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Sample records for waste transportation working

  1. Transuranic Waste Transportation Working Group Agenda

    Office of Environmental Management (EM)

    States Energy Board Joint Meeting of the Radioactive Materials Transportation Committee and the Transuranic Waste Transportation Working Group The Hilton Knoxville Knoxville, Tennessee May 15, 2012 Tuesday, May 15, 2012 8:30 a.m. Breakfast 9:30 a.m. Welcome / Opening Remarks / Introductions - Christopher Wells, Southern States Energy Board - Sandra Threatt, Chair, SSEB Radioactive Materials Transportation Working Group - Elgan Usrey, Chair, SSEB Transuranic Waste Transportation Working Group

  2. Transuranic Waste Transportation Working Group Agenda | Department of

    Office of Environmental Management (EM)

    Energy Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda (75.59 KB) More Documents & Publications Northeast High-Level Radioactive Waste Transportation Task Force Agenda TEC Working Group Topic Groups Archives Protocols Meeting Summaries TEC Meeting Summaries - September 2004

  3. WASTE PACKAGE TRANSPORTER DESIGN

    SciTech Connect (OSTI)

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

    1998-09-23

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

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

    Office of Environmental Management (EM)

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

  5. Waste Isolation Pilot Plant Transportation Security | Department...

    Office of Environmental Management (EM)

    Transportation Security Waste Isolation Pilot Plant Transportation Security Waste Isolation Pilot Plant Transportation Security (2.41 MB) More Documents & Publications Enterprise ...

  6. Mixed Waste Working Group report

    SciTech Connect (OSTI)

    Not Available

    1993-11-09

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

  7. Transportation External Coordination Working Group (TEC)

    Office of Environmental Management (EM)

    Transportation External Coordination Working Group (TEC) July 17-19, 2001 Cincinnati, Ohio Meeting Summary The Transportation External Coordination Working Group (TEC) held its 19 th semi-annual meeting July 17-19, 2001, in Cincinnati, Ohio. One hundred fifteen people attended (see Appendix A for listing of participants). Jim Carlson, U.S. Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) and TEC co-chair, welcomed participants to the meeting. He then introduced

  8. Transport Modeling Working Group Meeting Reports | Department...

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

    Modeling Working Group Meeting Reports Transport Modeling Working Group Meeting Reports View reports from meetings of the Transport Modeling Working Group, which meets twice per ...

  9. Transportation training: Focusing on movement of hazardous substances and wastes

    SciTech Connect (OSTI)

    Jones, E.; Moreland, W.M.

    1988-01-01

    Over the past 25 years extensive federal legislation involving the handling and transport of hazardous materials/waste has been passed that has resulted in numerous overlapping regulations administered and enforced by different federal agencies. The handling and transport of hazardous materials/waste involves a significant number of workers who are subject to a varying degree of risk should an accident occur during handling or transport. Effective transportation training can help workers address these risks and mitigate them, and at the same time enable ORNL to comply with the federal regulations concerning the transport of hazardous materials/waste. This presentation will outline how the Environmental and Health Protection Division's Technical Resources and Training Program at the Oak Ridge National Laboratory, working with transportation and waste disposal personnel, are developing and implementing a comprehensive transportation safety training program to meet the needs of our workers while satisfying appropriate federal regulations. 8 refs., 5 figs., 3 tabs.

  10. Vermont Waste Transportation Permit and License Information ...

    Open Energy Info (EERE)

    Waste Transportation Permit and License Information Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: Vermont...

  11. Annual Transportation Report for Radioactive Waste Shipments...

    National Nuclear Security Administration (NNSA)

    ANNUAL TRANSPORTATION REPORT FY 2008 Radioactive Waste Shipments to and from the Nevada Test Site (NTS) February 2009 United States Department of Energy National Nuclear Security...

  12. HMPT: Hazardous Waste Transportation Live 27928, Test 27929 ...

    Office of Scientific and Technical Information (OSTI)

    HMPT: Hazardous Waste Transportation Live 27928, Test 27929 Citation Details In-Document Search Title: HMPT: Hazardous Waste Transportation Live 27928, Test 27929 You are ...

  13. HMPT: Hazardous Waste Transportation Live 27928, Test 27929 ...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: HMPT: Hazardous Waste Transportation Live 27928, Test 27929 Citation Details In-Document Search Title: HMPT: Hazardous Waste Transportation Live 27928, Test 27929 ...

  14. Transportable Vitrification System Demonstration on Mixed Waste

    SciTech Connect (OSTI)

    Zamecnik, J.R.; Whitehouse, J.C.; Wilson, C.N.; Van Ryn, F.R.

    1998-01-01

    This paper describes preliminary results from the first demonstration of the Transportable Vitrification System (TVS) on actual mixed waste. The TVS is a fully integrated, transportable system for the treatment of mixed and low-level radioactive wastes. The demonstration was conducted at Oak Ridge`s East Tennessee Technology Park (ETTP), formerly known as the K-25 site. The purpose of the demonstration was to show that mixed wastes could be vitrified safely on a `field` scale using joule-heated melter technology and obtain information on system performance, waste form durability, air emissions, and costs.

  15. Repository Waste Package Transporter Shielding Weight Optimization

    SciTech Connect (OSTI)

    C.E. Sanders; Shiaw-Der Su

    2005-02-02

    The Yucca Mountain repository requires the use of a waste package (WP) transporter to transport a WP from a process facility on the surface to the subsurface for underground emplacement. The transporter is a part of the waste emplacement transport systems, which includes a primary locomotive at the front end and a secondary locomotive at the rear end. The overall system with a WP on board weights over 350 metric tons (MT). With the shielding mass constituting approximately one-third of the total system weight, shielding optimization for minimal weight will benefit the overall transport system with reduced axle requirements and improved maneuverability. With a high contact dose rate on the WP external surface and minimal personnel shielding afforded by the WP, the transporter provides radiation shielding to workers during waste emplacement and retrieval operations. This paper presents the design approach and optimization method used in achieving a shielding configuration with minimal weight.

  16. DOE - NNSA/NFO -- EM Radioactive Waste Transportation

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

    Transportation NNSANFO Language Options U.S. DOENNSA - Nevada Field Office Click to subscribe to NNSS News Radioactive Waste Transportation Transportation photo Government and ...

  17. The transportation external coordination working group

    SciTech Connect (OSTI)

    1995-10-01

    In an effort to improve coordinated interactions between the United States Department of Energy (DOE) and external groups interested in transportation activities, DOE established the Transportation External Coordination Working Group (TEC/WG). Membership includes representatives from State, Tribal and local governments, industry, and professional organizations. All DOE programs with significant transportation programs participate.

  18. Working with SRNL - Our Facilities- Waste Treatment Laboratories

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

    Waste Treatment Laboratories Working with SRNL Our Facilities - Waste Treatment Laboratories The Waste Treatment Laboratories is a collection of laboratories for research and development using nonradioactive simulants as well as shielded facilities for work with radioactive materials

  19. Rail transportation of Fernald remediation waste

    SciTech Connect (OSTI)

    Fellman, R.T.; Lojek, D.A.; Motl, G.P.; Weddendorf, W.K.

    1995-01-24

    Remediation of the Department of Energy (DOE) Fernald site located north of Cincinnati will generate large quantities of low-level radwaste. This volume includes approximately 1,050,000 tons of material to be removed from eight waste pits comprising Operable Unit 1 (OU-1). The remedial alternative selected includes waste material excavation, drying and transportation by rail to a burial site in the arid west for disposal. Rail transportation was selected not only because rail transportation is safer than truck transportation, but also because of the sheer magnitude of the project and the availability of bulk rail car unloading facilities at a representative disposal site. Based upon current waste quantity estimates as presented in the Feasibility Study for OUI, a fully-loaded 47-car unit train would depart the Fernald site weekly for five years. This paper illustrates the steps taken to obtain agency and public acceptance of the Record of Decision for the remedy which hinged on rail transportation. A preliminary, but detailed, rail transportation plan was prepared for the project to support a series of CERCLA public meetings conducted in late 1994. Some of the major issues addressed in the plan included the following: (1) Scope of project leading to selection of rail transportation; (2) Waste classification; (3) Rail Company overview; (4) Train configuration and rail car selection; (5) Routing; (6) Safety; (7) Prior Notification Requirements (8) Emergency Response. A series of three public meetings identified a number of issues of prime concern to Fernald stakeholders. Following resolution of these issues during the public comment period, a Record of Decision (ROD) approving implementation of the rail transportation strategy was approved pending incorporation of EPA and State of Ohio comments on December 22, 1994.

  20. Optimization of municipal solid waste collection and transportation routes

    SciTech Connect (OSTI)

    Das, Swapan Bhattacharyya, Bidyut Kr.

    2015-09-15

    Graphical abstract: Display Omitted - Highlights: • Profitable integrated solid waste management system. • Optimal municipal waste collection scheme between the sources and waste collection centres. • Optimal path calculation between waste collection centres and transfer stations. • Optimal waste routing between the transfer stations and processing plants. - Abstract: Optimization of municipal solid waste (MSW) collection and transportation through source separation becomes one of the major concerns in the MSW management system design, due to the fact that the existing MSW management systems suffer by the high collection and transportation cost. Generally, in a city different waste sources scatter throughout the city in heterogeneous way that increase waste collection and transportation cost in the waste management system. Therefore, a shortest waste collection and transportation strategy can effectively reduce waste collection and transportation cost. In this paper, we propose an optimal MSW collection and transportation scheme that focus on the problem of minimizing the length of each waste collection and transportation route. We first formulize the MSW collection and transportation problem into a mixed integer program. Moreover, we propose a heuristic solution for the waste collection and transportation problem that can provide an optimal way for waste collection and transportation. Extensive simulations and real testbed results show that the proposed solution can significantly improve the MSW performance. Results show that the proposed scheme is able to reduce more than 30% of the total waste collection path length.

  1. Transportation External Coordination Working Group (TEC)

    Office of Environmental Management (EM)

    Portland, Oregon - February 6-7, 2001 Transportation External Coordination Working Group (TEC) February 6-7, 2001 Portland, Oregon Meeting Summary The Transportation External Coordination Working Group (TEC) held its 18 th semi-annual meeting February 6-7, 2001, in Portland, Oregon. Attending were 125 representatives from national, State, Tribal and local government organizations, industry and professional groups and other interested parties/DOE programs who meet to address a variety of issues

  2. Transportation considerations related to waste forms and canisters for Defense TRU wastes

    SciTech Connect (OSTI)

    Schneider, K.J.; Andrews, W.B.; Schreiber, A.M.; Rosenthal, L.J.; Odle, C.J.

    1981-09-01

    This report identifies and discusses the considerations imposed by transportation on waste forms and canisters for contact-handled, solid transuranic wastes from the US Department of Energy (DOE) activities. The report reviews (1) the existing raw waste forms and potential immobilized waste forms, (2) the existing and potential future DOE waste canisters and shipping containers, (3) regulations and regulatory trends for transporting commercial transuranic wastes on the ISA, (4) truck and rail carrier requirements and preferences for transporting the wastes, and (5) current and proposed Type B external packagings for transporting wastes.

  3. HMPT: Hazardous Waste Transportation Live 27928, Test 27929 (Technical

    Office of Scientific and Technical Information (OSTI)

    Report) | SciTech Connect HMPT: Hazardous Waste Transportation Live 27928, Test 27929 Citation Details In-Document Search Title: HMPT: Hazardous Waste Transportation Live 27928, Test 27929 HMPT: Hazardous Waste Transportation (Live 27928, suggested one time and associated Test 27929, required initially and every 36 months) addresses the Department of Transportation (DOT) function-specific training requirements of the hazardous materials packagings and transportation (HMPT) Los Alamos

  4. Waste Management Committee Fiscal Year 2016 Work Plan | Department of

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

    Energy 6 Work Plan Waste Management Committee Fiscal Year 2016 Work Plan Topics: TA-54 WIPP Recovery Operations Waste Stored at Waste Control Specialists Consent Order Deliverables FY'17 Budget National Waste Forum WM-FY16-WP - March 9, 2016 (107.69

  5. Spent Fuel and High-Level Radioactive Waste Transportation Report

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by SSEB in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ``comprehensive overview of the issues.`` This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste Issues. In addition. this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages will be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.

  6. Spent fuel and high-level radioactive waste transportation report

    SciTech Connect (OSTI)

    Not Available

    1989-11-01

    This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by the Southern States Energy Board (SSEB) in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ``comprehensive overview of the issues.`` This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste issues. In addition, this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages sew be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.

  7. Spent fuel and high-level radioactive waste transportation report

    SciTech Connect (OSTI)

    Not Available

    1990-11-01

    This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by the Southern States Energy Board (SSEB) in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ``comprehensive overview of the issues.`` This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste issues. In addition, this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages will be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.

  8. WIPP waste acceptance criteria and transportation system

    SciTech Connect (OSTI)

    Wu, C.F.; Ward, T.R.; Gregory, P.C.

    1991-12-31

    The Waste Isolation Pilot Plant (WIPP), located near Carlsbad, New Mexico, USA, is a US Department of Energy (DOE) facility designed as a permanent repository for transuranic wastes in the center of a 2,000-foot-thick salt bed situated 2,150 feet underground. Construction of the facility started in 1975, under a congressional act of site selection. In 1979, demonstration of safe disposal at the WIPP was authorized by Public Law 96-164. The operational philosophy and practice at the facility are: (1) start clean -- stay clean, (2) meet or exceed regulatory requirements, and (3) control radiation exposure levels to as low as reasonably achievable (ALARA). Strict safety measures must be taken in the areas of waste preparation, transportation, and facility operation.

  9. DOE - NNSA/NFO -- EM Radioactive Waste Transportation

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

    Transportation>Transportation Working Group NNSANFO Language Options U.S. DOENNSA - Nevada Field Office Click to subscribe to NNSS News Transportation Working Group The ...

  10. Transportation Plan Ad Hoc Working Group | Department of Energy

    Office of Environmental Management (EM)

    Plan Ad Hoc Working Group Transportation Plan Ad Hoc Working Group PDF icon Transportation Plan Ad Hoc Working Group More Documents & Publications Nuclear Fuel Storage and...

  11. NREL: Transportation Research - Working with Us

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

    Working with Us Partnerships Drive Transportation Solutions Photo of two men standing in front of a large solar panel and an electric vehicle. NREL offers industry, academia, and government agencies opportunities to work with us and leverage our research expertise and capabilities. There are several ways for your organization to get involved with us: Partner with NREL through a Cooperative Research and Development Agreement or a Work-for-Others Agreement. License NREL-developed technologies. The

  12. UFD Storage and Transportation - Transportation Working Group Report

    SciTech Connect (OSTI)

    Maheras, Steven J.; Ross, Steven B.

    2011-08-01

    The Used Fuel Disposition (UFD) Transportation Task commenced in October 2010. As its first task, Pacific Northwest National Laboratory (PNNL) compiled a list of structures, systems, and components (SSCs) of transportation systems and their possible degradation mechanisms during extended storage. The list of SSCs and the associated degradation mechanisms [known as features, events, and processes (FEPs)] were based on the list of used nuclear fuel (UNF) storage system SSCs and degradation mechanisms developed by the UFD Storage Task (Hanson et al. 2011). Other sources of information surveyed to develop the list of SSCs and their degradation mechanisms included references such as Evaluation of the Technical Basis for Extended Dry Storage and Transportation of Used Nuclear Fuel (NWTRB 2010), Transportation, Aging and Disposal Canister System Performance Specification, Revision 1 (OCRWM 2008), Data Needs for Long-Term Storage of LWR Fuel (EPRI 1998), Technical Bases for Extended Dry Storage of Spent Nuclear Fuel (EPRI 2002), Used Fuel and High-Level Radioactive Waste Extended Storage Collaboration Program (EPRI 2010a), Industry Spent Fuel Storage Handbook (EPRI 2010b), and Transportation of Commercial Spent Nuclear Fuel, Issues Resolution (EPRI 2010c). SSCs include items such as the fuel, cladding, fuel baskets, neutron poisons, metal canisters, etc. Potential degradation mechanisms (FEPs) included mechanical, thermal, radiation and chemical stressors, such as fuel fragmentation, embrittlement of cladding by hydrogen, oxidation of cladding, metal fatigue, corrosion, etc. These degradation mechanisms are discussed in Section 2 of this report. The degradation mechanisms have been evaluated to determine if they would be influenced by extended storage or high burnup, the need for additional data, and their importance to transportation. These categories were used to identify the most significant transportation degradation mechanisms. As expected, for the most part, the

  13. TRANSPORT OF WASTE SIMULANTS IN PJM VENT LINES

    SciTech Connect (OSTI)

    Qureshi, Z

    2007-02-21

    The experimental work was conducted to determine whether there is a potential for waste simulant to transport or 'creep' up the air link line and contaminate the pulse jet vent system, and possibly cause long term restriction of the air link line. Additionally, if simulant creep occurred, establish operating parameters for washing down the line. The amount of the addition of flush fluids and mixer downtime must be quantified.

  14. Waste Management Committee Fiscal Year 2015 Work Plan | Department of

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

    Energy 5 Work Plan Waste Management Committee Fiscal Year 2015 Work Plan Topics: TA-54 Consent Order Deliverables FY'17 Budget National Waste Forum WM-FY15-WP - November 17, 2014 (255.83

  15. Development of a Transportable Vitrification System for Mixed Waste

    SciTech Connect (OSTI)

    Whitehouse, J.C.; Jantzen, C.M.; Bickford, D.F.; Kielpinski, A.L.; Helton, B.D.; Van Ryn, F.

    1995-01-13

    The US DOE through the Mixed Waste Integrated Program, has identified a need to move mixed waste vitrification technology from the laboratory to the field as rapidly as possible. A great deal of work over the last few years has shown the feasibility of immobilizing selected hazardous waste streams in a vitrified product. Lab-scale work has been extended to pilot-scale tests, usually with surrogates of the actual waste. DOE felt that the technology was mature enough to allow demonstration in the field, on actual wastes, with units that would be prototypic of full sized waste treatment equipment. To this end, DOE`s Office of Technology Development sponsored the Westinghouse Savannah River Company (WSRC) to specify, procure, test, and operate a field scale demonstration using mobile equipment. Oak Ridge Reservation was chosen as the initial location for the field demonstration and Martin Marietta Reservation was chosen as the initial location for the field demonstration and Martin Marietta Energy Systems (MMES) tasked with all permitting, site preparation, and field support activities. During September 1993, WSRC used a ``Vendor Forum`` to solicit preliminary proposals for the Transportable Vitrification System (TVS). A number of quality proposals were received and evaluated. A vendor was selected and detailed negotiations were completed in August 1994, at which time a contract was signed for the TVS. In parallel, WSRC opened a dialogue with MMES to explore candidate waste streams at the Oak Ridge Reservation for the first TVS vitrification campaign. After some preliminary work, a group of waste water sludges were selected. The first of these to be demonstrated with the TVS will be the West End Treatment Facility (WETF) sludge. This paper describes the development of the specification for the TVS, the design and construction activities to date, and ongoing efforts for permitting and site support. The schedule for field application is also discussed.

  16. AEO2015 Transportation Working Group Meeting

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

    5 Transportation Working Group Meeting Wednesday, July 30, 2014 2:00 - 3:00 p.m. Attendees in person: Austin Brown (NREL) Christopher Ramig (EPA) David Babson (EPA) Devi Mishra (EIA) John Maples (EIA) Lauren Rafelski (EPA) Mindi Farber-DeAnda (EIA) Nicholas Chase (EIA) Patricia Hutchins (EIA) Salil Deshpande (Energetics) Tom Stephens (ANL) Tom White (DOE) Attendees on the phone: Aaron Hula (EPA) Alicia Birky (TA Engineering) Chris Nevers (EPA) Chris Roof (Volpe) Christopher Grillo (IHS) Dallas

  17. Reduced waste generation technical work plan

    SciTech Connect (OSTI)

    Not Available

    1987-05-01

    The United States Department of Energy has established policies for avoiding plutonium losses to the waste streams and minimizing the generation of wastes produced at its nuclear facilities. This policy is evidenced in DOE Order 5820.2, which states Technical and administrative controls shall be directed towards reducing the gross volume of TRU waste generated and the amount of radioactivity in such waste.'' To comply with the DOE directive, the Defense Transuranic Waste Program (DTWP) supports and provides funding for specific research and development tasks at the various DOE sites to reduce the generation of waste. This document has been prepared to give an overview of current and past Reduced Waste Generation task activities which are to be based on technical and cost/benefit factors. The document is updated annually, or as needed, to reflect the status of program direction. Reduced Waste Generation (RWG) tasks encompass a wide range of goals which are basically oriented toward (1) avoiding the generation of waste, (2) changing processes or operations to reduce waste, (3) converting TRU waste into LLW by sorting or decontamination, and (4) reducing volumes through operations such as incineration or compaction.

  18. DOE's Transuranic Waste Processing Center Surpasses 3 Million Safe Work

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

    Hours | Department of Energy DOE's Transuranic Waste Processing Center Surpasses 3 Million Safe Work Hours DOE's Transuranic Waste Processing Center Surpasses 3 Million Safe Work Hours August 1, 2011 - 12:00pm Addthis OAK RIDGE, Tenn. - Earlier today, personnel from the U.S. Department of Energy (DOE) and Wastren Advantage, Inc. (WAI) met to celebrate the achievement of three million work hours without a lost-time accident at the Transuranic Waste Processing Center (TWPC). The TWPC is a

  19. Transportable Vitrification System: Operational experience gained during vitrification of simulated mixed waste

    SciTech Connect (OSTI)

    Whitehouse, J.C.; Burket, P.R.; Crowley, D.A.; Hansen, E.K.; Jantzen, C.M.; Smith, M.E.; Singer, R.P.; Young, S.R.; Zamecnik, J.R.; Overcamp, T.J.; Pence, I.W. Jr.

