existing infrastructure will add considerably to the overhead costs of research due to increased maintenance and operating costs as these facilities continue to age. The Liquid Gaseous Waste Treatment System (LGWTS) Reengineering Project is a UT-Battelle, LLC (UT-B) Operations Improvement Program (OIP) project that was undertaken to develop a plan for upgrading the ORNL liquid and gaseous waste systems to support ORNL's research mission.

Van Hoesen, S.D.

2003-09-09T23:59:59.000Z

391

Waste disposal options report. Volume 2  

SciTech Connect

Volume 2 contains the following topical sections: estimates of feed and waste volumes, compositions, and properties; evaluation of radionuclide inventory for Zr calcine; evaluation of radionuclide inventory for Al calcine; determination of k{sub eff} for high level waste canisters in various configurations; review of ceramic silicone foam for radioactive waste disposal; epoxides for low-level radioactive waste disposal; evaluation of several neutralization cases in processing calcine and sodium-bearing waste; background information for EFEs, dose rates, watts/canister, and PE-curies; waste disposal options assumptions; update of radiation field definition and thermal generation rates for calcine process packages of various geometries-HKP-26-97; and standard criteria of candidate repositories and environmental regulations for the treatment and disposal of ICPP radioactive mixed wastes.

Russell, N.E.; McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.; Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

1998-02-01T23:59:59.000Z

392

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory  

Science Conference Proceedings (OSTI)

This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

Neupauer, R.M.; Thurmond, S.M.

1992-09-01T23:59:59.000Z

393

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 2, Chemical constituents  

Science Conference Proceedings (OSTI)

This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

Neupauer, R.M.; Thurmond, S.M.

1992-09-01T23:59:59.000Z

394

Guideline for benchmarking thermal treatment systems for low-level mixed waste  

SciTech Connect

A process for benchmarking low-level mixed waste (LLMW) treatment technologies has been developed. When used in conjunction with the identification and preparation of surrogate waste mixtures, and with defined quality assurance and quality control procedures, the benchmarking process will effectively streamline the selection of treatment technologies being considered by the US Department of Energy (DOE) for LLMW cleanup and management. Following the quantitative template provided in the benchmarking process will greatly increase the technical information available for the decision-making process. The additional technical information will remove a large part of the uncertainty in the selection of treatment technologies. It is anticipated that the use of the benchmarking process will minimize technology development costs and overall treatment costs. In addition, the benchmarking process will enhance development of the most promising LLMW treatment processes and aid in transferring the technology to the private sector. To instill inherent quality, the benchmarking process is based on defined criteria and a structured evaluation format, which are independent of any specific conventional treatment or emerging process technology. Five categories of benchmarking criteria have been developed for the evaluation: operation/design; personnel health and safety; economics; product quality; and environmental quality. This benchmarking document gives specific guidance on what information should be included and how it should be presented. A standard format for reporting is included in Appendix A and B of this document. Special considerations for LLMW are presented and included in each of the benchmarking categories.

Hoffman, D.P.; Gibson, L.V. Jr.; Hermes, W.H. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States); Bastian, R.E. [Focus Environmental, Inc., Knoxville, TN (United States); Davis, W.T. [Tennessee Univ., Knoxville, TN (United States)

1994-01-01T23:59:59.000Z

395

Review of private sector treatment, storage, and disposal capacity for radioactive waste. Revision 1  

SciTech Connect

This report is an update of a report that summarized the current and near-term commercial and disposal of radioactive and mixed waste. This report was capacity for the treatment, storage, dating and written for the Idaho National Engineering Laboratory (INEL) with the objective of updating and expanding the report entitled ``Review of Private Sector Treatment, Storage, and Disposal Capacity for Radioactive Waste``, (INEL-95/0020, January 1995). The capacity to process radioactively-contaminated protective clothing and/or respirators was added to the list of private sector capabilities to be assessed. Of the 20 companies surveyed in the previous report, 14 responded to the request for additional information, five did not respond, and one asked to be deleted from the survey. One additional company was identified as being capable of performing LLMW treatability studies and six were identified as providers of laundering services for radioactively-contaminated protective clothing and/or respirators.

Smith, M.; Harris, J.G.; Moore-Mayne, S.; Mayes, R.; Naretto, C.