    1996-11-21

    The Transportable Vitrification System (TVS) is a large-scale, fully-integrated, transportable, vitrification system for the treatment of low-level nuclear and mixed wastes in the form of sludges, soils, incinerator ash, and similar waste streams. The TVS was built to demonstrate the vitrification of actual mixed waste at U. S. Department of Energy (DOE) sites. Currently, Westinghouse Savannah River Company (WSRC) is working with Lockheed Martin Energy Systems (LMES) to apply field scale vitrification to actual mixed waste at Oak Ridge Reservation`s (ORR) K-25 Site. Prior to the application of the TVS to actual mixed waste it was tested on simulated K-25 B and C Pond waste at Clemson University. This paper describes the results of that testing and preparations for the demonstration on actual mixed waste.

  20. Waste Management Committee Fiscal Year 2012 Work Plan | Department...

    Office of Environmental Management (EM)

    Management Committee Fiscal Year 2012 Work Plan Waste Management Committee Fiscal Year 2012 Work Plan Topics: TA-21 TA-54 RiskBenefit Principles Consent Order PDF icon WM-FY12-WP...

  1. Waste Management Committee Fiscal Year 2014 Work Plan | Department...

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

    4 Work Plan Waste Management Committee Fiscal Year 2014 Work Plan Topics: TA-54 Consent Order TA-49 Remediation TA-21 Remediation Material Disposal Areas WM-FY14-WP - September 25, ...

  2. Waste Management Committee Fiscal Year 2013 Work Plan | Department...

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

    3 Work Plan Waste Management Committee Fiscal Year 2013 Work Plan Topics: TA-21 TA-54 RiskBenefit Principles TA-49 Fiscal Year 2012 Budget WM-FY13-WP - September 26, 2012 (13.32

  3. TRANSPORT LOCOMOTIVE AND WASTE PACKAGE TRANSPORTER ITS STANDARDS IDENTIFICATION STUDY

    SciTech Connect (OSTI)

    K.D. Draper

    2005-03-31

    To date, the project has established important to safety (ITS) performance requirements for structures, systems and components (SSCs) based on identification and categorization of event sequences that may result in a radiological release. These performance requirements are defined within the ''Nuclear Safety Design Basis for License Application'' (NSDB) (BSC 2005). Further, SSCs credited with performing safe functions are classified as ITS. In turn, performance confirmation for these SSCs is sought through the use of consensus code and standards. The purpose of this study is to identify applicable codes and standards for the waste package (WP) transporter and transport locomotive ITS SSCs. Further, this study will form the basis for selection and the extent of applicability of each code and standard. This study is based on the design development completed for License Application only. Accordingly, identification of ITS SSCs beyond those defined within the NSDB are based on designs that may be subject to further development during detail design. Furthermore, several design alternatives may still be under consideration to satisfy certain safety functions, and that final selection will not be determined until further design development has occurred. Therefore, for completeness, throughout this study alternative designs currently under consideration will be discussed. Further, the results of this study will be subject to evaluation as part of a follow-on gap analysis study. Based on the results of this study the gap analysis will evaluate each code and standard to ensure each ITS performance requirement is fully satisfied. When a performance requirement is not fully satisfied a ''gap'' is highlighted. Thereafter, the study will identify supplemental requirements to augment the code or standard to meet performance requirements. Further, the gap analysis will identify non-standard areas of the design that will be subject to a Development Plan. Non-standard components and

  4. Status Update: Extended Storage and Transportation Waste Confidence...

    Office of Environmental Management (EM)

    Status Update: Extended Storage and Transportation Waste Confidence Presentation made by David W. Pstrak for the NTSF annual meeting held from May 14-16, 2013 in Buffalo, NY. ...

  5. Transportation functions of the Civilian Radioactive Waste Management System

    SciTech Connect (OSTI)

    Shappert, L.B.; Attaway, C.R.; Pope, R.B. ); Best, R.E.; Danese, F.L. ); Dixon, L.D. , Martinez, GA ); Jones, R.H. , Los Gatos, CA ); Klimas, M.J. ); Peterson, R.W

    1992-03-01

    Within the framework of Public Law 97.425 and provisions specified in the Code of Federal Regulations, Title 10 Part 961, the US Department of Energy has the responsibility to accept and transport spent fuel and high-level waste from various organizations which have entered into a contract with the federal government in a manner that protects the health and safety of the public and workers. In implementing these requirements, the Office of Civilian Radioactive Waste Management (OCRWM) has, among other things, supported the identification of functions that must be performed by a transportation system (TS) that will accept the waste for transport to a federal facility for storage and/or disposal. This document, through the application of system engineering principles, identifies the functions that must be performed to transport waste under this law.

  6. Transport Modeling Working Group | Department of Energy

    Energy Savers [EERE]

    for and understanding of transport phenomena in polymer electrolyte fuel cell stacks. ... to the efficient and cost-effective operation of polymer electrolyte fuel cells. ...

  7. FINAL Transportation External Coordination Working Group (TEC...

    Office of Environmental Management (EM)

    ... Put another way, one question for the group could be, what are the real problems ... and to learn more about other agencies participating in transportation and emergency planning. ...

  8. Women of Waste Management Panel Advises Audience: 'Embrace Hard Work' |

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

    Department of Energy Women of Waste Management Panel Advises Audience: 'Embrace Hard Work' Women of Waste Management Panel Advises Audience: 'Embrace Hard Work' March 30, 2015 - 12:00pm Addthis Panelists, from left, included Johnson, Charboneau, and Piketty, and moderator Jody Redeker. Panelists, from left, included Johnson, Charboneau, and Piketty, and moderator Jody Redeker. PHOENIX - A panel of distinguished leaders in nuclear cleanup discussed issues facing women in the workplace in

  9. Transuranic Waste Transportation Containers - Fact Sheet

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

    TRUPACT-II Each stainless steel TRUPACT-II is approximately eight feet in diameter, 10 ... that must be handled and transported in lead and steel-shielded transportation containers. ...

  10. Interim UFD Storage and Transportation - Transportation Working Group Report

    SciTech Connect (OSTI)

    Maheras, Steven J.; Ross, Steven B.

    2011-03-30

    The Used Fuel Disposition (UFD) Transportation Task commenced in October 2010. As its first task, Pacific Northwest National Laboratory (PNNL) compiled a draft list of structures, systems, and components (SSCs) of transportation systems and their possible degradation mechanisms during very long term storage (VLTS). The list of SSCs and the associated degradation mechanisms [known as features, events, and processes (FEPs)] were based on the list of SSCs and degradation mechanisms developed by the UFD Storage Task (Stockman et al. 2010)

  11. Waste Isolation Pilot Plant Transportation Security

    Office of Environmental Management (EM)

    WIPP Transportation Security Gregory M. Sahd Security Manager Carlsbad Field Office U.S. Department of Energy Contact Information Gregory M. Sahd Security Operations Carlsbad Field Office * U.S. Department of Energy 575.234.8117 * Greg.Sahd@wipp.ws WIPP Transportation "...The (WIPP transportation) system is safer than that employed for any other hazardous material in the U.S...." - National Academy of Sciences, WIPP Panel Hanford Idaho National Engineering and Environmental Laboratory

  12. Office Civilian Waste Management Transportation Institutional Program Update on Collaborative Efforts with Key Stakeholders

    SciTech Connect (OSTI)

    E. Saris; P. Austin; J.J. Offner

    2004-12-29

    The Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) created the Office of National Transportation in 2003 recognizing the need to revitalize and accelerate development of the transportation system. The Department has made a commitment to work through a collaborative planning process before developing specific policies and procedures and making transportation decisions. OCRWM has begun to build the institutional framework to support development of this transportation system. Interactions with stakeholders have been initiated. The authors describe the key stakeholders, identified issues, regional and national planning activities, and mechanisms for interaction.

  13. Transportable vitrification system demonstration on mixed waste. Revision 1

    SciTech Connect (OSTI)

    Zamecnik, J.R.; Whitehouse, J.C.; Wilson, C.N.; Van Ryn, F.R.

    1998-04-22

    The Transportable Vitrification System (TVS) is a large scale, fully integrated, vitrification system for the treatment of low-level and mixed wastes in the form of sludges, soils, incinerator ash, and many other waste streams. It was demonstrated on surrogate waste at Clemson University and at the Oak Ridge Reservation (ORR) prior to treating actual mixed waste. Treatment of a combination of dried B and C Pond sludge and CNF sludge was successfully demonstrated at ORR in 1997. The demonstration produced 7,616 kg of glass from 7,328 kg of mixed wastes with a 60% reduction in volume. Glass formulations for the wastes treated were developed using a combination of laboratory crucible studies with the actual wastes and small melter studies at Clemson with both surrogate and actual wastes. Initial characterization of the B and C Pond sludge had not shown the presence of carbon or fluoride, which required a modified glass formulation be developed to maintain proper glass redox and viscosity. The CNF sludge challenges the glass formulations due to high levels of phosphate and iron. The demonstration was delayed several times by permitting problems, a glass leak, and electrical problems. The demonstration showed that the two wastes could be successfully vitrified, although the design glass production rate was not achieved. The glass produced met the Universal Treatment Standards and the emissions from the TVS were well within the allowable permit limits.

  14. Tank Waste Transport Stability: Summary of Slurry and Salt-Solution Studies for FY 2001

    SciTech Connect (OSTI)

    Welch, T.D.

    2002-06-07

    Despite over 50 years of experience in transporting radioactive tank wastes to and from equipment and tanks at the Department of Energy's Hanford, Savannah River, and Oak Ridge sites, waste slurry transfer pipelines and process piping become plugged on occasion. At Hanford, several tank farm pipelines are no longer in service because of plugs. At Savannah River, solid deposits in the outlet line of the 2H evaporator have resulted in an unplanned extended downtime. Although waste transfer criteria and guidelines intended to prevent pipeline plugging are in place, they are not always adequate. To avoid pipeline plugging in the future, other factors that are not currently embodied in the transfer criteria may need to be considered. The work summarized here is being conducted to develop a better understanding of the chemical and waste flow dynamics during waste transfer. The goal is to eliminate pipeline plugs by improving analysis and engineering tools in the field that incorporate this understanding.

  15. TRU waste transportation -- The flammable gas generation problem

    SciTech Connect (OSTI)

    Connolly, M.J.; Kosiewicz, S.T.

    1997-11-01

    The Nuclear Regulatory Commission (NRC) has imposed a flammable gas (i.e., hydrogen) concentration limit of 5% by volume on transuranic (TRU) waste containers to be shipped using the TRUPACT-II transporter. This concentration is the lower explosive limit (LEL) in air. This was done to minimize the potential for loss of containment during a hypothetical 60 day period. The amount of transuranic radionuclide that is permissible for shipment in TRU waste containers has been tabulated in the TRUPACT-II Safety Analysis Report for Packaging (SARP, 1) to conservatively prevent accumulation of hydrogen above this 5% limit. Based on the SARP limitations, approximately 35% of the TRU waste stored at the Idaho National Engineering and Environmental Lab (INEEL), Los Alamos National Lab (LANL), and Rocky Flats Environmental Technology Site (RFETS) cannot be shipped in the TRUPACT-II. An even larger percentage of the TRU waste drums at the Savannah River Site (SRS) cannot be shipped because of the much higher wattage loadings of TRU waste drums in that site`s inventory. This paper presents an overview of an integrated, experimental program that has been initiated to increase the shippable portion of the Department of Energy (DOE) TRU waste inventory. In addition, the authors will estimate the anticipated expansion of the shippable portion of the inventory and associated cost savings. Such projection should provide the TRU waste generating sites a basis for developing their TRU waste workoff strategies within their Ten Year Plan budget horizons.

  16. Code System to Calculate Waste-Isolation Flow and Transport.

    Energy Science and Technology Software Center (OSTI)

    2001-01-26

    Version 00 Distribution is restricted to the United States Only. SWIFT2 (Sandia Waste Isolation Flow and Transport) is a fully transient, three-dimensional code that solves the coupled equations for transport in geologic media. The processes considered are fluid flow, heat transport, brine migration, and radionuclide-chain transport. Flow, heat and brine transport are coupled via fluid density, fluid viscosity, and porosity. Together they provide the velocity field on which the radionuclide transport depends. Both porous andmore » fractured media are considered. SWIFT2 was developed for use in the analysis of deep geologic nuclear waste-disposal facilities. However, it may be used in other areas such as waste injection into saline aquifers and heat storage in aquifers. Both dual-porosity and discrete-fracture conceptualizations may be considered for the fractured zones. A variable density is included throughout, and a variety of options are available to facilitate the various uses of the code.« less

  17. Developing an institutional strategy for transporting defense transuranic waste materials

    SciTech Connect (OSTI)

    Guerrero, J.V.; Kresny, H.S.

    1986-01-01

    In late 1988, the US Department of Energy (DOE) expects to begin emplacing transuranic waste materials in the Waste Isolation Pilot Plant (WIPP), an R and D facility to demonstrate the safe disposal of radioactive wastes resulting from defense program activities. Transuranic wastes are production-related materials, e.g., clothes, rags, tools, and similar items. These materials are contaminated with alpha-emitting transuranium radionuclides with half-lives of > 20 yr and concentrations > 100 nCi/g. Much of the institutional groundwork has been done with local communities and the State of New Mexico on the siting and construction of the facility. A key to the success of the emplacement demonstration, however, will be a qualified transportation system together with institutional acceptance of the proposed shipments. The DOE's Defense Transuranic Waste Program, and its contractors, has lead responsibility for achieving this goal. The Joint Integration Office (JIO) of the DOE, located in Albuquerque, New Mexico, is taking the lead in implementing an integrated strategy for assessing nationwide institutional concerns over transportation of defense transuranic wastes and in developing ways to resolve or mitigate these concerns. Parallel prototype programs are under way to introduce both the new packaging systems and the institutional strategy to interested publics and organizations.

  18. WIPP Facility Work Plan for Solid Waste Management Units

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2001-02-25

    This 2001 Facility Work Plan (FWP) has been prepared as required by Module VII, Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a), and incorporates comments from the New Mexico Environment Department (NMED) received on December 6, 2000 (NMED, 2000a). This February 2001 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. The permittees are evaluating data from previous investigations of the SWMUs and AOCs against the newest guidance proposed by the NMED. Based on these data, the permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facilitys Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit.

  19. Waste Contaminants at Military Bases Working Group report

    SciTech Connect (OSTI)

    Not Available

    1993-11-04

    The Waste Contaminants at Military Bases Working Group has screened six prospective demonstration projects for consideration by the Federal Advisory Committee to Develop On-Site Innovative Technologies (DOIT). These projects include the Kirtland Air Force Base Demonstration Project, the March Air Force Base Demonstration Project, the McClellan Air Force Base Demonstration Project, the Williams Air Force Base Demonstration Project, and two demonstration projects under the Air Force Center for Environmental Excellence. A seventh project (Port Hueneme Naval Construction Battalion Center) was added to list of prospective demonstrations after the September 1993 Working Group Meeting. This demonstration project has not been screened by the working group. Two additional Air Force remediation programs are also under consideration and are described in Section 6 of this document. The following information on prospective demonstrations was collected by the Waste Contaminants at Military Bases Working Group to assist the DOIT Committee in making Phase 1 Demonstration Project recommendations. The remainder of this report is organized into seven sections: Work Group Charter`s mission and vision; contamination problems, current technology limitations, and institutional and regulatory barriers to technology development and commercialization, and work force issues; screening process for initial Phase 1 demonstration technologies and sites; demonstration descriptions -- good matches;demonstration descriptions -- close matches; additional candidate demonstration projects; and next steps.

  20. Tank waste remediation system multi-year work plan

    SciTech Connect (OSTI)

    Not Available

    1994-09-01

    The Tank Waste Remediation System (TWRS) Multi-Year Work Plan (MYWP) documents the detailed total Program baseline and was constructed to guide Program execution. The TWRS MYWP is one of two elements that comprise the TWRS Program Management Plan. The TWRS MYWP fulfills the Hanford Site Management System requirement for a Multi-Year Program Plan and a Fiscal-Year Work Plan. The MYWP addresses program vision, mission, objectives, strategy, functions and requirements, risks, decisions, assumptions, constraints, structure, logic, schedule, resource requirements, and waste generation and disposition. Sections 1 through 6, Section 8, and the appendixes provide program-wide information. Section 7 includes a subsection for each of the nine program elements that comprise the TWRS Program. The foundation of any program baseline is base planning data (e.g., defendable product definition, logic, schedules, cost estimates, and bases of estimates). The TWRS Program continues to improve base data. As data improve, so will program element planning, integration between program elements, integration outside of the TWRS Program, and the overall quality of the TWRS MYWP. The MYWP establishes the TWRS baseline objectives to store, treat, and immobilize highly radioactive Hanford waste in an environmentally sound, safe, and cost-effective manner. The TWRS Program will complete the baseline mission in 2040 and will incur costs totalling approximately 40 billion dollars. The summary strategy is to meet the above objectives by using a robust systems engineering effort, placing the highest possible priority on safety and environmental protection; encouraging {open_quotes}out sourcing{close_quotes} of the work to the extent practical; and managing significant but limited resources to move toward final disposition of tank wastes, while openly communicating with all interested stakeholders.

  1. DWPF (Defense Waste Processing Facility) canister impact testing and analyses for the Transportation Technology Center

    SciTech Connect (OSTI)

    Farnsworth, R.K.; Mishima, J.

    1988-12-01

    A legal weight truck cask design has been developed for the US Department of Energy by GA Technologies, Inc. The cask will be used to transport defense high-level waste canisters produced by the Defense Waste Processing Facility (DWPF) at the Savannah River Plant. The development of the cask required the collection of impact data for the DWPF canisters. The Materials Characterization Center (MCC) performed this work under the guidance of the Transportation Technology Center (TTC) at Sandia National Laboratories. Two full-scale DWPF canisters filled with nonradioactive borosilicate glass were impacted under ''normal'' and ''hypothetical'' accident conditions. Two canisters, supplied by the DWPF, were tested. Each canister was vertically dropped on the bottom end from a height of either 0.3 m or 9.1 m (for normal or hypothetical accident conditions, respectively). The structural integrity of each canister was then examined using helium leak and dye penetrant testing. The canisters' diameters and heights, which had been previously measured, were then remeasured to determine how the canister dimensions had changed. Following structural integrity testing, the canisters were flaw leak tested. For transportation flaw leak testing, four holes were fabricated into the shell of canister A-27 (0.3 m drop height). The canister was then transported a total distance of 2069 miles. During transport, the waste form material that fell from each flaw was collected to determine the amount of size distribution of each flaw release. 2 refs., 8 figs., 12 tabs.

  2. Commercial low-level radioactive waste transportation liability and radiological risk

    SciTech Connect (OSTI)

    Quinn, G.J.; Brown, O.F. II; Garcia, R.S.

    1992-08-01

    This report was prepared for States, compact regions, and other interested parties to address two subjects related to transporting low-level radioactive waste to disposal facilities. One is the potential liabilities associated with low-level radioactive waste transportation from the perspective of States as hosts to low-level radioactive waste disposal facilities. The other is the radiological risks of low-level radioactive waste transportation for drivers, the public, and disposal facility workers.

  3. Second AEO2014 Transportation Working Group Meeting Summary

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

    , 2013 MEMORANDUM FOR: JOHN CONTI ASSISTANT ADMINISTRATOR FOR ENERGY ANALYSIS PAUL HOLTBERG TEAM LEADER ANALYSIS INTEGRATION TEAM JIM TURNURE DIRECTOR OFFICE OF ENERGY CONSUMPTION AND EFFICIENCY ANALYSIS FROM: TRANSPORTATION CONSUMPTION & EFFICIENCY ANALYSIS TEAM SUBJECT: Second AEO2014 Transportation Working Group Meeting Summary (presented on 09-25-2013) Attendees: Nicholas Chase (EIA/OECEA) Carrie Hughes-Cromwick (EIA/OES) Paul Holtberg (EIA/OEA) Trisha Hutchins (EIA/OECEA) Jim Kliesch

  4. WIPP Facility Work Plan for Solid Waste Management Units

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2002-02-14

    This 2002 Facility Work Plan (FWP) has been prepared as required by Module VII, Permit Condition VII.U.3 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit) (New Mexico Environment Department [NMED], 1999a), and incorporates comments from the NMED received on December 6, 2000 (NMED, 2000a). This February 2002 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. The Permittees are evaluating data from previous investigations of the SWMUs and AOCs against the most recent guidance proposed by the NMED. Based on these data, and completion of the August 2001 sampling requested by the NMED, the Permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA processcan be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable

  5. WASTES-II: Waste System Transportation and Economic Simulation--Release 24: User's guide

    SciTech Connect (OSTI)

    Ouderkirk, S.J.

    1988-12-01

    WASTES models each reactor pool and an at-reactor, out-of-pool (ex-pool) storage facility for each reactor site. Spent fuel transfers between pools can be simulated under various constraints controlled by user input. In addition to simulating each pool and ex-pool facility, WASTES can accommodate up to ten other storage facilities of four different types: federal interim storage (FIS), monitored retrievable storage (MRS), auxiliary plants, and repositories. Considerable flexibility is allowed for the user to specify system configuration and priorities for fuel receipts. In addition, the WASTES computer code simulates very detailed (assembly-specific) movements of spent fuel throughout the waste management system. Spent fuel characteristics that are tracked by WASTES for each movement are: discharge year and month, number of assemblies, weight of uranium (MTU), exposure, original enrichment, and heat generation rate (calculated from the preceding characteristics). Data for the WASTES model is based upon the DOE reactor-specific spent fuel data base, which is developed and maintained by the Energy Information Administration (EIA). In addition to the spent fuel characteristics, this data includes reactor location, type, transportation access, and historical and projected discharge data on the number of fuel assemblies. 8 refs., 3 figs., 4 tabs.

  6. 2011-03 "Using Rail transport for Moving Waste" | Department of Energy

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

    3 "Using Rail transport for Moving Waste" 2011-03 "Using Rail transport for Moving Waste" The intent of this NNMCAB recommendation is to see that the required cleanup at LANL is completed in the safest way, specifically relative to movement of waste. Rec 2011-03 - January 26, 2011 (158.28

  7. Russian Containers for Transportation of Solid Radioactive Waste

    SciTech Connect (OSTI)

    Petrushenko, V. G.; Baal, E. P.; Tsvetkov, D. Y.; Korb, V. R.; Nikitin, V. S.; Mikheev, A. A.; Griffith, A.; Schwab, P.; Nazarian, A.

    2002-02-28

    The Russian Shipyard ''Zvyozdochka'' has designed a new container for transportation and storage of solid radioactive wastes. The PST1A-6 container is cylindrical shaped and it can hold seven standard 200-liter (55-gallon) drums. The steel wall thickness is 6 mm, which is much greater than standard U.S. containers. These containers are fully certified to the Russian GOST requirements, which are basically identical to U.S. and IAEA standards for Type A containers. They can be transported by truck, rail, barge, ship, or aircraft and they can be stacked in 6 layers in storage facilities. The first user of the PST1A-6 containers is the Northern Fleet of the Russian Navy, under a program sponsored jointly by the U.S. DoD and DOE. This paper will describe the container design and show how the first 400 containers were fabricated and certified.

  8. Waste management project fiscal year 1998 multi-year work plan WBS 1.2

    SciTech Connect (OSTI)

    Slaybaugh, R.R.

    1997-08-29

    The MYWP technical baseline describes the work to be accomplished by the Project and the technical standards which govern that work. The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposition of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project (SW), Liquid Effluents Project (LEP), and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible. The paper tabulates the major facilities that interface with this Project, identifying the major facilities that generate waste, materials, or infrastructure for this Project and the major facilities that will receive waste and materials from this Project.

  9. Transportation Working Group (TWG) Meeting Friday, November 16, 2012

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

    Working Group (TWG) Meeting Friday, November 16, 2012 9-11am Nohemi Brewer, U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Transportation Manager, opened the meeting at 9:05am with 23 in-person attendees and two via video teleconferencing in Carson City. Following an introduction by Ms. Brewer, participants introduced themselves and identified their organization. Represented organizations included: NNSA/NSO; National Security Technologies, LLC;

  10. Trash or treasure? Putting coal combustion waste to work

    SciTech Connect (OSTI)

    Tenenbaum, D.J.

    2009-11-15

    The use of coal combustion wastes from power plants in construction materials, leaching and the impact of regulations are discussed.

  11. Waste Management Project fiscal year 1998 multi-year work plan, WBS 1.2

    SciTech Connect (OSTI)

    Jacobsen, P.H.

    1997-09-23

    The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposal of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project, Liquid Effluents Project, and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible.

  12. TECHNICAL EVALUATION OF THE SAFE TRANSPORTATION OF WASTE CONTAINERS COATED WITH POLYUREA

    SciTech Connect (OSTI)

    VAIL, T.S.

    2007-03-30

    This technical report is to evaluate and establish that the transportation of waste containers (e.g. drums, wooden boxes, fiberglass-reinforced plywood (FRP) or metal boxes, tanks, casks, or other containers) that have an external application of polyurea coating between facilities on the Hanford Site can be achieved with a level of onsite safety equivalent to that achieved offsite. Utilizing the parameters, requirements, limitations, and controls described in the DOE/RL-2001-36, ''Hanford Sitewide Transportation Safety Document'' (TSD) and the Department of Energy Richland Operations (DOE-RL) approved package specific authorizations (e.g. Package Specific Safety Documents (PSSDs), One-Time Requests for Shipment (OTRSs), and Special Packaging Authorizations (SPAS)), this evaluation concludes that polyurea coatings on packages does not impose an undue hazard for normal and accident conditions. The transportation of all packages on the Hanford Site must comply with the transportation safety basis documents for that packaging system. Compliance with the requirements, limitations, or controls described in the safety basis for a package system will not be relaxed or modified because of the application of polyurea. The inspection criteria described in facility/projects procedures and work packages that ensure compliance with Container Management Programs and transportation safety basis documentation dictate the need to overpack a package without consideration for polyurea. This technical report reviews the transportation of waste packages coated with polyurea and does not credit the polyurea with enhancing the structural, thermal, containment, shielding, criticality, or gas generating posture of a package. Facilities/Projects Container Management Programs must determine if a container requires an overpack prior to the polyurea application recognizing that circumstances newly discovered surface contamination or loss of integrity may require a previously un

  13. Evaluation of the transport and resuspension of a simulated nuclear waste slurry: Nuclear Waste Treatment Program

    SciTech Connect (OSTI)

    Carleson, T.E.; Drown, D.C.; Hart, R.E.; Peterson, M.E.

    1987-09-01

    The Department of Chemical Engineering at the University of Idaho conducted research on the transport and resuspension of a simulated high-level nuclear waste slurry. In the United States, the reference process for treating both defense and civilian HLLW is vitrification using the liquid-fed ceramic melter process. The non-Newtonian behavior of the slurry complicates the evaluation of the transport and resuspension characteristics of the slurry. The resuspension of a simulated (nonradioactive) melter feed slurry was evaluated using a slurry designated as WV-205. The simulated slurry was developed for the West Valley Demonstration Project and was used during a pilot-scale ceramic melter (PSCM) experiment conducted at PNL in July 1985 (PSCM-21). This study involved determining the transport characteristics of a fully suspended slurry and the resuspension characteristics of settled solids in a pilot-scale pipe loop. The goal was to predict the transport and resuspension of a full-scale system based on rheological data for a specific slurry. The rheological behavior of the slurry was evaluated using a concentric cylinder rotational viscometer, a capillary tube viscometer, and the pilot-scale pipe loop. The results obtained from the three approaches were compared. 40 refs., 74 figs., 15 tabs.

  14. Waste management facilities cost information for transportation of radioactive and hazardous materials

    SciTech Connect (OSTI)

    Feizollahi, F.; Shropshire, D.; Burton, D.

    1995-06-01

    This report contains cost information on the U.S. Department of Energy (DOE) Complex waste streams that will be addressed by DOE in the programmatic environmental impact statement (PEIS) project. It describes the results of the task commissioned by DOE to develop cost information for transportation of radioactive and hazardous waste. It contains transportation costs for most types of DOE waste streams: low-level waste (LLW), mixed low-level waste (MLLW), alpha LLW and alpha MLLW, Greater-Than-Class C (GTCC) LLW and DOE equivalent waste, transuranic (TRU) waste, spent nuclear fuel (SNF), and hazardous waste. Unit rates for transportation of contact-handled (<200 mrem/hr contact dose) and remote-handled (>200 mrem/hr contact dose) radioactive waste are estimated. Land transportation of radioactive and hazardous waste is subject to regulations promulgated by DOE, the U.S. Department of Transportation (DOT), the U.S. Nuclear Regulatory Commission (NRC), and state and local agencies. The cost estimates in this report assume compliance with applicable regulations.

  15. A Dual Regime Reactive Transport Model for Simulation of High Level Waste Tank Closure Scenarios - 13375

    SciTech Connect (OSTI)

    Sarkar, Sohini; Kosson, David S.; Brown, Kevin; Garrabrants, Andrew C.; Meeussen, Hans; Van der Sloot, Hans

    2013-07-01

    A numerical simulation framework is presented in this paper for estimating evolution of pH and release of major species from grout within high-level waste tanks after closure. This model was developed as part of the Cementitious Barriers Partnership. The reactive transport model consists of two parts - (1) transport of species, and (2) chemical reactions. The closure grout can be assumed to have varying extents of cracking and composition for performance assessment purposes. The partially or completely degraded grouted tank is idealized as a dual regime system comprising of a mobile region having solid materials with cracks and macro-pores, and an immobile/stagnant region having solid matrix with micropores. The transport profiles of the species are calculated by incorporating advection of species through the mobile region, diffusion of species through the immobile/stagnant region, and exchange of species between the mobile and immobile regions. A geochemical speciation code in conjunction with the pH dependent test data for a grout material is used to obtain a mineral set that best describes the trends in the test data of the major species. The dual regime reactive transport model predictions are compared with the release data from an up-flow column percolation test. The coupled model is then used to assess effects of crack state of the structure, rate and composition of the infiltrating water on the pH evolution at the grout-waste interface. The coupled reactive transport model developed in this work can be used as part of the performance assessment process for evaluating potential risks from leaching of a cracked tank containing elements of human health and environmental concern. (authors)

  16. Northeast High-Level Radioactive Waste Transportation Task Force...

    Office of Environmental Management (EM)

    members & alternates appointment status Legislative Liaisons Staff ... (by speaker phone) 1:45 p.m. Update: Decommissioning Plant Coalition Nuclear Waste ...

  17. RCRA information on hazardous wastes for publicly owned treatment works. Technical report

    SciTech Connect (OSTI)

    Not Available

    1985-09-01

    The guidance manual provides guidance to municipal personnel in understanding hazardous waste requirements of the Resource Conservation and Recovery Act (RCRA) and the implications of these RCRA requirements for the wastewater treatment plant operated by your municipality, for your local pretreatment program, and for local industries served by the treatment plant. The primary purpose of the manual is the RCRA notification requirement specified in the General Pretreatment Regulations. The manual focuses on Subtitle C requirements. (Subtitle C is directly applicable to industries since this program regulates generators, transporters, and disposers of hazardous waste). The manual also provides a general understanding of how federal RCRA requirements for hazardous waste affect industrial users. The manual also will be helpful in complying with any applicable federal requirements incumbent upon your POTW under Subtitle C of RCRA. The appendices contain lists of hazardous wastes regulated by federal requirements; selected EPA-approved forms for hazardous waste facilities to use; RCRA information brochure which briefly outlines the Act's impact on industries that generate or transport hazardous wastes; and EPA pamphlets summarizing information for generators of small quantities of hazardous waste.

  18. Midwestern High-Level Radioactive Waste Transportation Project. Highway infrastructure report

    SciTech Connect (OSTI)

    Sattler, L.R.

    1992-02-01

    In addition to arranging for storage and disposal of radioactive waste, the US Department of Energy (DOE) must develop a safe and efficient transportation system in order to deliver the material that has accumulated at various sites throughout the country. The ability to transport radioactive waste safely has been demonstrated during the past 20 years: DOE has made over 2,000 shipments of spent fuel and other wastes without any fatalities or environmental damage related to the radioactive nature of the cargo. To guarantee the efficiency of the transportation system, DOE must determine the optimal combination of rail transport (which allows greater payloads but requires special facilities) and truck transport Utilizing trucks, in turn, calls for decisions as to when to use legal weight trucks or, if feasible, overweight trucks for fewer but larger shipments. As part of the transportation system, the Facility Interface Capability Assessment (FICA) study contributes to DOE`s development of transportation plans for specific facilities. This study evaluates the ability of different facilities to receive, load and ship the special casks in which radioactive materials will be housed during transport In addition, the DOE`s Near-Site Transportation Infrastructure (NSTI) study (forthcoming) will evaluate the rail, road and barge access to 76 reactor sites from which DOE is obligated to begin accepting spent fuel in 1998. The NSTI study will also assess the existing capabilities of each transportation mode and route, including the potential for upgrade.

  19. MODELING OF THE GROUNDWATER TRANSPORT AROUND A DEEP BOREHOLE NUCLEAR WASTE REPOSITORY

    SciTech Connect (OSTI)

    N. Lubchenko; M. Rodríguez-Buño; E.A. Bates; R. Podgorney; E. Baglietto; J. Buongiorno; M.J. Driscoll

    2015-04-01

    The concept of disposal of high-level nuclear waste in deep boreholes drilled into crystalline bedrock is gaining renewed interest and consideration as a viable mined repository alternative. A large amount of work on conceptual borehole design and preliminary performance assessment has been performed by researchers at MIT, Sandia National Laboratories, SKB (Sweden), and others. Much of this work relied on analytical derivations or, in a few cases, on weakly coupled models of heat, water, and radionuclide transport in the rock. Detailed numerical models are necessary to account for the large heterogeneity of properties (e.g., permeability and salinity vs. depth, diffusion coefficients, etc.) that would be observed at potential borehole disposal sites. A derivation of the FALCON code (Fracturing And Liquid CONvection) was used for the thermal-hydrologic modeling. This code solves the transport equations in porous media in a fully coupled way. The application leverages the flexibility and strengths of the MOOSE framework, developed by Idaho National Laboratory. The current version simulates heat, fluid, and chemical species transport in a fully coupled way allowing the rigorous evaluation of candidate repository site performance. This paper mostly focuses on the modeling of a deep borehole repository under realistic conditions, including modeling of a finite array of boreholes surrounded by undisturbed rock. The decay heat generated by the canisters diffuses into the host rock. Water heating can potentially lead to convection on the scale of thousands of years after the emplacement of the fuel. This convection is tightly coupled to the transport of the dissolved salt, which can suppress convection and reduce the release of the radioactive materials to the aquifer. The purpose of this work has been to evaluate the importance of the borehole array spacing and find the conditions under which convective transport can be ruled out as a radionuclide transport mechanism

  20. Silicon-Polymer Encapsulation of High-Level Calcine Waste for Transportation or Disposal

    SciTech Connect (OSTI)

    G. G. Loomis; C. M. Miller; J. A. Giansiracusa; R. Kimmel; S. V. Prewett

    2000-01-01

    This report presents the results of an experimental study investigating the potential uses for silicon-polymer encapsulation of High Level Calcine Waste currently stored within the Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Engineering and Environmental Laboratory (INEEL). The study investigated two different applications of silicon polymer encapsulation. One application uses silicon polymer to produce a waste form suitable for disposal at a High Level Radioactive Waste Disposal Facility directly, and the other application encapsulates the calcine material for transportation to an offsite melter for further processing. A simulated waste material from INTEC, called pilot scale calcine, which contained hazardous materials but no radioactive isotopes was used for the study, which was performed at the University of Akron under special arrangement with Orbit Technologies, the originators of the silicon polymer process called Polymer Encapsulation Technology (PET). This document first discusses the PET process, followed by a presentation of past studies involving PET applications to waste problems. Next, the results of an experimental study are presented on encapsulation of the INTEC calcine waste as it applies to transportation or disposal of calcine waste. Results relating to long-term disposal include: (1) a characterization of the pilot calcine waste; (2) Toxicity Characteristic Leaching Procedure (TCLP) testing of an optimum mixture of pilot calcine, polysiloxane and special additives; and, (3) Material Characterization Center testing MCC-1P evaluation of the optimum waste form. Results relating to transportation of the calcine material for a mixture of maximum waste loading include: compressive strength testing, 10-m drop test, melt testing, and a Department of Transportation (DOT) oxidizer test.

  1. Polysiloxane Encapsulation of High Level Calcine Waste for Transportation or Disposal

    SciTech Connect (OSTI)

    Loomis, Guy George

    2000-03-01

    This report presents the results of an experimental study investigating the potential uses for silicon-polymer encapsulation of High Level Calcine Waste currently stored within the Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Engineering and Environmental Laboratory (INEEL). The study investigated two different applications of silicon polymer encapsulation. One application uses silicon polymer to produce a waste form suitable for disposal at a High Level Radioactive Waste Disposal Facility directly, and the other application encapsulates the calcine material for transportation to an offsite melter for further processing. A simulated waste material from INTEC, called pilot scale calcine, which contained hazardous materials but no radioactive isotopes was used for the study, which was performed at the University of Akron under special arrangement with Orbit Technologies, the originators of the silicon polymer process called Polymer Encapsulation Technology (PET). This document first discusses the PET process, followed by a presentation of past studies involving PET applications to waste problems. Next, the results of an experimental study are presented on encapsulation of the INTEC calcine waste as it applies to transportation or disposal of calcine waste. Results relating to long-term disposal include: 1) a characterization of the pilot calcine waste; 2) Toxicity Characteristic Leaching Procedure (TCLP) testing of an optimum mixture of pilot calcine, polysiloxane and special additives; and, 3) Material Characterization Center testing MCC-1P evaluation of the optimum waste form. Results relating to transportation of the calcine material for a mixture of maximum waste loading include: compressive strength testing, 10-m drop test, melt testing, and a Department of Transportation (DOT) oxidizer test.

  2. Historical Information on the Transportation External Coordination Working Group (TEC)

    Broader source: Energy.gov [DOE]

    TEC was formed in 1992 to improve coordination between the U.S. Department of Energy (DOE) and external groups interested in the Department's transportation activities. TEC was co-chaired by DOE's...

  3. Costs and impacts of transporting nuclear waste to candidate repository sites

    SciTech Connect (OSTI)

    McSweeney, T.I.; Peterson, R.W.; Gupta, R.

    1983-12-31

    In this paper, a status report on the current estimated costs and impacts of transporting high-level nuclear wastes to candidate disposal sites is given. Impacts in this analysis are measured in terms of risk to public health and safety. Since it is difficult to project the status of the nuclear industry to the time of repository operation - 20 to 50 years in the future - particular emphasis in the paper is placed on the evaluation of uncertainties. The first part of this paper briefly describes the characteristics of the waste that must be transported to a high-level waste disposal site. This discussion is followed by a section describing the characteristics of the waste transport system. Subsequent sections describe the costs and risk assessments of waste transport. Finally, in a concluding section, the effect of the uncertainties in the definition of the waste disposal system on cost and risk levels is evaluated. This last section also provides some perspectives on the magnitude of the cost and risk levels relative to other comparable costs and risks generally encountered. 13 references, 2 figures, 16 tables.

  4. The ecological relevance of transport in waste disposal systems in Western Europe

    SciTech Connect (OSTI)

    Salhofer, Stefan Schneider, Felicitas; Obersteiner, Gudrun

    2007-07-01

    With the development of modern waste management systems in Western Europe, a remarkable increase in the distances for waste transportation has been observed. The question thus arises whether recycling with longer transport distances is ecologically advantageous or whether disposal without recycling is to be preferred. This situation was analysed using selected product and waste streams. This included refrigerators, paper, polyethylene films and expanded polystyrene. For each of these streams, a life cycle analysis was conducted with an emphasis on waste transport. The system boundaries were set in terms of the generation of waste to recycling or landfilling. The comparison included several scenarios with recycling and different transport distances. Landfilling was used as the reference scenario. The results obtained demonstrated how transport distances influence the ecological benefit of recycling. In the case of expanded polystyrene, the ecological boundaries are reached in practical situations, while with other materials these boundaries are far from being attained. In these cases, more complex and elaborate collection schemes, such as kerbside collection, which is economically convenient and shows the highest collection rates, can also be recommended.

  5. Transportable Vitrification System RCRA Closure Practical Waste Disposition Saves Time And Money

    SciTech Connect (OSTI)

    Brill, Angie; Boles, Roger; Byars, Woody

    2003-02-26

    The Transportable Vitrification System (TVS) was a large-scale vitrification system for the treatment of mixed wastes. The wastes contained both hazardous and radioactive materials in the form of sludge, soil, and ash. The TVS was developed to be moved to various United States Department of Energy (DOE) facilities to vitrify mixed waste as needed. The TVS consists of four primary modules: (1) Waste and Additive Materials Processing Module; (2) Melter Module; (3) Emissions Control Module; and (4) Control and Services Module. The TVS was demonstrated at the East Tennessee Technology Park (ETTP) during September and October of 1997. During this period, approximately 16,000 pounds of actual mixed waste was processed, producing over 17,000 pounds of glass. After the demonstration was complete it was determined that it was more expensive to use the TVS unit to treat and dispose of mixed waste than to direct bury this waste in Utah permitted facility. Thus, DOE had to perform a Resource Conservation and Recovery Act (RCRA) closure of the facility and find a reuse for as much of the equipment as possible. This paper will focus on the following items associated with this successful RCRA closure project: TVS site closure design and implementation; characterization activities focused on waste disposition; pollution prevention through reuse; waste minimization efforts to reduce mixed waste to be disposed; and lessons learned that would be integrated in future projects of this magnitude.

  6. Code System to Calculate Waste-Isolation Flow and Transport.

    Energy Science and Technology Software Center (OSTI)

    1999-10-18

    Version 00 SWIFT solves the coupled or individual equations governing fluid flow, heat transport, brine displacement, and radionuclide displacement in geologic media. Fluid flow may be transient or steady state. One, two, or three dimensions are available, and transport of radionuclides chains is possible.

  7. Idaho Crews Use Waste Treatment Expertise to Land Additional Work |

    Office of Environmental Management (EM)

    Management Human Capital Management The strategic management of human capital requires comprehensive planning and analysis in order to develop, implement, and evaluate programs that support every facet of employee work life. DOE human capital initiatives are designed to support continuous improvement and accountability in accordance with the DOE Human Capital Management Accountability Program (HCMAP), which is an internal DOE audit process of servicing human resources offices and addresses those

  8. Physical, Hydraulic, and Transport Properties of Sediments and Engineered Materials Associated with Hanford Immobilized Low-Activity Waste

    SciTech Connect (OSTI)

    Rockhold, Mark L.; Zhang, Z. F.; Meyer, Philip D.; Thomle, Jonathan N.

    2015-02-28

    Current plans for treatment and disposal of immobilized low-activity waste (ILAW) from Hanford’s underground waste storage tanks include vitrification and storage of the glass waste form in a nearsurface disposal facility. This Integrated Disposal Facility (IDF) is located in the 200 East Area of the Hanford Central Plateau. Performance assessment (PA) of the IDF requires numerical modeling of subsurface flow and reactive transport processes over very long periods (thousands of years). The models used to predict facility performance require parameters describing various physical, hydraulic, and transport properties. This report provides updated estimates of physical, hydraulic, and transport properties and parameters for both near- and far-field materials, intended for use in future IDF PA modeling efforts. Previous work on physical and hydraulic property characterization for earlier IDF PA analyses is reviewed and summarized. For near-field materials, portions of this document and parameter estimates are taken from an earlier data package. For far-field materials, a critical review is provided of methodologies used in previous data packages. Alternative methods are described and associated parameters are provided.

  9. Idaho Cold War Waste Removal Advancing as Work on Eighth Area Begins

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

    Danielle Miller, (208) 569-7806 Erik Simpson, (208) 390-9464 For Immediate Release: January 13, 2014 Idaho Cold War Waste Removal Advancing as Work on Eighth Area Begins IDAHO FALLS, ID - The U.S. Department of Energy and Idaho site cleanup contractor CH2M-WG Idaho (CWI) have begun removing Cold War weapons waste at the eighth area of the 97-acre Subsurface Disposal Area (SDA). The Idaho Site contains a total of nine targeted waste areas within the SDA. To date, six retrieval areas have been

  10. Chemically Reactive Working Fluids for the Capture and Transport...

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

    Planar Optical Waveguide Coupler Transformers for High-Power Solar Enegy Collection and Transmission Chemically Reactive Working Fluids Low-Cost Light Weigh Thin Film Solar ...