1995-04-14T23:59:59.000Z

396

DEWATERING TREATMENT SCALE-UP TESTING RESULTS OF HANFORD TANK WASTES  

SciTech Connect

This report documents CH2M HILL Hanford Group Inc. (CH2M HILL) 2007 dryer testing results in Richland, WA at the AMEC Nuclear Ltd., GeoMelt Division (AMEC) Horn Rapids Test Site. It provides a discussion of scope and results to qualify the dryer system as a viable unit-operation in the continuing evaluation of the bulk vitrification process. A 10,000 liter (L) dryer/mixer was tested for supplemental treatment of Hanford tank low-activity wastes, drying and mixing a simulated non-radioactive salt solution with glass forming minerals. Testing validated the full scale equipment for producing dried product similar to smaller scale tests, and qualified the dryer system for a subsequent integrated dryer/vitrification test using the same simulant and glass formers. The dryer system is planned for installation at the Hanford tank farms to dry/mix radioactive waste for final treatment evaluation of the supplemental bulk vitrification process.

TEDESCHI AR

2008-01-23T23:59:59.000Z

397

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

398

Microstructural Characterisation of Bainitic Bearing Steel  

Science Conference Proceedings (OSTI)

Abstract Scope, Bainitic heat treatments are applied for rolling bearings where there are typically high demands on toughness and crack propagation resistance .

399

DOE/EIS-0290 Advanced Mixed Waste Treatment Project (January 1999)  

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

2-1999/AppxA.HTML[6/24/2011 1:16:37 PM] 2-1999/AppxA.HTML[6/24/2011 1:16:37 PM] APPENDIX A CONSULTATION LETTERS This appendix will include consultation/approval letters between the U.S. Department of Energy (DOE) and the U.S. Fish and Wildlife Service regarding threatened and endangered species, and between other State and Federal agencies as needed. Letters currently supplied are from the U.S. Fish and Wildlife Service to DOE. DOE/EIS-0290 Advanced Mixed Waste Treatment Project (January 1999) file:///I|/Data%20Migration%20Task/EIS-0290-FEIS-02-1999/AppxA.HTML[6/24/2011 1:16:37 PM] DOE/EIS-0290 Advanced Mixed Waste Treatment Project (January 1999) file:///I|/Data%20Migration%20Task/EIS-0290-FEIS-02-1999/AppxA.HTML[6/24/2011 1:16:37 PM] DOE/EIS-0290 Advanced Mixed Waste Treatment Project (January 1999)

400

Review of the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity, December 2012  

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

the Hanford Site the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity December 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background.......................................................................................................................................... 1 3.0 Scope and Methodology... ................................................................................................................... 1

Note: This page contains sample records for the topic "bearing waste treatment" 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

Review of the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity, December 2012  

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

the Hanford Site the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity December 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background.......................................................................................................................................... 1 3.0 Scope and Methodology... ................................................................................................................... 1

402

Composition of simulants used in the evaluation of electrochemical processes for the treatment of high-level wastes  

SciTech Connect

Four simulants are being used in the evaluation of electrochemical processes for the treatment of high-level wastes (HLW). These simulants represent waste presently stored at the Hanford, Idaho Falls, Oak Ridge, and Savannah River sites. Three of the simulants are highly alkaline salt solutions (Hanford, Oak Ridge, and Savannah River), and one is highly acidic (Idaho Falls).

Hobbs, D.T.

1994-06-27T23:59:59.000Z

403

Demonstration of New Technologies Required for the Treatment of Mixed Waste Contaminated with {ge}260 ppm Mercury  

Science Conference Proceedings (OSTI)

The Resource Conservation and Recovery Act (RCRA) defines several categories of mercury wastes, each of which has a defined technology or concentration-based treatment standard, or universal treatment standard (UTS). RCRA defines mercury hazardous wastes as any waste that has a TCLP value for mercury of 0.2 mg/L or greater. Three of these categories, all nonwastewaters, fall within the scope of this report on new technologies to treat mercury-contaminated wastes: wastes as elemental mercury; hazardous wastes with less than 260 mg/kg [parts per million (ppm)] mercury; and hazardous wastes with 260 ppm or more of mercury. While this report deals specifically with the last category--hazardous wastes with 260 ppm or