  11. TRANSPORTATION WORKING GROUP (TWG) MEETING Clark County Government...

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

    Works Tim Murphy, NDEP Irene Navis, Clark County Office of Emergency ManagementYucca Mountain Oversight Scott Page, NDEP Gene Pasinski, Clark County Russ Peacock, White Pine ...

  12. Transportation Issues and Resolutions Compilation of Laboratory Transportation Work Package Reports

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Transportation Team identified the retrievability and subcriticality safety functions to be of primary importance to the transportation of UNF after extended storage and to transportation of high burnup fuel. The tasks performed and described herein address issues related to retrievability and subcriticality; integrity of cladding (embrittled, high burnup cladding, loads applied to cladding during transport), criticality analyses of failed UNF within transport packages, moderator exclusion concepts, stabilization of cladding with canisters for criticality control; and the need for maintaining a detailed inventory of UNF in dry storage as an ongoing activity.

  13. Carlsbad Area Office unveils full-scale model of new WIPP waste transportation cask

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

    Carlsbad Area Office Unveils Full-Scale Model Of New WIPP Waste Transportation Cask CARLSBAD, N.M., February 23, 2000 - The U.S. Department of Energy's (DOE) Carlsbad Area Office today unveiled a full-scale model of its newest waste transportation cask, the RH-72B, during a ceremony at the local DOE offices. "This is another milestone for the Department of Energy," said Dr. Inés Triay, Manager of the Carlsbad Area Office, describing the importance of the new container for those

  14. Chair Report Consultancy Meeting on Nuclear Security Assessment Methodologies (NUSAM) Transport Case Study Working Group

    SciTech Connect (OSTI)

    Shull, Doug

    2015-08-19

    The purpose of the consultancy assignment was to (i) apply the NUSAM assessment methods to hypothetical transport security table top exercise (TTX) analyses and (ii) document its results to working materials of NUSAM case study on transport. A number of working group observations, using the results of TTX methodologies, are noted in the report.

  15. Streamtube Fate and Transport Modeling of the Source Term for the Old Radioactive Waste

    SciTech Connect (OSTI)

    Brewer, K.

    2000-11-16

    The modeling described in this report is an extension of previous fate and transport modeling for the Old Radioactive Waste Burial Ground Corrective Measures Study/Feasibility Study. The purpose of this and the previous modeling is to provide quantitative input to the screening of remedial alternatives for the CMS/FS for this site.

  16. Geochemical factors affecting radionuclide transport through near and far fields at a Low-Level Waste Disposal Site

    SciTech Connect (OSTI)

    Kaplan, D.I.; Seme, R.J.; Piepkho, M.G.

    1995-03-01

    The concentration of low-level waste (LLW) contaminants in groundwater is determined by the amount of contaminant present in the solid waste, rate of release from the waste and surrounding barriers, and a number of geochemical processes including adsorption, desorption, diffusion, precipitation, and dissolution. To accurately predict radionuclide transport through the subsurface, it is essential that the important geochemical processes affecting radionuclide transport be identified and, perhaps more importantly, accurately quantified and described in a mathematically defensible manner.

  17. Comparative study of Waste Isolation Pilot Plant (WIPP) transportation alternatives

    SciTech Connect (OSTI)

    Not Available

    1994-02-01

    WIPP transportation studies in the Final Supplement Environmental Impact Statement for WIPP are the baseline for this report. In an attempt to present the most current analysis, this study incorporates the most relevant data available. The following three transportation options are evaluated for the Disposal Phase, which is assumed to be 20 years: Truck shipments, consisting of a tractor and trailer, with three TRUPACT-IIs or one RH-72B; Regular commercial train shipments consisting of up to three railcars carrying up to 18 TRUPACT-IIs or up to six RH-72Bs; Dedicated train shipments consisting of a locomotive, an idle car, railcars carrying 18 TRUPACT-IIs or six RH-72Bs, another idle car, and a caboose or passenger car with an emergency response specialist. No other cargo is carried. This report includes: A consideration of occupational and public risks and exposures, and other environmental impacts; A consideration of emergency response capabilities; and An extimation of comparative costs.

  18. Building waste management core indicators through Spatial Material Flow Analysis: Net recovery and transport intensity indexes

    SciTech Connect (OSTI)

    Font Vivanco, David; Puig Ventosa, Ignasi; Gabarrell Durany, Xavier

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer Sustainability and proximity principles have a key role in waste management. Black-Right-Pointing-Pointer Core indicators are needed in order to quantify and evaluate them. Black-Right-Pointing-Pointer A systematic, step-by-step approach is developed in this study for their development. Black-Right-Pointing-Pointer Transport may play a significant role in terms of environmental and economic costs. Black-Right-Pointing-Pointer Policy action is required in order to advance in the consecution of these principles. - Abstract: In this paper, the material and spatial characterization of the flows within a municipal solid waste (MSW) management system are combined through a Network-Based Spatial Material Flow Analysis. Using this information, two core indicators are developed for the bio-waste fraction, the Net Recovery Index (NRI) and the Transport Intensity Index (TII), which are aimed at assessing progress towards policy-related sustainable MSW management strategies and objectives. The NRI approaches the capacity of a MSW management system for converting waste into resources through a systematic metabolic approach, whereas the TII addresses efficiency in terms of the transport requirements to manage a specific waste flow throughout the entire MSW management life cycle. Therefore, both indicators could be useful in assessing key MSW management policy strategies, such as the consecution of higher recycling levels (sustainability principle) or the minimization of transport by locating treatment facilities closer to generation sources (proximity principle). To apply this methodological approach, the bio-waste management system of the region of Catalonia (Spain) has been chosen as a case study. Results show the adequacy of both indicators for identifying those points within the system with higher capacity to compromise its environmental, economic and social performance and therefore establishing clear targets for policy

  19. EM Contractor’s Success in Addressing Challenging Waste Leads to More Cleanup Work

    Broader source: Energy.gov [DOE]

    IDAHO FALLS, Idaho – The EM program’s Idaho Site cleanup contractor CH2M-WG Idaho’s (CWI) success last year in treating and packaging 6,000 drums of radioactive and hazardous waste left over from the Cold War weapons program has spawned additional cleanup work for the company.

  20. Operating Experience and Lessons Learned in the Use of Soft-Sided Packaging for Transportation and Disposal of Low Activity Radioactive Waste

    SciTech Connect (OSTI)

    Kapoor, A.; Gordon, S.; Goldston, W.

    2013-07-08

    This paper describes the operating experience and lessons learned at U.S. Department of Energy (DOE) sites as a result of an evaluation of potential trailer contamination and soft-sided packaging integrity issues related to the disposal of low-level and mixed low-level (LLW/MLLW) radioactive waste shipments. Nearly 4.3 million cubic meters of LLW/MLLW will have been generated and disposed of during fiscal year (FY) 2010 to FY 2015either at commercial disposal sites or disposal sites owned by DOE. The LLW/MLLW is packaged in several different types of regulatory compliant packaging and transported via highway or rail to disposal sites safely and efficiently in accordance with federal, state, and local regulations and DOE orders. In 1999, DOE supported the development of LLW containers that are more volumetrically efficient, more cost effective, and easier to use as compared to metal or wooden containers that existed at that time. The DOE Idaho National Engineering and Environmental Laboratory (INEEL), working in conjunction with the plastic industry, tested several types of soft-sided waste packaging systems that meet U.S. Department of Transportation requirements for transport of low specific activity and surface contaminated objects. Since then, soft-sided packaging of various capacities have been used successfully by the decontamination and decommissioning (D&D) projects to package, transport, and dispose D&D wastes throughout the DOE complex. The joint team of experts assembled by the Energy Facility Contractors Group from DOE waste generating sites, DOE and commercial waste disposal facilities, and soft-sided packaging suppliers conducted the review of soft-sided packaging operations and transportation of these packages to the disposal sites. As a result of this evaluation, the team developed several recommendations and best practices to prevent or minimize the recurrences of equipment contamination issues and proper use of soft-sided packaging for transport

  1. Report of the 7th Meeting of the Transport Modeling Working Group

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

    7 th Meeting of the Transport Modeling Working Group May 22 and 23, 2014 The Transport Modeling Working Group (TMWG) met over 1.5 days at the end of May at Lawrence Berkeley National Laboratory. The chosen topics were to discuss multiphase flow with a focus on the diffusion media and the nexus between durability and transport modeling. The format was similar to previous meetings with ample time for discussion led off by a few presentations pertinent to the topic at hand. Both core TMWG

  2. Evaluating Transport and Attenuation of Inorganic Contaminants in the Vadose Zone for Aqueous Waste Disposal Sites

    SciTech Connect (OSTI)

    Truex, Michael J.; Oostrom, Martinus; Tartakovsky, Guzel D.

    2015-09-01

    An approach was developed for evaluating vadose zone transport and attenuation of aqueous wastes containing inorganic (non-volatile) contaminants that were disposed of at the land surface (i.e., directly to the ground in cribs, trenches, tile fields, etc.) and their effect on the underlying groundwater. The approach provides a structured method for estimating transport of contaminants through the vadose zone and the resulting temporal profile of groundwater contaminant concentrations. The intent of the approach is also to provide a means for presenting and explaining the results of the transport analysis in the context of the site-specific waste disposal conditions and site properties, including heterogeneities and other complexities. The document includes considerations related to identifying appropriate monitoring to verify the estimated contaminant transport and associated predictions of groundwater contaminant concentrations. While primarily intended for evaluating contaminant transport under natural attenuation conditions, the approach can also be applied to identify types of, and targets for, mitigation approaches in the vadose zone that would reduce the temporal profile of contaminant concentrations in groundwater, if needed.

  3. Coupling of Nuclear Waste Form Corrosion and Radionuclide Transports in Presence of Relevant Repository Sediments

    SciTech Connect (OSTI)

    Wall, Nathalie A.; Neeway, James J.; Qafoku, Nikolla P.; Ryan, Joseph V.

    2015-09-30

    Assessments of waste form and disposal options start with the degradation of the waste forms and consequent mobilization of radionuclides. Long-term static tests, single-pass flow-through tests, and the pressurized unsaturated flow test are often employed to study the durability of potential waste forms and to help create models that predict their durability throughout the lifespan of the disposal site. These tests involve the corrosion of the material in the presence of various leachants, with different experimental designs yielding desired information about the behavior of the material. Though these tests have proved instrumental in elucidating various mechanisms responsible for material corrosion, the chemical environment to which the material is subject is often not representative of a potential radioactive waste repository where factors such as pH and leachant composition will be controlled by the near-field environment. Near-field materials include, but are not limited to, the original engineered barriers, their resulting corrosion products, backfill materials, and the natural host rock. For an accurate performance assessment of a nuclear waste repository, realistic waste corrosion experimental data ought to be modeled to allow for a better understanding of waste form corrosion mechanisms and the effect of immediate geochemical environment on these mechanisms. Additionally, the migration of radionuclides in the resulting chemical environment during and after waste form corrosion must be quantified and mechanisms responsible for migrations understood. The goal of this research was to understand the mechanisms responsible for waste form corrosion in the presence of relevant repository sediments to allow for accurate radionuclide migration quantifications. The rationale for this work is that a better understanding of waste form corrosion in relevant systems will enable increased reliance on waste form performance in repository environments and potentially

  4. Multiple-tracer tests for contaminant transport process identification in saturated municipal solid waste

    SciTech Connect (OSTI)

    Woodman, N.D. Rees-White, T.C.; Stringfellow, A.M.; Beaven, R.P.; Hudson, A.P.

    2015-04-15

    Highlights: • Multiple tracers were applied to saturated MSW to test dual-porosity properties. • Lithium demonstrated to be non-conservative as a tracer. • 260 mm diameter column too small to test transport properties of MSW. • The classical advection-dispersion mode was rejected due to high dispersivity. • Characteristic diffusion times did not vary with the tracer. - Abstract: Two column tests were performed in conditions emulating vertical flow beneath the leachate table in a biologically active landfill to determine dominant transport mechanisms occurring in landfills. An improved understanding of contaminant transport process in wastes is required for developing better predictions about potential length of the long term aftercare of landfills, currently measured in timescales of centuries. Three tracers (lithium, bromide and deuterium) were used. Lithium did not behave conservatively. Given that lithium has been used extensively for tracing in landfill wastes, the tracer itself and the findings of previous tests which assume that it has behaved conservatively may need revisiting. The smaller column test could not be fitted with continuum models, probably because the volume of waste was below a representative elemental volume. Modelling compared advection-dispersion (AD), dual porosity (DP) and hybrid AD–DP models. Of these models, the DP model was found to be the most suitable. Although there is good evidence to suggest that diffusion is an important transport mechanism, the breakthrough curves of the different tracers did not differ from each other as would be predicted based on the free-water diffusion coefficients. This suggested that solute diffusion in wastes requires further study.

  5. Safety evaluation for packaging transportation of equipment for tank 241-C-106 waste sluicing system

    SciTech Connect (OSTI)

    Calmus, D.B.

    1994-08-25

    A Waste Sluicing System (WSS) is scheduled for installation in nd waste storage tank 241-C-106 (106-C). The WSS will transfer high rating sludge from single shell tank 106-C to double shell waste tank 241-AY-102 (102-AY). Prior to installation of the WSS, a heel pump and a transfer pump will be removed from tank 106-C and an agitator pump will be removed from tank 102-AY. Special flexible receivers will be used to contain the pumps during removal from the tanks. After equipment removal, the flexible receivers will be placed in separate containers (packagings). The packaging and contents (packages) will be transferred from the Tank Farms to the Central Waste Complex (CWC) for interim storage and then to T Plant for evaluation and processing for final disposition. Two sizes of packagings will be provided for transferring the equipment from the Tank Farms to the interim storage facility. The packagings will be designated as the WSSP-1 and WSSP-2 packagings throughout the remainder of this Safety Evaluation for Packaging (SEP). The WSSP-1 packagings will transport the heel and transfer pumps from 106-C and the WSSP-2 packaging will transport the agitator pump from 102-AY. The WSSP-1 and WSSP-2 packagings are similar except for the length.

  6. Waste Management | Department of Energy

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

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

  7. Study on Shielding Requirements for Radioactive Waste Transportation in a Mo-99 Production Plant - 13382

    SciTech Connect (OSTI)

    Melo Rego, Maria Eugenia de; Kazumi Sakata, Solange; Vicente, Roberto; Hiromoto, Goro

    2013-07-01

    Brazil is currently planning to produce {sup 99}Mo from fission of low enriched uranium (LEU) targets. The planned end of irradiation activity of {sup 99}Mo is about 185 TBq (5 kCi) per week to meet the present domestic demand of {sup 99m}Tc generators. The radioactive wastes from the production plant will be transferred to a waste treatment facility at the same site. The total activity of the actinides, fission and activation products present in the wastes can be predicted based on the yields of fission and activation data for the irradiation conditions, such as composition and mass of uranium targets, irradiation time, neutron flux, production schedule, etc., which were in principle already established by the project management. The transportation of the wastes from the production plant to the treatment facility will be done by means of special shielded packages. An assessment of the shielding required for the packages has been done and the results are presented here, aiming at contributing to the design of the waste management facility for the {sup 99}Mo production plant. (authors)

  8. User's manual for the Sandia Waste-Isolation Flow and Transport model (SWIFT).

    SciTech Connect (OSTI)

    Reeves, Mark; Cranwell, Robert M.

    1981-11-01

    This report describes a three-dimensional finite-difference model (SWIFT) which is used to simulate flow and transport processes in geologic media. The model was developed for use by the Nuclear Regulatory Commission in the analysis of deep geologic nuclear waste-disposal facilities. This document, as indicated by the title, is a user's manual and is intended to facilitate the use of the SWIFT simulator. Mathematical equations, submodels, application notes, and a description of the program itself are given herein. In addition, a complete input data guide is given along with several appendices which are helpful in setting up a data-input deck. Computer code SWIFT (Sandia Waste Isolation, Flow and Transport Model) is a fully transient, three-dimensional model which solves the coupled equations for transport in geologic media. The processes considered are: (1) fluid flow; (2) heat transport; (3) dominant-species miscible displacement; and (4) trace-species miscible displacement. The first three processes are coupled via fluid density and viscosity. Together they provide the velocity field on which the fourth process depends.

  9. dfnWorks: A discrete fracture network framework for modeling subsurface flow and transport

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

    Hyman, Jeffrey D.; Karra, Satish; Makedonska, Nataliia; Gable, Carl W.; Painter, Scott L.; Viswanathan, Hari S.

    2015-11-01

    DFNWORKS is a parallelized computational suite to generate three-dimensional discrete fracture networks (DFN) and simulate flow and transport. Developed at Los Alamos National Laboratory over the past five years, it has been used to study flow and transport in fractured media at scales ranging from millimeters to kilometers. The networks are created and meshed using DFNGEN, which combines FRAM (the feature rejection algorithm for meshing) methodology to stochastically generate three-dimensional DFNs with the LaGriT meshing toolbox to create a high-quality computational mesh representation. The representation produces a conforming Delaunay triangulation suitable for high performance computing finite volume solvers in anmore » intrinsically parallel fashion. Flow through the network is simulated in dfnFlow, which utilizes the massively parallel subsurface flow and reactive transport finite volume code PFLOTRAN. A Lagrangian approach to simulating transport through the DFN is adopted within DFNTRANS to determine pathlines and solute transport through the DFN. Example applications of this suite in the areas of nuclear waste repository science, hydraulic fracturing and CO2 sequestration are also included.« less

  10. dfnWorks: A discrete fracture network framework for modeling subsurface flow and transport

    SciTech Connect (OSTI)

    Hyman, Jeffrey D.; Karra, Satish; Makedonska, Nataliia; Gable, Carl W.; Painter, Scott L.; Viswanathan, Hari S.

    2015-11-01

    DFNWORKS is a parallelized computational suite to generate three-dimensional discrete fracture networks (DFN) and simulate flow and transport. Developed at Los Alamos National Laboratory over the past five years, it has been used to study flow and transport in fractured media at scales ranging from millimeters to kilometers. The networks are created and meshed using DFNGEN, which combines FRAM (the feature rejection algorithm for meshing) methodology to stochastically generate three-dimensional DFNs with the LaGriT meshing toolbox to create a high-quality computational mesh representation. The representation produces a conforming Delaunay triangulation suitable for high performance computing finite volume solvers in an intrinsically parallel fashion. Flow through the network is simulated in dfnFlow, which utilizes the massively parallel subsurface flow and reactive transport finite volume code PFLOTRAN. A Lagrangian approach to simulating transport through the DFN is adopted within DFNTRANS to determine pathlines and solute transport through the DFN. Example applications of this suite in the areas of nuclear waste repository science, hydraulic fracturing and CO2 sequestration are also included.

  11. Evaluation of Transportation Vibration Associated with Relocation of Work in Process As Part of KCRIMS

    SciTech Connect (OSTI)

    Hartwig, Troy

    2013-04-01

    During relocation of the Kansas City Plant (KCP) from the site at Bannister Road to the site at Botts Road, work in process (WIP) within a production department must be transported. This report recommends packaging to mitigate vibration levels experienced by products during between-facility transportation. Measurements and analysis demonstrate that this mitigation results in vibration levels less than those experienced by the product during routine production processes within potentially damaging frequency ranges.

  12. Spring 2012 National Transportation Stakeholder Forum Meetings, Tennessee |

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

    Department of Energy 2 National Transportation Stakeholder Forum Meetings, Tennessee Spring 2012 National Transportation Stakeholder Forum Meetings, Tennessee NTSF Registration Website Save The Date! NTSF Spring 2012 Agenda NTSF Agenda Midwestern Radioactive Materials Transportation Committee Agenda Northeast High-Level Radioactive Waste Transportation Task Force Agenda Transuranic Waste Transportation Working Group Agenda Western Governor's Association Agenda NTSF Presentations Session

  13. TRU TeamWorks - a biweekly e-newsletter for the Waste Isolation Pilot Plant (WIPP) team

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

    TRU TeamWorks - a biweekly e-newsletter for the Waste Isolation Pilot Plant (WIPP) team July 28, 2005 Shipments scheduled to arrive 07/31/05 - 08/06/05 21 Hanford - 4 INL - 14 LANL - 2 SRS - 1 (subject to change) 3,783 total shipments received as of 07/26/05 file:///C|/Documents%20and%20Settings/antipom/Desktop/TeamWorks%20Website/index.htm (1 of 3)7/28/2005 8:17:59 AM TRU TeamWorks - a biweekly e-newsletter for the Waste Isolation Pilot Plant (WIPP) team Waste disposed as of 07/26/05 : 501

  14. Comparative transportation risk assessment for borosilicate-glass and ceramic forms for immobilization of SRP Defense waste

    SciTech Connect (OSTI)

    Moyer, R A

    1982-04-01

    It is currently planned to immobilize the SRP high-level nuclear waste in solid form and then ship it from SRP to a federal repository. This report compared transportation operations and risks for SRP high-level waste in a borosilicate glass form and in a ceramic form. Radiological and nonradiological impacts from normal transport and from potential accidents during transit were determined using the Defense Waste Process Facility Environmental Impact Statement (DWPF EIS) as the source of basic data. Applicable regulations and some current regulatory uncertainties are also discussed.

  15. WIPP Facility Work Plan for Solid Waste Management Units and Areas of Concern

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2002-03-05

    This 2002 Facility Work Plan (FWP) has been prepared as required by Module VII, Permit Condition VII.U.3 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit) (New Mexico Environment Department [NMED], 1999a), and incorporates comments from the NMED received on December 6, 2000 (NMED, 2000a). This February 2002 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. The Permittees are evaluating data from previous investigations of the SWMUs and AOCs against the most recent guidance proposed by the NMED. Based on these data, and completion of the August 2001 sampling requested by the NMED, the Permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA processcan be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable

  16. WIPP Facility Work Plan for Solid Waste Management Units and Areas of Concern

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2002-03-05

    his 2002 Facility Work Plan (FWP) has been prepared as required by Module VII,Permit Condition VII.U.3 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit) (New Mexico Environment Department [NMED], 1999a), and incorporates comments from the NMED received onDecember 6, 2000 (NMED, 2000a). This February 2002 FWP describes the program-matic facility-wide approach to future investigations at Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. The Permittees are evaluating data from previous investigations of the SWMUs and AOCs against the mostrecent guidance proposed by the NMED. Based on these data, and completion of the August 2001 sampling requested by the NMED, the Permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA)Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may beused for any SWMU or AOC (NMED, 1998). This accelerated approach is used toreplace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to

  17. Hazardous waste contamination of water resources (Superfund clean-up policy and the Seymour recycling case). Hearings before the Subcommittee on Investigations and Oversight of the Committee on Public Works and Transportation, House of Representatives, Ninety-Eighth Congress, Second Session, March 13, 14, 15, 1984

    SciTech Connect (OSTI)

    Not Available

    1985-01-01

    Nine witnesses testified over three days of hearings on water contamination due to illegal dumping of hazardous wastes and the administration of the Superfund Law to clean up designated sites. The witnesses were asked to evaluate the overall effect of the program and to consider whether Superfund has a positive or negative effect on the development of more environmentally benign technology. A focus for the testimony was on the Seymour waste site. The witnesses included representatives of the aluminum, automobile, chemical, and high technology industries, who were among the 24 industries making a settlement with the Environmental Protection Agency. Additional material submitted for the record by the witnesses and others follows the testimony.

  18. Proceedings of the second FY87 meeting of the National Working Group for Reduction in Transuranic Waste Arisings

    SciTech Connect (OSTI)

    Not Available

    1987-09-01

    The Second FY87 Meeting of the National Working Group for Reduction in Transuranic Waste Arisings (NWGRTWA) was held at the Lawrence Livermore National Laboratory, Tuesday and Wednesday, July 28--29, 1987. The purpose of the meeting was to discuss (1) modeling programs for waste reduction, (2) proposed FY88 and out-year tasks including the SRL Pu incineration, immobilization improvement, erbia coating technology, and (3) improvements in up-stream recovery operations to effect waste reduction. In addition, tours were made of the LLNL Waste Operations, the Laser Fusion (NOVA), and the Magnetic Fusion (MFTF).

  19. Performance Assessment Transport Modeling of Uranium at the Area 5 Radioactive Waste Management Site at the Nevada National Security Site

    SciTech Connect (OSTI)

    NSTec Radioactive Waste

    2010-10-12

    Following is a brief summary of the assumptions that are pertinent to the radioactive isotope transport in the GoldSim Performance Assessment model of the Area 5 Radioactive Waste Management Site, with special emphasis on the water-phase reactive transport of uranium, which includes depleted uranium products.

  20. Deployment at the Savannah River Site of a standardized, modular transportable and connectable hazard category 2 nuclear system for repackaging TRU waste

    SciTech Connect (OSTI)

    Lussiez, G.; Hickman, S.; Anast, K. R.; Oliver, W. B.

    2004-01-01

    This paper describes the conception, design, fabrication and deployment of a modular, transportable, connectable Category 2 nuclear system deployed at the Savannah River site to be used for characterizing and repackaging Transuranic Waste destined for the Waste Isolation Pilot Plant (WIPP). A standardized Nuclear Category 2 and Performance Category 2 envelope called a 'Nuclear Transportainer' was conceived and designed that provides a safety envelope for nuclear operations. The Nuclear Transportainer can be outfitted with equipment that performs functions necessary to meet mission objectives, in this case repackaging waste for shipment to WIPP. Once outfitted with process and ventilation systems the Nuclear Transportainer is a Modular Unit (MU). Each MU is connectable to other MUS - nuclear or non-nuclear - allowing for multiple functions, command & control, or increasing capacity. The design took advantage of work already in-progress at Los Alamos National Laboratory (LANL) for a similar system to be deployed at LANL's Technical Area 54.

  1. Analysis of human factors effects on the safety of transporting radioactive waste materials: Technical report

    SciTech Connect (OSTI)

    Abkowitz, M.D.; Abkowitz, S.B.; Lepofsky, M.

    1989-04-01

    This report examines the extent of human factors effects on the safety of transporting radioactive waste materials. It is seen principally as a scoping effort, to establish whether there is a need for DOE to undertake a more formal approach to studying human factors in radioactive waste transport, and if so, logical directions for that program to follow. Human factors effects are evaluated on driving and loading/transfer operations only. Particular emphasis is placed on the driving function, examining the relationship between human error and safety as it relates to the impairment of driver performance. Although multi-modal in focus, the widespread availability of data and previous literature on truck operations resulted in a primary study focus on the trucking mode from the standpoint of policy development. In addition to the analysis of human factors accident statistics, the report provides relevant background material on several policies that have been instituted or are under consideration, directed at improving human reliability in the transport sector. On the basis of reported findings, preliminary policy areas are identified. 71 refs., 26 figs., 5 tabs.

  2. WIPP Transportation

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

    Transuranic Waste Transportation Container Documents Documents related to transuranic waste containers and packages. CBFO Tribal Program Information about WIPP shipments across tribal lands. Transportation Centralized Procurement Program - The Centralized Procurement Program provides a common method to procure standard items used in the packaging and handling of transuranic wasted destined for WIPP. Transuranic Waste Transportation Routes - A map showing transuranic waste generator sites and

  3. Investigating the effect of compression on solute transport through degrading municipal solid waste

    SciTech Connect (OSTI)

    Woodman, N.D. Rees-White, T.C.; Stringfellow, A.M.; Beaven, R.P.; Hudson, A.P.

    2014-11-15

    Highlights: • The influence of compression on MSW flushing was evaluated using 13 tracer tests. • Compression has little effect on solute diffusion times in MSW. • Lithium tracer was conservative in non-degrading waste but not in degrading waste. • Bromide tracer was conservative, but deuterium was not. - Abstract: The effect of applied compression on the nature of liquid flow and hence the movement of contaminants within municipal solid waste was examined by means of thirteen tracer tests conducted on five separate waste samples. The conservative nature of bromide, lithium and deuterium tracers was evaluated and linked to the presence of degradation in the sample. Lithium and deuterium tracers were non-conservative in the presence of degradation, whereas the bromide remained effectively conservative under all conditions. Solute diffusion times into and out of less mobile blocks of waste were compared for each test under the assumption of dominantly dual-porosity flow. Despite the fact that hydraulic conductivity changed strongly with applied stress, the block diffusion times were found to be much less sensitive to compression. A simple conceptual model, whereby flow is dominated by sub-parallel low permeability obstructions which define predominantly horizontally aligned less mobile zones, is able to explain this result. Compression tends to narrow the gap between the obstructions, but not significantly alter the horizontal length scale. Irrespective of knowledge of the true flow pattern, these results show that simple models of solute flushing from landfill which do not include depth dependent changes in solute transport parameters are justified.

  4. Transportation safety training

    SciTech Connect (OSTI)

    Jones, E.

    1990-01-01

    Over the past 25 years extensive federal legislation involving the handling and transport of hazardous materials/waste has been passed that has resulted in numerous overlapping regulations administered and enforced by different federal agencies. The handling and transport of hazardous materials/waste involves a significant number of workers who are subject to a varying degree of risk should an accident occur during handling or transport. Effective transportation training can help workers address these risks and mitigate them, and at the same time enable ORNL to comply with the federal regulations concerning the transport of hazardous materials/waste. This presentation will outline how the Environmental and Health Protection Division's Technical Resources and Training Section at the Oak Ridge National Laboratory, working with transportation and waste disposal personnel, have developed and implemented a comprehensive transportation safety training program to meet the needs of our workers while satisfying appropriate federal regulations. 8 refs., 3 tabs.

  5. Excess Weapons Plutonium Disposition: Plutonium Packaging, Storage and Transportation and Waste Treatment, Storage and Disposal Activities

    SciTech Connect (OSTI)

    Jardine, L J; Borisov, G B

    2004-07-21

    A fifth annual Excess Weapons Plutonium Disposition meeting organized by Lawrence Livermore National Laboratory (LLNL) was held February 16-18, 2004, at the State Education Center (SEC), 4 Aerodromnya Drive, St. Petersburg, Russia. The meeting discussed Excess Weapons Plutonium Disposition topics for which LLNL has the US Technical Lead Organization responsibilities. The technical areas discussed included Radioactive Waste Treatment, Storage, and Disposal, Plutonium Oxide and Plutonium Metal Packaging, Storage and Transportation and Spent Fuel Packaging, Storage and Transportation. The meeting was conducted with a conference format using technical presentations of papers with simultaneous translation into English and Russian. There were 46 Russian attendees from 14 different Russian organizations and six non-Russian attendees, four from the US and two from France. Forty technical presentations were made. The meeting agenda is given in Appendix B and the attendance list is in Appendix C.

  6. Hazardous waste contamination of water resources (Superfund clean-up policy and the Seymour recycling case). Hearing before the Subcommittee on Investigations and Oversight of the Committee on Public Works and Transportation, House of Representatives, Ninety-Eighth Congress, First Session, December 20, 1983

    SciTech Connect (OSTI)

    Not Available

    1985-01-01

    Representatives of the Environmental Protection Agency in charge of enforcing waste programs and the Department of Justice testified at a hearing on the Seymour, Indiana recycling center, which has become a toxic waste dump. The committee's purpose was to determine how the situation developed, why the federal government was slow to litigate against parties in the case who did not settle, and why those who did settle were released without further liability. The ultimate objective is to assure adequate resources to address ground water problems through the Superfund program and to avoid similar situations in the future. The witnesses described their role in the enforcement procedure. Material received from witnesses and other interested parties for the record follows their testimony.

  7. Greater-than-Class C low-level radioactive waste transportation regulations and requirements study. National Low-Level Waste Management Program

    SciTech Connect (OSTI)

    Tyacke, M.; Schmitt, R.

    1993-07-01

    The purpose of this report is to identify the regulations and requirements for transporting greater-than-Class C (GTCC) low-level radioactive waste (LLW) and to identify planning activities that need to be accomplished in preparation for transporting GTCC LLW. The regulations and requirements for transporting hazardous materials, of which GTCC LLW is included, are complex and include several Federal agencies, state and local governments, and Indian tribes. This report is divided into five sections and three appendices. Section 1 introduces the report. Section 2 identifies and discusses the transportation regulations and requirements. The regulations and requirements are divided into Federal, state, local government, and Indian tribes subsections. This report does not identify the regulations or requirements of specific state, local government, and Indian tribes, since the storage, treatment, and disposal facility locations and transportation routes have not been specifically identified. Section 3 identifies the planning needed to ensure that all transportation activities are in compliance with the regulations and requirements. It is divided into (a) transportation packaging; (b) transportation operations; (c) system safety and risk analysis, (d) route selection; (e) emergency preparedness and response; and (f) safeguards and security. This section does not provide actual planning since the details of the Department of Energy (DOE) GTCC LLW Program have not been finalized, e.g., waste characterization and quantity, storage, treatment and disposal facility locations, and acceptance criteria. Sections 4 and 5 provide conclusions and referenced documents, respectively.

  8. Information basis for developing comprehensive waste management system-US-Japan joint nuclear energy action plan waste management working group phase I report.

    SciTech Connect (OSTI)

    Nutt, M.; Nuclear Engineering Division

    2010-05-25

    The activity of Phase I of the Waste Management Working Group under the United States - Japan Joint Nuclear Energy Action Plan started in 2007. The US-Japan JNEAP is a bilateral collaborative framework to support the global implementation of safe, secure, and sustainable, nuclear fuel cycles (referred to in this document as fuel cycles). The Waste Management Working Group was established by strong interest of both parties, which arise from the recognition that development and optimization of waste management and disposal system(s) are central issues of the present and future nuclear fuel cycles. This report summarizes the activity of the Waste Management Working Group that focused on consolidation of the existing technical basis between the U.S. and Japan and the joint development of a plan for future collaborative activities. Firstly, the political/regulatory frameworks related to nuclear fuel cycles in both countries were reviewed. The various advanced fuel cycle scenarios that have been considered in both countries were then surveyed and summarized. The working group established the working reference scenario for the future cooperative activity that corresponds to a fuel cycle scenario being considered both in Japan and the U.S. This working scenario involves transitioning from a once-through fuel cycle utilizing light water reactors to a one-pass uranium-plutonium fuel recycle in light water reactors to a combination of light water reactors and fast reactors with plutonium, uranium, and minor actinide recycle, ultimately concluding with multiple recycle passes primarily using fast reactors. Considering the scenario, current and future expected waste streams, treatment and inventory were discussed, and the relevant information was summarized. Second, the waste management/disposal system optimization was discussed. Repository system concepts were reviewed, repository design concepts for the various classifications of nuclear waste were summarized, and the factors

  9. Chemical Engineering Division fuel cycle programs. Quarterly progress report, April-June 1979. [Pyrochemical/dry processing; waste encapsulation in metal; transport in geologic media

    SciTech Connect (OSTI)

    Steindler, M.J.; Ader, M.; Barletta, R.E.

    1980-09-01

    For pyrochemical and dry processing materials development included exposure to molten metal and salt of Mo-0.5% Ti-0.07% Ti-0.01% C, Mo-30% W, SiC, Si/sub 2/ON/sub 2/, ZrB/sub 2/-SiC, MgAl/sub 2/O/sub 4/, Al/sub 2/O/sub 3/, AlN, HfB/sub 2/, Y/sub 2/O/sub 3/, BeO, Si/sub 3/N/sub 4/, nickel nitrate-infiltrated W, W-coated Mo, and W-metallized alumina-yttria. Work on Th-U salt transport processing included solubility of Th in liquid Cd, defining the Cd-Th and Cd-Mg-Th phase diagrams, ThO/sub 2/ reduction experiments, and electrolysis of CaO in molten salt. Work on pyrochemical processes and associated hardware for coprocessing U and Pu in spent FBR fuels included a second-generation computer model of the transport process, turntable transport process design, work on the U-Cu-Mg system, and U and Pu distribution coefficients between molten salt and metal. Refractory metal vessels are being service-life tested. The chloride volatility processing of Th-based fuel was evaluated for its proliferation resistance, and a preliminary ternary phase diagram for the Zn-U-Pu system was computed. Material characterization and process analysis were conducted on the Exportable Pyrochemical process (Pyro-Civex process). Literature data on oxidation of fissile metals to oxides were reviewed. Work was done on chemical bases for the reprocessing of actinide oxides in molten salts. Flowsheets are being developed for the processing of fuel in molten tin. Work on encapsulation of solidified radioactive waste in metal matrix included studies of leach rate of crystalline waste materials and of the impact resistance of metal-matrix waste forms. In work on the transport properties of nuclear waste in geologic media, adsorption of Sr on oolitic limestone was studied, as well as the migration of Cs in basalt. Fitting of data on the adsorption of iodate by hematite to a mathematical model was attempted.

  10. Assessing recycling versus incineration of key materials in municipal waste: The importance of efficient energy recovery and transport distances

    SciTech Connect (OSTI)

    Merrild, Hanna; Larsen, Anna W.; Christensen, Thomas H.

    2012-05-15

    Highlights: Black-Right-Pointing-Pointer We model the environmental impact of recycling and incineration of household waste. Black-Right-Pointing-Pointer Recycling of paper, glass, steel and aluminium is better than incineration. Black-Right-Pointing-Pointer Recycling and incineration of cardboard and plastic can be equally good alternatives. Black-Right-Pointing-Pointer Recyclables can be transported long distances and still have environmental benefits. Black-Right-Pointing-Pointer Paper has a higher environmental benefit than recyclables found in smaller amounts. - Abstract: Recycling of materials from municipal solid waste is commonly considered to be superior to any other waste treatment alternative. For the material fractions with a significant energy content this might not be the case if the treatment alternative is a waste-to-energy plant with high energy recovery rates. The environmental impacts from recycling and from incineration of six material fractions in household waste have been compared through life cycle assessment assuming high-performance technologies for material recycling as well as for waste incineration. The results showed that there are environmental benefits when recycling paper, glass, steel and aluminium instead of incinerating it. For cardboard and plastic the results were more unclear, depending on the level of energy recovery at the incineration plant, the system boundaries chosen and which impact category was in focus. Further, the environmental impact potentials from collection, pre-treatment and transport was compared to the environmental benefit from recycling and this showed that with the right means of transport, recyclables can in most cases be transported long distances. However, the results also showed that recycling of some of the material fractions can only contribute marginally in improving the overall waste management system taking into consideration their limited content in average Danish household waste.

  11. Annual Transportation Report for Radioactive Waste Shipments to and from the Nevada Test Site, Fiscal Year 2009

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2010-02-01

    In February 1997, the U.S. Department of Energy (DOE), Nevada Operations Office (now known as the Nevada Site Office) issued the Mitigation Action Plan which addressed potential impacts described in the Final Environmental Impact Statement for the Nevada Test Site and Off-Site Locations in the State of Nevada (DOE/EIS 0243). The DOE, Nevada Operations Office committed to several actions, including the preparation of an annual report, which summarizes waste shipments to and from the Nevada Test Site (NTS) Radioactive Waste Management Site (RWMS) at Area 5 and Area 3. Since 2006, the Area 3 RWMS has been in cold stand-by. This document satisfies requirements regarding low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) transported to and from the NTS during FY 2009. In addition, this document provides shipment, volume, and route information on transuranic (TRU) waste shipped from the NTS to the Idaho National Laboratory, near Idaho Falls, Idaho.

  12. PRESTO-II: a low-level waste environmental transport and risk assessment code

    SciTech Connect (OSTI)

    Fields, D.E.; Emerson, C.J.; Chester, R.O.; Little, C.A.; Hiromoto, G.

    1986-04-01

    PRESTO-II (Prediction of Radiation Effects from Shallow Trench Operations) is a computer code designed for the evaluation of possible health effects from shallow-land and, waste-disposal trenches. The model is intended to serve as a non-site-specific screening model for assessing radionuclide transport, ensuing exposure, and health impacts to a static local population for a 1000-year period following the end of disposal operations. Human exposure scenarios considered include normal releases (including leaching and operational spillage), human intrusion, and limited site farming or reclamation. Pathways and processes of transit from the trench to an individual or population include ground-water transport, overland flow, erosion, surface water dilution, suspension, atmospheric transport, deposition, inhalation, external exposure, and ingestion of contaminated beef, milk, crops, and water. Both population doses and individual doses, as well as doses to the intruder and farmer, may be calculated. Cumulative health effects in terms of cancer deaths are calculated for the population over the 1000-year period using a life-table approach. Data are included for three example sites: Barnwell, South Carolina; Beatty, Nevada; and West Valley, New York. A code listing and example input for each of the three sites are included in the appendices to this report.

  13. Working Group 7.0 Environmental Transport and Health Effects, Chernobyl Studies Project. Progress report, October 1994 -- March 1995

    SciTech Connect (OSTI)

    Anspaugh, L.R.; Hendrickson, S.M.

    1995-06-01

    This document presents the details from the working group 7.0 Chernobyl Studies Project. This working group looked at the environmental transport and health effects from the fallout due to the meltdown of Chernobylsk-4 reactor. Topics include: hydrological transport; chromosome painting dosimetry; EPR, TL and OSL dosimetry; stochastic effects; thyroid studies; and leukemia studies.

  14. Contaminant transport in unconfined aquifer, input to low-level tank waste interim performance assessment

    SciTech Connect (OSTI)

    Lu, A.H., Westinghouse Hanford

    1996-08-14

    This report describes briefly the Hanford sitewide groundwater model and its application to the Low-Level Tank Waste Disposal (LLTWD) interim Performance Assessment (PA). The Well Intercept Factor (WIF) or dilution factor from a given areal flux entering the aquifer released from the LLTWD site are calculated for base case and various sensitivity cases. In conjunction with the calculation for released fluxes through vadose zone transport,the dose at the compliance point can be obtained by a simple multiplication. The relative dose contribution from the upstream sources was also calculated and presented in the appendix for an equal areal flux at the LLTWD site. The results provide input for management decisions on remediation action needed for reduction of the released fluxes from the upstream facilities to the allowed level to meet the required dose criteria.

  15. Design and Fabrication of a Transportable Vitrification System for Mixed Waste Processing

    SciTech Connect (OSTI)

    Whitehouse, J.C.; Jantzen, C.M.; Van Ryn, F.R.; Davis, D.H.

    1995-04-06

    The stabilization and disposal of mixed wastes, which contain both hazardous and radioactive materials, is a significant waste management challenge to the DOE complex.

  16. GHG emission factors developed for the collection, transport and landfilling of municipal waste in South African municipalities

    SciTech Connect (OSTI)

    Friedrich, Elena; Trois, Cristina

    2013-04-15

    Highlights: ► An average GHG emission factor for the collection and transport of municipal solid waste in South Africa is calculated. ► A range of GHG emission factors for different types of landfills (including dumps) in South Africa are calculated. ► These factors are compared internationally and their implications for South Africa and developing countries are discussed . ► Areas for new research are highlighted. - Abstract: Greenhouse gas (GHG) emission factors are used with increased frequency for the accounting and reporting of GHG from waste management. However, these factors have been calculated for developed countries of the Northern Hemisphere and are lacking for developing countries. This paper shows how such factors have been developed for the collection, transport and landfilling of municipal waste in South Africa. As such it presents a model on how international results and methodology can be adapted and used to calculate country-specific GHG emission factors from waste. For the collection and transport of municipal waste in South Africa, the average diesel consumption is around 5 dm{sup 3} (litres) per tonne of wet waste and the associated GHG emissions are about 15 kg CO{sub 2} equivalents (CO{sub 2} e). Depending on the type of landfill, the GHG emissions from the landfilling of waste have been calculated to range from −145 to 1016 kg CO{sub 2} e per tonne of wet waste, when taking into account carbon storage, and from 441 to 2532 kg CO{sub 2} e per tonne of wet waste, when carbon storage is left out. The highest emission factor per unit of wet waste is for landfill sites without landfill gas collection and these are the dominant waste disposal facilities in South Africa. However, cash strapped municipalities in Africa and the developing world will not be able to significantly upgrade these sites and reduce their GHG burdens if there is no equivalent replacement of the Clean Development Mechanism (CDM) resulting from the Kyoto agreement

  17. Preparation of a technology development roadmap for the Accelerator Transmutation of Waste (ATW) System : report of the ATW separations technologies and waste forms technical working group.

    SciTech Connect (OSTI)

    Collins, E.; Duguid, J.; Henry, R.; Karell, E.; Laidler, J.; McDeavitt, S.; Thompson, M.; Toth, M.; Williamson, M.; Willit, J.

    1999-08-12

    In response to a Congressional mandate to prepare a roadmap for the development of Accelerator Transmutation of Waste (ATW) technology, a Technical Working Group comprised of members from various DOE laboratories was convened in March 1999 for the purpose of preparing that part of the technology development roadmap dealing with the separation of certain radionuclides for transmutation and the disposal of residual radioactive wastes from these partitioning operations. The Technical Working Group for ATW Separations Technologies and Waste Forms completed its work in June 1999, having carefully considered the technology options available. A baseline process flowsheet and backup process were identified for initial emphasis in a future research, development and demonstration program. The baseline process combines aqueous and pyrochemical processes to permit the efficient separation of the uranium, technetium, iodine and transuranic elements from the light water reactor (LWR) fuel in the head-end step. The backup process is an all- pyrochemical system. In conjunction with the aqueous process, the baseline flowsheet includes a pyrochemical process to prepare the transuranic material for fabrication of the ATW fuel assemblies. For the internal ATW fuel cycle the baseline process specifies another pyrochemical process to extract the transuranic elements, Tc and 1 from the ATW fuel. Fission products not separated for transmutation and trace amounts of actinide elements would be directed to two high-level waste forms, one a zirconium-based alloy and the other a glass/sodalite composite. Baseline cost and schedule estimates are provided for a RD&D program that would provide a full-scale demonstration of the complete separations and waste production flowsheet within 20 years.

  18. Tank waste remediation system fiscal year 1998 multi-year work plan WBS 1.1

    SciTech Connect (OSTI)

    Lenseigne, D. L.

    1997-09-15

    The TWRS Project Mission is to manage and immobilize for disposal the Hanford Site radioactive tank waste and cesium (Cs)/strontium (Sr) capsules in a safe, environmentally sound, and cost-effective manner. The scope includes all activities needed to (1) resolve safety issues; (2) operate, maintain, and upgrade the tank farms and supporting infrastructure; (3) characterize, retrieve, pretreat, and immobilize the waste for disposal and tank farm closure; and (4) use waste minimization and evaporation to manage tank waste volumes to ensure that the tank capacities of existing DSTs are not exceeded. The TWRS Project is responsible for closure of assigned operable units and D&D of TWRS facilities.

  19. Phase 1 RCRA Facility Investigation & Corrective Measures Study Work Plan for Single Shell Tank (SST) Waste Management Areas

    SciTech Connect (OSTI)

    MCCARTHY, M.M.

    1999-08-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) Corrective Action Program (RCAP) for single-shell tank (SST) farms at the US. Department of Energy's (DOE'S) Hanford Site. The DOE Office of River Protection (ORP) initiated the RCAP to address the impacts of past and potential future tank waste releases to the environment. This work plan defines RCAP activities for the four SST waste management areas (WMAs) at which releases have contaminated groundwater. Recognizing the potential need for future RCAP activities beyond those specified in this master work plan, DOE has designated the currently planned activities as ''Phase 1.'' If a second phase of activities is needed for the WMAs addressed in Phase 1, or if releases are detected at other SST WMAs, this master work plan will be updated accordingly.

  20. Statements of work for FY 1996 to 2001 for the Hanford Low-Level Tank Waste Performance Assessment Project

    SciTech Connect (OSTI)

    Mann, F.M.

    1995-06-07

    The statements of work for each activity and task of the Hanford Low-Level Tank Waste Performance Assessment project are given for the fiscal years 1996 through 2001. The end product of this program is approval of a final performance assessment by the Department of Energy in the year 2000.

  1. Phase 1 RCRA Facility Investigation and Corrective Measures Study Work Plan for Single Shell Tank Waste Management Areas

    SciTech Connect (OSTI)

    ROGERS, P.M.

    2000-06-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) for single-shell tank (SST) farms at the Hanford Site. Evidence indicates that releases at four of the seven SST waste management areas have impacted.

  2. Transuranic Waste Tabletop | Department of Energy

    Office of Environmental Management (EM)

    Transuranic Waste Tabletop Transuranic Waste Tabletop OBJECTIVES Given a simulated radioactive materials transportation accident, applicable procedures, and map references, demonstrate through participatory discussion a working knowledge of the following emergency response and concept of operations elements: „ Concept of operations for the emergency response to a radioactive materials transportation accident, including the Unified Incident Command System utilized in the field. „ Initial and

  3. An integrated systems approach to remote retrieval of buried transuranic waste using a telerobotic transport vehicle, innovative end effector, and remote excavator

    SciTech Connect (OSTI)

    Smith, A.M.; Rice, P.; Hyde, R.; Peterson, R.

    1995-02-01

    Between 1952 and 1970, over two million cubic feet of transuranic mixed waste was buried in shallow pits and trenches in the Subsurface Disposal Area at the Idaho National Engineering Laboratory Radioactive Waste Management Complex. Commingled with this two million cubic feet of waste is up to 10 million cubic feet of fill soil. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. The main contaminants are micron-sized particles of plutonium and americium oxides, chlorides, and hydroxides. Retrieval, treatment, and disposal is one of the options being considered for the waste. This report describes the results of a field demonstration conducted to evaluate technologies for excavating, and transporting buried transuranic wastes at the INEL, and other hazardous or radioactive waste sites throughout the US Department of Energy complex. The full-scale demonstration, conduced at RAHCO Internationals facilities in Spokane, Washington, in the summer of 1994, evaluated equipment performance and techniques for digging, dumping, and transporting buried waste. Three technologies were evaluated in the demonstration: an Innovative End Effector for dust free dumping, a Telerobotic Transport Vehicle to convey retrieved waste from the digface, and a Remote Operated Excavator to deploy the Innovative End Effector and perform waste retrieval operations. Data were gathered and analyzed to evaluate retrieval performance parameters such as retrieval rates, transportation rates, human factors, and the equipment`s capability to control contamination spread.

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

    SciTech Connect (OSTI)

    Kim, C.H.; Jung, S.

    1997-12-31

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

  5. Small Business Awarded Contract for Recovery Act Work at DOE Waste Facility

    Broader source: Energy.gov [DOE]

    Louisiana small business to provide geosynthetic materials and installation services for expansion of the Department of Energy’s Environmental Management Waste Management Facility (EMWMF) on the Oak Ridge Reservation.

  6. Extended Development Work to Validate a HLW Calcine Waste Form via INL's Cold Crucible Induction Melter

    SciTech Connect (OSTI)

    James A. King; Vince Maio

    2011-09-01

    To accomplish calcine treatment objectives, the Idaho Clean-up Project contractor, CWI, has chosen to immobilize the calcine in a glass-ceramic via the use of a Hot-Isostatic-Press (HIP); a treatment selection formally documented in a 2010 Record of Decision (ROD). Even though the HIP process may prove suitable for the calcine as specified in the ROD and validated in a number of past value engineering sessions, DOE is evaluating back-up treatment methods for the calcine as a result of the technical, schedule, and cost risk associated with the HIPing process. Consequently DOE HQ has requested DOE ID to make INL's bench-scale cold-crucible induction melter (CCIM) available for investigating its viability as a process alternate to calcine treatment. The waste form is the key component of immobilization of radioactive waste. Providing a solid, stable, and durable material that can be easily be stored is the rationale for immobilization of radioactive waste material in glass, ceramic, or glass-ceramics. Ceramic waste forms offer an alternative to traditional borosilicate glass waste forms. Ceramics can usually accommodate higher waste loadings than borosilicate glass, leading to smaller intermediate and long-term storage facilities. Many ceramic phases are known to possess superior chemical durability as compared to borosilicate glass. However, ceramics are generally multiphase systems containing many minor phase that make characterization and prediction of performance within a repository challenging. Additionally, the technologies employed in ceramic manufacture are typically more complex and expensive. Thus, many have proposed using glass-ceramics as compromise between in the more inexpensive, easier to characterize glass waste forms and the more durable ceramic waste forms. Glass-ceramics have several advantages over traditional borosilicate glasses as a waste form. Borosilicate glasses can inadvertently devitrify, leading to a less durable product that could crack

  7. Waste Guide

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

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

  8. EBS Radionuclide Transport Abstraction

    SciTech Connect (OSTI)

    J. Prouty

    2006-07-14

    The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment (TSPA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport model considers advective transport and diffusive transport

  9. Superfund at work: Hazardous waste cleanup efforts nationwide, Spring 1993 (Powersville site profile, Peach County, Georgia)

    SciTech Connect (OSTI)

    Not Available

    1993-01-01

    The US Environmental Protection Agency (EPA) encountered much more than a municipal landfill at the Powersville site in Peach County, Georgia. Contamination from improperly dumped hazardous wastes and pesticides tainted an old quarry used for household garbage. Chemicals migrating into area ground water threatened local drinking water supplies. To address these issues, EPA's Superfund program designed a cleanup strategy that included: negotiating with the county and chemical companies to contain the hazardous wastes on site underneath a protective cover; investigating reports of drinking water contamination and extending municipal water lines to affected residents; and conducting a tailored community relations program to inform and educate residents about the site.

  10. Transportation and packaging headquarters support 1997 multi-year work plan WBS 8.1

    SciTech Connect (OSTI)

    Chapman, T.J., Westinghouse Hanford

    1996-08-01

    To develop and implement baseline and state-of-the-art transportation and packaging resources for DOE, and its support contractors. These resources include effective strategies, tools and techniques, packaging and transportation systems, operational methods, policy and guidance focused at providing safety,efficient, regulatory compliant and cost-effective materials transportation.

  11. Interim remedial action work plan for the cesium plots at Waste Area Grouping 13 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Not Available

    1993-07-01

    This remedial action work plan (RAWP) is issued under the Federal Facility Agreement to provide a basic approach for implementing the interim remedial action (IRA) described in Interim Record of Decision for the Oak Ridge National Laboratory Waste Area Grouping 13 Cesium Plots, Oak Ridge, Tennessee. This RAWP summarizes the interim record of decision (IROD) requirements and establishes the strategy for the implementation of the field activities. As documented in the IROD document, the primary goal of this action is to reduce the risk to human health and the environment resulting from current elevated levels of gamma radiation on the site and at areas accessible to the public adjacent to the site. The major steps of this IRA are to: Excavate cesium-contaminated soil; place the excavated soils in containers and transport to Waste Area Grouping (WAG) 6; and backfill excavated plots with clean fill materials. The actual remedial action will be performed by Department of Energy prime contractor, MK-Ferguson of Oak Ridge Company. Remediation of the cesium plots will require approximately 60 days to complete. During this time, all activities will be performed according to this RAWP and the applicable specifications, plans, and procedures referred to in this document. The IRA on WAG 13 will prevent a known source of cesium-contaminated soil from producing elevated levels of gamma radiation in areas accessible to the public, eliminate sources of contamination to the environment, and reduce the risks associated with surveillance and maintenance of the WAG 13 site.

  12. Coupled Model for Heat and Water Transport in a High Level Waste Repository in Salt

    Broader source: Energy.gov [DOE]

    This report summarizes efforts to simulate coupled thermal-hydrological-chemical (THC) processes occurring within a generic hypothetical high-level waste (HLW) repository in bedded salt.

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

    SciTech Connect (OSTI)

    Taylor, Dean Dalton; Barnes, Charles Marshall

    2002-09-01

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

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

    SciTech Connect (OSTI)

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

    2002-09-09

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

  15. Waste Preparation and Transport Chemistry: Results of the FY 2000 Studies

    SciTech Connect (OSTI)

    Hunt, R.D.

    2001-02-06

    Problems with pipeline plugs at Hanford have occurred throughout its tank farm system. Most cross-site transfer lines at Hanford are no longer functional due to these plugs. Waste transfers frequently led to partial line plugs, resulting in substantial amounts of water being added to the tank system in an attempt to free the lines. In response to these plugs, the Hanford tank farm developed waste acceptance criteria that a waste must pass before it can be transferred (Shekarriz et al., 1997). The criteria, which include physical properties such as viscosity, specific gravity, and percent solids, are based primarily on past operational experience. Unfortunately, the chemistry of the waste solutions was not included in the criteria even though the tank farm operators are fully aware of its importance. Pipeline plugs have also occurred during relatively short waste transfers at Hanford. In FY 2000, the effort to saltwell pump 50,000 gal of filtered waste from tank U-103 to tank SY-102 was delayed for several weeks due to a plugged pipeline. Attempts to locate the plug(s) determined that it had occurred in the 02-A flex and that other plugs were possible in each of the SY-farm flexes. Modifications such as larger flex jumpers and additional heat tracing were made to the transfer system. The plug was probably attributable to a reduction in the temperature of the waste in the pipeline. The waste in tank U-103 was approximately 30 C prior to the transfer. During tests on actual waste from tank U-103 (Herting, 1999), trisodium phosphate solids were observed at temperatures as high as 20 C after a 50% dilution with water. Therefore, the following precautions (Herting, 1999) were recommended during the saltwell pumping of tank U-103. First, the tank waste should not be heated prior to the transfer. Second, the waste should not be permitted to cool during the transfer. Third, the waste should be kept moving during the transfer. A previous Tanks Focus Area (TFA) study (Hunt et

  16. Work plan for the identification of techniques for in-situ sensing of layering/interfaces of Hanford high level waste tank

    SciTech Connect (OSTI)

    Vargo, G.F. Jr.

    1995-06-16

    The purpose of this work scope is to identify a specific potential technology/device/instrument/ideas that would provide the tank waste data. A method is needed for identifying layering and physical state within the large waste tanks at the Hanford site in Washington State. These interfaces and state changes can adversely impact sampling and characterization activities.

  17. Supplemental information related to risk assessment for the off-site transportation of low-level mixed waste for the U.S. Department of Energy waste management programmatic environmental impact statement

    SciTech Connect (OSTI)

    Monette, F.A.; Biwer, B.M.; LePoire, D.J.; Lazaro, M.A.; Antonopoulos, A.A.; Hartmann, H.M.; Policastro, A.J.; Chen, S.Y.

    1996-12-01

    This report provides supplemental information to support the human health risk assessment conducted for the transportation of low-level mixed waste (LLMW) in support of the US Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS). The assessment considers both the radioactive and chemical hazards associated with LLMW transportation. Detailed descriptions of the transportation health risk assessment methods and results of the assessment are presented in Appendix E of the WM PEIS. This report presents additional information that is not included in Appendix E but that was needed to conduct the transportation risk assessment for Waste Management (WM) LLMW. Included are definitions of the LLMW alternatives considered in the WM PEIS; data related to the inventory and to the physical, chemical, and radiological characteristics of WM LLMW; an overview of the risk assessment methods; and detailed results of the assessment for each WM LLMW case considered.

  18. ASSESSING EXPOSURE TO THE PUBLIC FROM LOW LEVEL RADIOACTIVE WASTE (LLW) TRANSPORTATION TO THE NEVADA TEST SITE.

    SciTech Connect (OSTI)

    Miller, J.J.; Campbell, S.; Church, B.W.; Shafer, D. S.; Gillespie, D.; Sedano, S.; Cebe, J.J.

    2003-02-27

    The United States (U.S.) Department of Energy (DOE) Nevada Test Site (NTS) is one of two regional sites where low-level radioactive waste (LLW) from approved DOE and U.S. DOD generators across the United States is disposed. In federal fiscal year (FY) 2002, over 57,000 cubic meters of waste was transported to and disposed at the NTS. DOE and U.S. Department of Transportation (DOT) regulations ensure that radiation exposure from truck shipments to members of the public is negligible. Nevertheless, particularly in rural communities along transportation routes in Utah and Nevada, there is perceived risk from members of the public about incremental exposure from LLW trucks, especially when ''Main Street'' and the LLW transportation route are the same. To better quantify the exposure to gamma radiation, a stationary monitoring array of four pressurized ion chambers (PICs) have been set up in a pullout just before LLW trucks reach the entrance to the NTS. The PICs are positioned at a distance of one meter from the sides of the truck trailer and at a height appropriate for the design of the trucks that will be used in FY2003 to haul LLW to the NTS. The use of four PICs (two on each side of the truck) is to minimize and to correct for non-uniformity where radiation levels from waste packages vary from side to side, and from front to back in the truck trailer. The PIC array is being calibrated by collecting readings from each PIC exposed to a known 137Cs source that was positioned at different locations on a flatbed stationed in the PIC array, along with taking secondary readings from other known sources. Continuous data collection using the PICs, with and without a truck in the array, is being used to develop background readings. In addition, acoustic sensors are positioned on each side of the PIC array to record when a large object (presumably a truck) enters the array. In FY2003, PIC surveys from as many incoming LLW trucks as possible will be made and survey data

  19. Guidance manual for the identification of hazardous wastes delivered to publicly owned treatment works by truck, rail, or dedicated pipe

    SciTech Connect (OSTI)

    Not Available

    1987-06-01

    The manual is directed towards two types of facilities: First, guidance is to POTWs that wish to preclude the entry of hazardous wastes into their facilities and avoid regulation and liability under RCRA. Administrative/technical recommendations for control of such wastes is provided, many of which are already in use by POTWs. Second, the responsibilities of POTWs that choose to accept hazardous wastes from truck, rail, or dedicated pipeline are discussed, including relevant regulatory provisions, strict liability and corrective action requirements for releases, and recommended procedures for waste acceptance/management. The manual describes the RCRA regulatory status of wastes that POTW operators typically may encounter. The manual includes a Waste Monitoring Plan. Appendices give the following: RCRA lists; RCRA listed hazardous wastes; examples of POTW sewer use ordinance language, waste hauler permit; waste tracking form, notification of hazardous waste activity; uniform hazardous waste manifest; biennial hazardous waste report; and state hazardous waste contacts.

  20. Georgia Hosts Multi-Agency Waste Isolation Pilot Plant Transportation Exercise

    Broader source: Energy.gov [DOE]

    COVINGTON, Ga. – Emergency personnel throughout the U.S. who respond in the event of a potential accident involving radioactive waste shipments take part in mock training scenarios to help them prepare for an actual incident.

  1. Superfund at work: Hazardous waste cleanup efforts nationwide, Winter 1994 (Seymour recycling site profile, Seymour, Indiana)

    SciTech Connect (OSTI)

    Not Available

    1994-01-01

    Leaking barrels of chemicals reacted and erupted into spontaneous fires and explosions at the Seymour Recycling Corporation in the 1970s. The poorly managed and overburdened hazardous waste storage and incineration facility polluted soil and ground water with solvents, acids, and heavy metals. With help from the Indiana Department of Environmental Management (IDEM) and the City of Seymour, cooperative efforts lead to an effective remediation of the site including: an immediate removal of drums, tanks and soil; a comprehensive ground water treatment system and extension of the municipal water supply to affected residents; and use of two innovative technologies, bioremediation and soil vapor extraction.

  2. A methodology for optimal MSW management, with an application in the waste transportation of Attica Region, Greece

    SciTech Connect (OSTI)

    Economopoulou, M.A.; Economopoulou, A.A.; Economopoulos, A.P.

    2013-11-15

    Highlights: • A two-step (strategic and detailed optimal planning) methodology is used for solving complex MSW management problems. • A software package is outlined, which can be used for generating detailed optimal plans. • Sensitivity analysis compares alternative scenarios that address objections and/or wishes of local communities. • A case study shows the application of the above procedure in practice and demonstrates the results and benefits obtained. - Abstract: The paper describes a software system capable of formulating alternative optimal Municipal Solid Wastes (MSWs) management plans, each of which meets a set of constraints that may reflect selected objections and/or wishes of local communities. The objective function to be minimized in each plan is the sum of the annualized capital investment and annual operating cost of all transportation, treatment and final disposal operations involved, taking into consideration the possible income from the sale of products and any other financial incentives or disincentives that may exist. For each plan formulated, the system generates several reports that define the plan, analyze its cost elements and yield an indicative profile of selected types of installations, as well as data files that facilitate the geographic representation of the optimal solution in maps through the use of GIS. A number of these reports compare the technical and economic data from all scenarios considered at the study area, municipality and installation level constituting in effect sensitivity analysis. The generation of alternative plans offers local authorities the opportunity of choice and the results of the sensitivity analysis allow them to choose wisely and with consensus. The paper presents also an application of this software system in the capital Region of Attica in Greece, for the purpose of developing an optimal waste transportation system in line with its approved waste management plan. The formulated plan was able to

  3. Site 300 hazardous-waste-assessment project. Interim report: December 1981. Preliminary site reconnaissance and project work plan

    SciTech Connect (OSTI)

    Raber, E.; Helm, D.; Carpenter, D.; Peifer, D.; Sweeney, J.

    1982-01-20

    This document was prepared to outline the scope and objectives of the Hazardous Waste Assessment Project (HWAP) at Site 300. This project was initiated in October, 1981, to investigate the existing solid waste landfills in an effort to satisfy regulatory guidelines and assess the potential for ground-water contamination. This involves a site-specific investigation (utilizing geology, hydrology, geophysics and geochemistry) with the goal of developing an effective ground-water quality monitoring network. Initial site reconnaissance work has begun and we report the results, to date, of our geologic hydrogeologic studies. All known solid waste disposal locations are underlain by rocks of either the Late Miocene Neroly Formation or the Cierbo Formation, both of which are dominantly sandstones interbedded with shale and claystone. The existence of a regional confined (artesian) aquifer, as well as a regional water-table aquifer is postulated for Site 300. Preliminary analysis has led to an understanding of directions and depths of regional ground-water flow.

  4. Categorical Exclusion 4565, Waste Management Construction Support

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

    and universal wastes); apply fabric and gravel to ground; transport equipment; transport materials; transport waste; remove vegetation; place barriers; place erosion controls;...

  5. Work plan for the fabrication of the radioisotope thermoelectric generator transportation system package mounting

    SciTech Connect (OSTI)

    Satoh, J.A.

    1994-11-09

    The Radioisotope Thermoelectric Generator (RTG) has available a dedicated system for the transportation of RTG payloads. The RTG Transportation System (System 100) is comprised of four systems; the Package (System 120), the Semi-trailer (System 140), the Gas Management (System 160), and the Facility Transport (System 180). This document provides guidelines on the fabrication, technical requirements, and quality assurance of the Package Mounting (Subsystem 145), part of System 140. The description follows the Development Control Requirements of WHC-CM-6-1, EP 2.4, Rev. 3.

  6. Unsaturated flow and transport through fractured rock related to high-level waste repositories; Final report, Phase 3

    SciTech Connect (OSTI)

    Evans, D.D.; Rasmussen, T.C. [Arizona Univ., Tucson, AZ (USA). Dept. of Hydrology and Water Resources

    1991-01-01

    Research results are summarized for a US Nuclear Regulatory Commission contract with the University of Arizona focusing on field and laboratory methods for characterizing unsaturated fluid flow and solute transport related to high-level radioactive waste repositories. Characterization activities are presented for the Apache Leap Tuff field site. The field site is located in unsaturated, fractured tuff in central Arizona. Hydraulic, pneumatic, and thermal characteristics of the tuff are summarized, along with methodologies employed to monitor and sample hydrologic and geochemical processes at the field site. Thermohydrologic experiments are reported which provide laboratory and field data related to the effects conditions and flow and transport in unsaturated, fractured rock. 29 refs., 17 figs., 21 tabs.

  7. Waste Preparation and Transport Chemistry: Results of the FY 2002 Studies

    SciTech Connect (OSTI)

    Hunt, R.D.

    2003-07-10

    The initial step in the remediation of nuclear waste stored at Hanford and the Savannah River Site (SRS) involves the retrieval and transfer of the waste to another tank or to a treatment facility. The retrieved waste can range from a filtered supernatant to a slurry. Nearly all of the recent solid formation problems encountered during waste transfers and subsequent treatment steps have involved decanted or filtered supernatants. Problems with slurry transfers have not yet surfaced, because tank farm operations at Hanford and the SRS have focused primarily on supernatant transfers and treatment. For example, the interim stabilization program at Hanford continues to reduce the level of supernatants and interstitial liquids in its single-shell tanks through saltwell pumping of filtered liquid. In addition, at present, the cross-site transfer lines at Hanford can be used only to transfer liquids. Another reason for fewer problems with slurry transfers involves the additions of large quantities of dilution water prior to the transfer. When the waste is transferred, a drop in temperature is expected because most transfer lines are not heated. However, the dilution water reduces or eliminates solid formation caused by this temperature drop. In sharp contrast, decanted or filtered supernatants are near or at saturation for certain compounds. In such cases, tank farm operators must continue to evaporate their liquid waste since available tank space is quite limited. Solid formation can occur when the temperature of saturated solutions drops even slightly. The evaporation step can also lead to the formation of problematic solids. At the SRS, the evaporation of a relatively dilute waste stream was suspended due to the formation of deposits in the evaporator system. Therefore, small drops in temperature or evaporation can lead to problematic solid formations.

  8. TRU waste inventory collection and work-off plans for the centralization of TRU waste characterization at INL - on your mark - get set - 9410

    SciTech Connect (OSTI)

    Mctaggert, Jerri Lynne; Lott, Sheila; Gadbury, Casey

    2009-01-01

    The U.S. Department of Energy (DOE) amended the Record of Decision (ROD) for the Waste Management Program: Treatment and Storage ofTransuranic Waste to centralize transuranic (TRU) waste characterization/certification from fourteen TRU waste sites. This centralization will allow for treatment, characterization and certification ofTRU waste from the fourteen sites, thirteen of which are sites with small quantities ofTRU waste, at the Idaho National Laboratory (INL) prior to shipping the waste to the Waste Isolation Pilot Plant (WIPP) for disposal. Centralization ofthis TRU waste will avoid the cost ofbuilding treatment, characterization, certification, and shipping capabilities at each ofthe small quantity sites that currently do not have existing facilities. Advanced Mixed Waste Treatment Project (AMWTP) and Idaho Nuclear Technology and Engineering Center (INTEC) will provide centralized shipping facilities, to WIPP, for all ofthe small quantity sites. Hanford, the one large quantity site identified in the ROD, has a large number ofwaste in containers that are overpacked into larger containers which are inefficient for shipment to and disposal at WIPP. The AMWTP at the INL will reduce the volume ofmuch of the CH waste and make it much more efficient to ship and dispose of at WIPP. In addition, the INTEC has a certified remote handled (RH) TRU waste characterization/certification program at INL to disposition TRU waste from the sites identified in the ROD.

  9. Stakeholder Transportation Scorecard: Reviewing Nevada's Recommendations for Enhancing the Safety and Security of Nuclear Waste Shipments - 13518

    SciTech Connect (OSTI)

    Dilger, Fred C.; Ballard, James D.; Halstead, Robert J.

    2013-07-01

    As a primary stakeholder in the Yucca Mountain program, the state of Nevada has spent three decades examining and considering national policy regarding spent nuclear fuel and high-level radioactive waste transportation. During this time, Nevada has identified 10 issues it believes are critical to ensuring the safety and security of any spent nuclear fuel transportation program, and achieving public acceptance. These recommendations are: 1) Ship the oldest fuel first; 2) Ship mostly by rail; 3) Use dual-purpose (transportable storage) casks; 4) Use dedicated trains for rail shipments; 5) Implement a full-scale cask testing program; 6) Utilize a National Environmental Policy Act (NEPA) process for the selection of a new rail spur to the proposed repository site; 7) Implement the Western Interstate Energy Board (WIEB) 'straw man' process for route selection; 8) Implement Section 180C assistance to affected States, Tribes and localities through rulemaking; 9) Adopt safety and security regulatory enhancements proposed states; and 10) Address stakeholder concerns about terrorism and sabotage. This paper describes Nevada's proposals in detail and examines their current status. The paper describes the various forums and methods by which Nevada has presented its arguments and sought to influence national policy. As of 2012, most of Nevada's recommendations have been adopted in one form or another, although not yet implemented. If implemented in a future nuclear waste program, the State of Nevada believes these recommendations would form the basis for a successful national transportation plan for shipments to a geologic repository and/or centralized interim storage facility. (authors)

  10. Statement of work for conceptual design of solidified high-level waste interim storage system project (phase I)

    SciTech Connect (OSTI)

    Calmus, R.B., Westinghouse Hanford

    1996-12-17

    The U.S. Department of Energy (DOE) has embarked upon a course to acquire Hanford Site tank waste treatment and immobilization services using privatized facilities. This plan contains a two phased approach. Phase I is a ``proof-of-principle/commercial demonstration- scale`` effort and Phase II is a full-scale production effort. In accordance with the planned approach, interim storage (IS) and disposal of various products from privatized facilities are to be DOE furnished. The path forward adopted for Phase I solidification HLW IS entails use of Vaults 2 and 3 in the Spent Nuclear Fuel Canister Storage Building, to be located in the Hanford Site 200 East Area. This Statement of Work describes the work scope to be performed by the Architect-Engineer to prepare a conceptual design for the solidified HLW IS System.

  11. Supplemental information related to risk assessment for the off-site transportation of low-level waste for the U.S. Department of Energy waste management programmatic environmental impact statement

    SciTech Connect (OSTI)

    Monette, F.A.; Biwer, B.M.; LePoire, D.J.; Chen, S.Y. [Argonne National Lab., IL (United States). Environmental Assessment Div.

    1996-12-01

    This report presents supplemental information to support the human health risk assessment conducted for the transportation of low-level waste (LLW) in support of the US Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS). Detailed descriptions of the transportation health risk assessment method and results of the assessment are presented in Appendix E of the WM PEIS and are not repeated in this report. This report presents additional information that is not presented in Appendix E but that was needed to conduct the transportation risk assessment for Waste Management (WM) LLW. Included are definition of the LLW alternatives considered in the WM PEIS, data related to the inventory and to the physical and radiological characteristics of WM LLW, an overview of the risk assessment method, and detailed results of the assessment for each WM LLW alternative considered.

  12. Co-combustion of pellets from Soma lignite and waste dusts of furniture works

    SciTech Connect (OSTI)

    Deveci, N.D.; Yilgin, M.; Pehlivan, D.

    2008-07-01

    In this work, volatiles and char combustion behaviors of the fuel pellets prepared from a low quality lignite and the dusts of furniture works and their various blends were investigated in an experimental fixed bed combustion system through which air flowed by natural convection. Combustion data obtained for varied bed temperatures, mass of pellets, and blend compositions has showed that ignition times of the pellets decreased and volatiles combustion rates tended to increase with the burning temperature. It was concluded that some synergy had existed between lignite and lower ratios of furniture work dusts, which was indicated by a prompt effect on the volatiles combustion rates. Char combustion rates of blend pellets have depended predominantly on the amount of lignite in the blend. The amounts of combustion residues of the pellets were considerably higher than those calculated from individual ash contents of the raw materials and related to lignite ratio in the blends.

  13. Mechanical environmental transport of actinides and ¹³⁷Cs from an arid radioactive waste disposal site

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

    Snow, Mathew S.; Clark, Sue B.; Morrison, Samuel S.; Watrous, Matthew G.; Olson, John E.; Snyder, Darin C.

    2015-10-01

    Particulate transport represents an important mechanism for actinides and fission products at the Earth's surface; soil samples taken in the early 1970's near the Subsurface Disposal Area (SDA) at Idaho National Laboratory (INL) provide a case study for examining the mechanisms and characteristics of actinide transport under arid conditions. Transuranic waste was disposed via shallow land burial at the SDA until shortly after a flooding event that occurred in 1969. In this study we analyze soils collected in the early 1970's for ¹³⁷Cs, ²⁴¹Am, and Pu using a combination of radiometric and mass spectrometric techniques. Two distinct ²⁴⁰Pu/²³⁹Pu isotopic ratiosmore » are observed for contamination from the SDA, with values ranging from at least 0.059 to 0.069. ²⁴¹Am concentrations are observed to increase only slightly in 0-4 cm soils over the ~40 year period since soil sampling, contrary to Markham's previous hypothesis that ²⁴¹Pu is principally associated with the 0-4 cm soil fractions (Markham 1978). The lack of statistical difference in ²⁴¹Am/²³⁹⁺²⁴⁰Pu ratios with depth suggests mechanical transport and mixing discrete contaminated particles under arid conditions. Occasional samples beyond the northeastern corner are observed to contain anomalously high Pu concentrations with corresponding low ²⁴⁰Pu/²³⁹Pu atoms ratios, suggesting the occurrence of "hot particles;" application of a background Pu subtraction results in calculated Pu atom ratios for the "hot particles" which are statistically similar to those observed in the northeastern corner. Taken together, our data suggests that flooding resulted in mechanical transport of contaminated particles into the area between the SDA and the flood containment dike in the northeastern corner, following which subsequent contamination spreading resulted from wind transport of discrete particles.« less

  14. Mechanical environmental transport of actinides and ¹³⁷Cs from an arid radioactive waste disposal site

    SciTech Connect (OSTI)

    Snow, Mathew S.; Clark, Sue B.; Morrison, Samuel S.; Watrous, Matthew G.; Olson, John E.; Snyder, Darin C.

    2015-10-01

    Particulate transport represents an important mechanism for actinides and fission products at the Earth's surface; soil samples taken in the early 1970's near the Subsurface Disposal Area (SDA) at Idaho National Laboratory (INL) provide a case study for examining the mechanisms and characteristics of actinide transport under arid conditions. Transuranic waste was disposed via shallow land burial at the SDA until shortly after a flooding event that occurred in 1969. In this study we analyze soils collected in the early 1970's for ¹³⁷Cs, ²⁴¹Am, and Pu using a combination of radiometric and mass spectrometric techniques. Two distinct ²⁴⁰Pu/²³⁹Pu isotopic ratios are observed for contamination from the SDA, with values ranging from at least 0.059 to 0.069. ²⁴¹Am concentrations are observed to increase only slightly in 0-4 cm soils over the ~40 year period since soil sampling, contrary to Markham's previous hypothesis that ²⁴¹Pu is principally associated with the 0-4 cm soil fractions (Markham 1978). The lack of statistical difference in ²⁴¹Am/²³⁹⁺²⁴⁰Pu ratios with depth suggests mechanical transport and mixing discrete contaminated particles under arid conditions. Occasional samples beyond the northeastern corner are observed to contain anomalously high Pu concentrations with corresponding low ²⁴⁰Pu/²³⁹Pu atoms ratios, suggesting the occurrence of "hot particles;" application of a background Pu subtraction results in calculated Pu atom ratios for the "hot particles" which are statistically similar to those observed in the northeastern corner. Taken together, our data suggests that flooding resulted in mechanical transport of contaminated particles into the area between the SDA and the flood containment dike in the northeastern corner, following which subsequent contamination spreading resulted from wind transport of discrete particles.

  15. Fate and transport processes controlling the migration of hazardous and radioactive materials from the Area 5 Radioactive Waste Management Site (RWMS)

    SciTech Connect (OSTI)

    Estrella, R.

    1994-10-01

    Desert vadose zones have been considered as suitable environments for the safe and long-term isolation of hazardous wastes. Low precipitation, high evapotranspiration and thick unsaturated alluvial deposits commonly found in deserts make them attractive as waste disposal sites. The fate and transport of any contaminant in the subsurface is ultimately determined by the operating retention and transformation processes in the system and the end result of the interactions among them. Retention (sorption) and transformation are the two major processes that affect the amount of a contaminant present and available for transport. Retention processes do not affect the total amount of a contaminant in the soil system, but rather decrease or eliminate the amount available for transport at a given point in time. Sorption reactions retard the contaminant migration. Permanent binding of solute by the sorbent is also possible. These processes and their interactions are controlled by the nature of the hazardous waste, the properties of the porous media and the geochemical and environmental conditions (temperature, moisture and vegetation). The present study summarizes the available data and investigates the fate and transport processes that govern the migration of contaminants from the Radioactive Waste Management Site (RWMS) in Area 5 of the Nevada Test Site (NTS). While the site is currently used only for low-level radioactive waste disposal, past practices have included burial of material now considered hazardous. Fundamentals of chemical and biological transformation processes are discussed subsequently, followed by a discussion of relevant results.

  16. National Transportation Stakeholders Forum (NTSF) Charter | Department...

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

    Services Waste Management Packaging and Transportation National Transportation Stakeholders Forum National Transportation Stakeholders Forum (NTSF) Charter National ...

  17. Transportation of Spent Nuclear Fuel and High Level Waste to Yucca Mountain: The Next Step in Nevada

    SciTech Connect (OSTI)

    Sweeney, Robin L,; Lechel, David J.

    2003-02-25

    In the U.S. Department of Energy's ''Final Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada,'' the Department states that certain broad transportation-related decisions can be made. These include the choice of a mode of transportation nationally (mostly legal-weight truck or mostly rail) and in Nevada (mostly rail, mostly legal-weight truck, or mostly heavy-haul truck with use of an associated intermodal transfer station), as well as the choice among alternative rail corridors or heavy-haul truck routes with use of an associated intermodal transfer station in Nevada. Although a rail line does not service the Yucca Mountain site, the Department has identified mostly rail as its preferred mode of transportation, both nationally and in the State of Nevada. If mostly rail is selected for Nevada, the Department would then identify a preference for one of the rail corridors in consultation with affected stakeholders, particularly the State of Nevada. DOE would then select the rail corridor and initiate a process to select a specific rail alignment within the corridor for the construction of a rail line. Five proposed rail corridors were analyzed in the Final Environmental Impact Statement. The assessment considered the impacts of constructing a branch rail line in the five 400-meter (0.25mile) wide corridors. Each corridor connects the Yucca Mountain site with an existing mainline railroad in Nevada.

  18. Development of Alternate Soil Clean-Up Goals for Hanford Waste Sites Using Fate and Transport Modeling

    SciTech Connect (OSTI)

    Hoover, J.D. [Fluor Hanford, Inc. (United States); McMahon, W.J. [CH2M Hill Hanford Group (United States); Leary, K.D. [DOE/RL (United States)

    2008-07-01

    Remedial Action Goals (RAGs) for soil contaminant levels that are protective of groundwater have been determined for the Removal/Treatment/Disposal (RTD) sites at the 200-UW-1 Operable Unit on the Hanford Site. The RAG values were determined using a methodology involving the back-calculation of soil contaminant levels protective of groundwater (i.e., resulting groundwater concentrations are {<=} MCLs) in conjunction with the fate and transport modeling as a risk-based alternative to the currently prescribed use of background or detection limit default values. This methodology is important for waste management activities at the Hanford Site because it provides risk-based metrics and a technical basis for determining the levels of contamination 'left in place' in the Hanford Site vadose zone that are protective of human health and the environment. The methodology and the use of fate and transport modeling described here comply with federal guidelines for the use of environmental models. This approach is also consistent with one of several allowable methods identified in State guidelines for deriving soil concentrations for ground water protection. Federal and state guidelines recommend the use of site-specific information and data in risk-based assessments of risk and/or protectiveness. The site-specific characteristics of the Hanford Site, which include consideration of the semi-arid climate, an unsaturated zone thickness of over 80 m (262 feet), and associated/other site features and processes, are integral for the risk-based assessments associated with the protection of groundwater pathway. This methodology yields soil cleanup values (RAGs) for the 200-UW-1 OU waste sites selected for the removal/treatment/disposal (RTD) remedy. These proposed RAGs for uranium, nitrate, and technetium-99 are derived from soil concentrations calculated not to cause contamination of groundwater at levels that exceed the ground water MCLs, and are 40 to 200 times greater than

  19. Radionuclide-Chelating Agent Complexes in Low-Level Radioactive Decontamination Waste; Stability, Adsorption and Transport Potential

    SciTech Connect (OSTI)

    Serne, R. Jeffrey; Cantrell, Cantrell J.; Lindenmeier, Clark W.; Owen, Antionette T.; Kutnyakov, Igor V.; Orr, Robert D.; Felmy, Andrew R.

    2002-02-01

    Speciation calculations were done to determine whether organic complexants facilitate transport of radionuclides leached from waste buried in soils. EDTA readily mobilizes divalent transition metals and moderately impacts trivalent actinides. Picolinate readily mobilizes only Ni2+ and Co2+. These speciation predictions ignore the influence of soil adsorption and biodegradation that break apart the complexes. In adsorption studies, picolinate concentrations have to be >10-4 M to lower the adsorption of Ni and Co. For Sm(III), Th(IV), Np(V), U(VI), and Pu, the picolinate concentration must be >10-3 M before adsorption decreases. EDTA forms strong complexes with divalent transition metals and can stop adsorption of Ni and Co when EDTA solution concentrations are 10-5 M. EDTA complexes with Np(V), U(VI), and Pu are much weaker; EDTA concentrations would have to be >10-3 M to adversely effects non-transition metal/radionuclide adsorption. Most picolinate and ETDA-metal complexes appear to readily dissociate during interactions with soils. The enhanced migration of radionuclide-organic complexes may be limited to a few unique conditions. We recommend that mixtures of metal/radionuclides and EDTA should not be solidified or co-disposed with high pH materials such as cement. For weaker binding organic complexants, such as picolinate, citrate and oxalate, co-disposal of decontamination wastes and concrete should be acceptable.

  20. Assessing Potential Exposure from Truck Transport of Low-level Radioactive Waste to the Nevada Test Site

    SciTech Connect (OSTI)

    J. Miller; D. Shafer; K. Gray; B. Church; S. Campbell; B. Holz

    2005-08-01

    Since 1980, over 651,558 m{sup 3} (23,000,000 ft{sup 3}) of low-level radioactive waste (LLW) have been disposed of at the Nevada Test Site (NTS) by shallow land burial. Since 1988, the majority of this waste has been generated at other United States (U.S.) Department of Energy (DOE) and Department of Defense (DoD) sites and facilities in the U.S. Between fiscal year (FY) 2002 and the publication date, the volumes of LLW being shipped by truck to the NTS increased sharply with the accelerated closure of DOE Environmental Management (EM) Program sites (DOE, 2002). The NTS is located 105 km (65 mi) northwest of Las Vegas, Nevada, in the U.S. There continue to be public concerns over the safety of LLW shipments to the NTS. They can be broadly divided into two categories: (1) the risk of accidents involving trucks traveling on public highways; and (2) whether residents along transportation routes receive cumulative exposure from individual LLW shipments that pose a long-term health risk. The DOE and U.S. Department of Transportation (DOT) regulations ensure that radiation exposure from truck shipments to members of the public is negligible. Nevertheless, particularly in rural communities along transportation routes in Utah and Nevada, there is a perceived risk from members of the public about cumulative exposure, particularly when ''Main Street'' and the routes being used by LLW trucks are one in the same. To provide an objective assessment of gamma radiation exposure to members of the public from LLW transport by truck, the Desert Research Institute (DRI) and the DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) established a stationary and automated array of four pressurized ion chambers (PICs) in a vehicle pullout for LLW trucks to pass through just outside the entrance to the NTS. The PICs were positioned at a distance of 1.0 m (3.3 ft) from the sides of the truck trailer and at a height of 1.5 m (5.0 ft) to simulate conditions that a

  1. Assessing Potential Exposure from Truck Transport of Low-level Radioactive Waste to the Nevada Test Site

    SciTech Connect (OSTI)

    Miller, J; Shafer, D; Gray, K; Church, B; Campbell, S; Holtz, B.

    2005-08-15

    Since 1980, over 651,558 m{sup 3} (23,000,000 ft{sup 3}) of low-level radioactive waste (LLW) have been disposed of at the Nevada Test Site (NTS) by shallow land burial. Since 1988, the majority of this waste has been generated at other United States (U.S.) Department of Energy (DOE) and Department of Defense (DoD) sites and facilities in the U.S. Between fiscal year (FY) 2002 and the publication date, the volumes of LLW being shipped by truck to the NTS increased sharply with the accelerated closure of DOE Environmental Management (EM) Program sites (DOE, 2002). The NTS is located 105 km (65 mi) northwest of Las Vegas, Nevada, in the U.S. There continue to be public concerns over the safety of LLW shipments to the NTS. They can be broadly divided into two categories: (1) the risk of accidents involving trucks traveling on public highways; and (2) whether residents along transportation routes receive cumulative exposure from individual LLW shipments that pose a long-term health risk. The DOE and U.S. Department of Transportation (DOT) regulations ensure that radiation exposure from truck shipments to members of the public is negligible. Nevertheless, particularly in rural communities along transportation routes in Utah and Nevada, there is a perceived risk from members of the public about cumulative exposure, particularly when ''Main Street'' and the routes being used by LLW trucks are one in the same. To provide an objective assessment of gamma radiation exposure to members of the public from LLW transport by truck, the Desert Research Institute (DRI) and the DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) established a stationary and automated array of four pressurized ion chambers (PICs) in a vehicle pullout for LLW trucks to pass through just outside the entrance to the NTS. The PICs were positioned at a distance of 1.0 m (3.3 ft) from the sides of the truck trailer and at a height of 1.5 m (5.0 ft) to simulate conditions that a

  2. EM QA Working Group September 2011 Meeting Materials | Department...

    Energy Savers [EERE]

    Nuclear Materials & Waste Tank Waste and Waste Processing Waste Disposition Packaging and Transportation Site & Facility Restoration Deactivation & Decommissioning (D&D)...

  3. transportation

    National Nuclear Security Administration (NNSA)

    security missions undertaken by the U.S. government.

    Pantex Plant's Calvin Nelson honored as Analyst of the Year for Transportation Security http:nnsa.energy.gov...

  4. Chernobyl Studies Project: Working group 7.0, Environmental transport and health effects. Progress report, March--September 1994

    SciTech Connect (OSTI)

    Anspaugh, L.R.; Hendrickson, S.M.

    1994-12-01

    In April 1988, the US and the former-USSR signed a Memorandum of Cooperation (MOC) for Civilian Nuclear Reactor Safety; this MOC was a direct result of the accident at the Chernobyl Nuclear Power Plant Unit 4 and the following efforts by the two countries to implement a joint program to improve the safety of nuclear power plants and to understand the implications of environmental releases. A Joint Coordinating Committee for Civilian Nuclear Reactor Safety (JCCCNRS) was formed to implement the MOC. The JCCCNRS established many working groups; most of these were the responsibility of the Nuclear Regulatory Commission, as far as the US participation was concerned. The lone exception was Working Group 7 on Environmental Transport and Health Effects, for which the US participation was the responsibility of the US Department of Energy (DOE). The purpose of Working Group 7 was succintly stated to be, ``To develop jointly methods to project rapidly the health effects of any future nuclear reactor accident.`` To implement the work DOE then formed two subworking groups: 7.1 to address Environmental Transport and 7.2 to address Health Effects. Thus, the DOE-funded Chernobyl Studies Project began. The majority of the initial tasks for this project are completed or near completion. The focus is now turned to the issue of health effects from the Chernobyl accident. Currently, we are involved in and making progress on the case-control and co-hort studies of thyroid diseases among Belarussian children. Dosimetric aspects are a fundamental part of these studies. We are currently working to implement similar studies in Ukraine. A major part of the effort of these projects is supporting these studies, both by providing methods and applications of dose reconstruction and by providing support and equipment for the medical teams.

  5. A report on high-level nuclear waste transportation: Prepared pursuant to assembly concurrent resolution No. 8 of the 1987 Nevada Legislature

    SciTech Connect (OSTI)

    1988-12-01

    This report has been prepared by the staff of the State of Nevada Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) in response to Assembly Concurrent Resolution No. 8 (ACR 8), passed by the Nevada State Legislature in 1987. ACR 8 directed the NWPO, in cooperation with affected local governments and the Legislative committee on High-Level Radioactive Waste, to prepare this report which scrutinizes the US Department of Energy`s (DOE) plans for transportation of high-level radioactive waste to the proposed yucca Mountain repository, which reviews the regulatory structure under which shipments to a repository would be made and which presents NWPO`s plans for addressing high-level radioactive waste transportation issues. The report is divided into three major sections. Section 1.0 provides a review of DOE`s statutory requirements, its repository transportation program and plans, the major policy, programmatic, technical and institutional issues and specific areas of concern for the State of Nevada. Section 2.0 contains a description of the current federal, state and tribal transportation regulatory environment within which nuclear waste is shipped and a discussion of regulatory issues which must be resolved in order for the State to minimize risks and adverse impacts to its citizens. Section 3.0 contains the NWPO plan for the study and management of repository-related transportation. The plan addresses four areas, including policy and program management, regulatory studies, technical reviews and studies and institutional relationships. A fourth section provides recommendations for consideration by State and local officials which would assist the State in meeting the objectives of the plan.

  6. Transportation Management Workshop: Proceedings

    SciTech Connect (OSTI)

    Not Available

    1993-10-01

    This report is a compilation of discussions presented at the Transportation Management Workshop held in Gaithersburg, Maryland. Topics include waste packaging, personnel training, robotics, transportation routing, certification, containers, and waste classification.

  7. EBS Radionuclide Transport Abstraction

    SciTech Connect (OSTI)

    J.D. Schreiber

    2005-08-25

    The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in ''Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration'' (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment for the license application (TSPA-LA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA-LA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport model considers

  8. Evaluation of conceptual, mathematical and physical-and-chemical models for describing subsurface radionuclide transport at the Lake Karachai Waste Disposal Site

    SciTech Connect (OSTI)

    Rumynin, V.G.; Mironenko, V.A.; Sindalovsky, L.N.; Boronina, A.V.; Konosavsky, P.K.; Pozdniakov, S.P.

    1998-06-01

    The goal of this work was to develop the methodology and to improve understanding of subsurface radionuclide transport for application to the Lake Karachai Site and to identify the influence of the processes and interactions involved into transport and fate of the radionuclides. The report is focused on two sets of problems, which have to do both with, hydrodynamic and hydrogeochemical aspects of the contaminant transport.

  9. WIPP Documents - Transportation

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

    Transportation

  10. DE-EM-0001971 WIPP M&O C-1 SECTION C PERFORMANCE WORK STATEMENT

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

    DE-EM-0001971 WIPP M&O C-1 SECTION C PERFORMANCE WORK STATEMENT 1. CONTRACT PURPOSE The major purpose of this contract is to operate and maintain the Waste Isolation Pilot Plant (WIPP) and to implement the DOE's National Transuranic Waste program (NTP). The overall mission of the WIPP and the National Transuranic Waste Program is to protect human health and the environment by safe management, retrieval, characterization, transportation, and disposal of approved wastes. 2. BACKGROUND 2.1

  11. DE-EM-0001971 WIPP M&O C-1 SECTION C PERFORMANCE WORK STATEMENT

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

    C-1 SECTION C PERFORMANCE WORK STATEMENT 1. CONTRACT PURPOSE The major purpose of this contract is to operate and maintain the Waste Isolation Pilot Plant (WIPP) and to implement the DOE's National Transuranic Waste program (NTP). The overall mission of the WIPP and the National Transuranic Waste Program is to protect human health and the environment by safe management, retrieval, characterization, transportation, and disposal of approved wastes. 2. BACKGROUND 2.1 Background: The WIPP is located

  12. Technical Work Plan For: Calculation of Waste Packave and Drip Shield Response to Vibratory Ground Motion and Revision of the Seismic Consequence Abstraction

    SciTech Connect (OSTI)

    M. Gross

    2006-12-08

    The overall objective of the work scope covered by this technical work plan (TWP) is to develop new damage abstractions for the seismic scenario class in total system performance assessment (TSPA). The new abstractions will be based on a new set of waste package and drip shield damage calculations in response to vibratory ground motion and fault displacement. The new damage calculations, which are collectively referred to as damage models in this TWP, are required to represent recent changes in waste form packaging and in the regulatory time frame. The new damage models also respond to comments from the Independent Validation Review Team (IVRT) postvalidation review of the draft TSPA model regarding performance of the drip shield and to an Additional Information Need (AIN) from the U.S. Nuclear Regulatory Commission (NRC).

  13. A simulation of the transport and fate of radon-222 derived from thorium-230 low-level waste in the near-surface zone of the Radioactive Waste Management Site in Area 5 of the Nevada Test Site

    SciTech Connect (OSTI)

    Lindstrom, F.T.; Cawlfield, D.E.; Donahue, M.E.; Emer, D.F.; Shott, G.J.

    1993-12-01

    US Department of Energy (DOE) Order 5820.2A (DOE, 1988) requires performance assessments on all new and existing low-level radioactive waste (LLW) disposal sites. An integral part of performance assessment is estimating the fluxes of radioactive gases such as radon-220 and radon-222. Data needs pointed out by mathematical models drive site characterization. They provide a logical means of performing the required flux estimations. Thorium-230 waste, consisting largely of thorium hydroxide and thorium oxides, has been approved for disposal in shallow trenches and pits at the LLW Radioactive Waste Management Site in Area 5 of the Nevada Test Site. A sophisticated gas transport model, CASCADR8 (Lindstrom et al., 1992b), was used to simulate the transport and fate of radon-222 from its source of origin, nine feet below a closure cap of native soil, through the dry alluvial earth, to its point of release into the atmosphere. CASCADR8 is an M-chain gas-phase radionuclide transport and fate model. It has been tailored to the site-specific needs of the dry desert environment of southern Nevada. It is based on the mass balance principle for each radionuclide and uses gas-phase diffusion as well as barometric pressure-induced advection as its main modes of transport. CASCADR8 uses both reversible and irreversible sorption kinetic rules as well as the usual classical Bateman (1910) M-chain decay rules for its kinetic processes. Worst case radon-222 gas-phase concentrations, as well as surface fluxes, were estimated over 40 days. The maximum flux was then used in an exposure assessment model to estimate the total annual dose equivalent received by a person residing in a standard 2500-square-foot house with 10-foot walls. Results are described.

  14. 4th Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    SciTech Connect (OSTI)

    Gregory, Louis

    2014-12-02

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. There was one shipment of two drums sent for offsite treatment and disposal. This report summarizes the 4th quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014.

  15. Lessons learned by southern states in transportation of radioactive materials

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    This report has been prepared under a cooperative agreement with DOE`s Office of Civilian Radioactive Waste Management (OCRWM) and is a summary of the lessons learned by southern states regarding the transportation of radioactive materials including High-Level Radioactive Wastes (HLRW) and Spent Nuclear Fuel (SNF). Sources used in this publication include interviews of state radiological health and public safety officials that are members of the Southern States Energy Board (SSEB) Advisory Committee on Radioactive Materials Transportation, as well as the Board`s Transuranic (TRU) Waste Transportation Working Group. Other sources include letters written by the above mentioned committees concerning various aspects of DOE shipment campaigns.

  16. 1st Quarter Transportation Report FY 2015: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    SciTech Connect (OSTI)

    Gregory, Louis

    2015-02-20

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 1st quarter of Fiscal Year (FY) 2015 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report include minor volumes of non-radioactive classified waste/material that were approved for disposal (non-radioactive classified or nonradioactive classified hazardous). Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to rounding conventions for volumetric conversions from cubic meters to cubic feet.

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

    SciTech Connect (OSTI)

    Hanke, P.M.

    1987-11-04

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

  18. Waste Isolation Pilot Plant | Department of Energy

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

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

  19. Conceptual design statement of work for the immobilized low-activity waste disposal facility, project W-520

    SciTech Connect (OSTI)

    Pickett, W.W.

    1998-04-30

    This Statement of Work outlines the deliverables and schedule for preparation of the Project W-520 Conceptual Design Report, including, work plans, site development plan, preliminary safety evaluation, and conceptual design.

  20. 3rd Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    SciTech Connect (OSTI)

    Gregory, Louis

    2014-09-20

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 3rd quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014 in Tables 4 and 5. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report do not include minor volumes of non-radioactive materials that were approved for disposal. Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to differing rounding conventions.

  1. Health assessment for Fletcher's Paint Works and Storage Facility Hazardous Waste Material, Milford, Hillsborough County, New Hampshire, Region 1. CERCLIS No. NHD981067614. Preliminary report

    SciTech Connect (OSTI)

    Not Available

    1990-06-11

    Fletcher's Paint Works and Storage Facility Hazardous Waste Site (Fletcher's Paint Site) in Milford, New Hampshire, consists of three distinct entities: Fletcher's Paint Works at 21 Elm Street, Fletcher's Paint Storage Facility on Mill Street, and a drainage ditch leading from the storage facility property to Hampshire Paper Company property. The aggregation of these three properties was based on the similar nature of operations and wastes, the close proximity of the areas, the same target population, and the same underlying aquifer at risk of contamination. The aggregated site has contributed to the contamination of soil, groundwater, surface water, sediment, and air with various volatile organic chemicals (VOCs), semivolatile organic chemicals (SVOCs), heavy metals, and polychlorinated biphenyls (PCBs). Environmental monitoring related to the Fletcher's Paint Site has consisted of sampling of the Keyes Well by the NH WSPCC, and sampling at the paint works, storage facility and drainage ditch by NUS Corporation and EPA's Environmental Services Division (ESD). Contaminant levels at each location is discussed individually. Based upon the available information, the Fletcher's Paint NPL Site is considered to be of potential public health concern because of the risk to public health caused by potential exposure to hazardous substances, such as VOCs, PCBs, PAHs, and heavy metals, at concentrations that may result in adverse health effects. Exposure to contaminated soil and surface water, and potentially contaminated fish may be occurring. The site is located in a densely populated part of town, while the storage facility is readily accessible to children walking to and from school.

  2. Laboratory Waste | Sample Preparation Laboratories

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

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

  3. Waste Disposal | Department of Energy

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

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

  4. Development of a Density Sensor for In-Line Real-Time Process Control and Monitoring of Slurries during Radioactive Waste Retrieval and Transport Operations at DOE Sites

    SciTech Connect (OSTI)

    Bamberger, Judith A.; Greenwood, Margaret S.

    2001-11-19

    A density sensor (densimeter) to monitor and control slurries in-line real-time during radioactive waste retrieval and transport and detect conditions leading to degraded transport and line plugging is described. Benefits over baseline grab samples and off line analysis include: early detection and prevention of pipeline plugging, real-time density through the transfer process, elimination of grab sampling and off-line analysis, and reduced worker radiation exposure. The sensor is small, robust and could be retrofitted into existing pump pit manifolds and transfer lines. The probe uses ultrasonic signal reflection at the fluid-pipe wall interface to quantify density and features include: a non-intrusive sensing surface located flush with the pipeline wall; performance that is not affected by entrained air or by electromagnetic noise from nearby pumps and other equipment and is compact. Components were tested for chemical and radiation resistance and the spool piece was pressure tested in accordance with ASME Process Piping Code B31.3 and approved by the Hanford Site Flammable Gas Equipment Advisory Board for installation. During pipeline tests, the sensor predicted density within + 2% oriented in vertical and horizontal position. The densimeter is installed in the modified process manifold that is installed in the prefabricated pump pit at Hanford tank SY-101 site. In FY-2002 the density sensor performance will be evaluated during transfers of both water and waste through the pipeline. A separate project developed an ultrasonic sensor that: 1) can be attached permanently to a pipeline wall, possibly as a spool piece inserted into the line or 2) can clamp onto an existing pipeline wall and be movable to another location. This method is attractive for radioactive fluids transport applications because the sensors could be applied to existing equipment without the need to penetrate the pipe pressure boundary or to open the system to install new equipment.

  5. Nuclear Waste Materials Characterization Center. Semiannual progress report, April 1985-September 1985

    SciTech Connect (OSTI)

    Mendel, J.E.

    1985-12-01

    Work continued on converting MCC Quality Assurance practices to comply with the national QA standard for nuclear facilities, ANSI/ASME NQA-1. Support was provided to the following: Office of Geologic Repositories; Salt Repository Project; Basalt Waste Isolation Project; Office of Defense Waste and Byproducts Management; Hanford Programs; Transportation Technology Center; and West Valley Demonstration Project. (LM)

  6. Working Copy

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

    DOE/WIPP-99-2286 Waste Isolation Pilot Plant Environmental Notification or Reporting Implementation Plan Revision 7 U.S. Department of Energy December 2013 This document supersedes DOE/WIPP-99-2286, Rev. 6. Working Copy Waste Isolation Pilot Plant Environmental Notification or Reporting Implementation Plan DOE/WIPP-99-2286, Rev. 7 2 TABLE OF CONTENTSCHANGE HISTORY SUMMARY .............................................. 3 ACRONYMS AND ABBREVIATIONS

  7. Radioactive Material Transportation Practices

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

    2002-09-23

    Establishes standard transportation practices for Departmental programs to use in planning and executing offsite shipments of radioactive materials including radioactive waste. Does not cancel other directives.

  8. TEC Working Group Topic Groups Section 180(c) | Department of Energy

    Office of Environmental Management (EM)

    Section 180(c) TEC Working Group Topic Groups Section 180(c) Section 180(c) is a provision in the Nuclear Waste Policy Act that requires DOE to implement a program of technical and financial assistance to states for training public safety officials of appropriate units of local government and to Indian tribes through whose jurisdictions the Department plans to transport spent nuclear fuel or high-level waste to a facility authorized under the Nuclear Waste Policy Act. The training would cover

  9. Notice of construction work in tank farm waste transfer pit 241-UX-154 double-contained receiver tank

    SciTech Connect (OSTI)

    HILL, J.S.

    1999-08-05

    The following description and any attachments and references are provided to the Washington State Department of Health (WDOH), Division of Radiation Protection, Air Emissions & Defense Waste Section as a notice of construction (NOC) in accordance with Washington Administrative Code (WAC) 246-247, Radiation Protection - Air Emissions. WAC 246-247-060, ''Applications, registration, and licensing'', states ''This section describes the information requirements for approval to construct, modify, and operate an emission unit. Any NOC requires the submittal of information listed in Appendix A,'' Appendix A (WAC 246-247-110) lists the requirements that must be addressed. Additionally, the following description, attachments, and references are provided to the U.S. Environmental Protection Agency (EPA) as an NOC, in accordance with Title 40 Code of Federal Regulations (CFR), Part 61, ''National Emission Standards for Hazardous Air Pollutants.'' The information required for submittal to the EPA is specified in 40 CFR 61.07. The potential emissions from this activity are estimated to provide less than 0.1 millirem/year total effective dose equivalent to the hypothetical offsite maximally exposed individual, and commencement is needed within a short time. Therefore, this application also is intended to provide notification of the anticipated date of initial startup in accordance with the requirement listed in 40 CFR 61.09(a)(1), and it is requested that approval of this application also will constitute EPA acceptance of this initial startup notification. Written notification of the actual date of initial startup, in accordance with the requirement listed in 40 CFR 61.09(a)(2), will be provided later. The activities described in this NOC are estimated to provide a potential offsite (unabated) total effective dose equivalent (TEDE) to the hypothetical maximally exposed individual (h4EI) of 1.53 E02 millirem per year.

  10. Notice of construction work in tank farm waste transfer pit 244-TX double contained receiver-tank

    SciTech Connect (OSTI)

    HILL, J.S.

    1999-07-14

    The following description and any attachments and references are provided to the Washington State Department of Health (WDOH), Division of Radiation Protection, Air Emissions & Defense Waste Section as a notice of construction (NOC) in accordance with Washington Administrative Code (WAC) 246-247, Radiation Protection - Air Emissions. WAC 246-247-060, ''Applications, registration, and licensing'', states ''This section describes the information requirements for approval to construct, modify, and operate an emission unit. Any NOC requires the submittal of information listed in Appendix A,'' Appendix A (WAC 246-247-1 10) lists the requirements that must be addressed. Additionally, the following description, attachments, and references are provided to the U.S. Environmental Protection Agency (EPA) as an NOC, in accordance with Title 40 Code of Federal Regulations (CFR), Part 61, ''National Emission Standards for Hazardous Air Pollutants.'' The information required for submittal to the EPA is specified in 40 CFR 61.07. The potential emissions from this activity are estimated to provide less than 0.1 milliredyear total effective dose equivalent to the hypothetical offsite maximally exposed individual, and commencement is needed within a short time. Therefore, this application also is intended to provide notification of the anticipated date of initial startup in accordance with the requirement listed in 40 CFR 61.09(a)(1), and it is requested that approval of this application also will constitute EPA acceptance of this initial startup notification. Written notification of the actual date of initial startup, in accordance with the requirement listed in 40 CFR 61.09(a)(2), will be provided later. The activities described in this NOC are estimated to provide a potential offsite (unabated) total effective dose equivalent (TEDE) to the hypothetical maximally exposed individual (MEI) of 2.36 E-02 millirem per year.

  11. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    | NRC Officials Visit WIPP Tod A weekly e-newsletter for the Waste Isolation Pilot Plant team September 25, 2003 The Big Story Recertification - a work in progress Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 9-25-03 at 7:16 a.m.) 21 Shipments

  12. Thermal, chemical, and mass-transport processes induced in abyssal sediments by the emplacement of nuclear waste: experimental and modeling results

    SciTech Connect (OSTI)

    McVey, D.F.; Erickson, K.L.; Seyfried, W.

    1980-01-01

    This paper discusses heat and mass transport studies of marine red clay sediments being considered as a nuclear waste isolation medium. Numerical models indicate that for a maximum allowable sediment/canister interface temperature of 200 to 250/sup 0/C, the sediment can absorb about 1.5 kW initial power from waste in a 3 m long by 0.3 m dia canister buried 30 m in the sediment. Fluid displacement due to convection is found to be less than 1 m. Laboratory studies of the geochemical effects induced by heating sediment/seawater mixtures indicate that the canister and waste form must be designed to resist a hot, acid (pH 3 to 4) oxidizing environment. Since the thermally altered sediment volume of about 5.5 m/sup 3/ is small relative to the sediment volume overlying the canister, the acid and oxidizing conditions are not anticipated to effect the properties of the far field. Using sorption coefficient correlations, the migration of four nuclides /sup 239/Pu, /sup 137/Cs, /sup 129/I, and /sup 99/Tc were computer for a canister buried 30 m deep in a 60 m thick red clay sediment layer. It was found that the /sup 239/Pu and /sup 137/Cs are essentially completely contained in the sediments, while /sup 129/I and /sup 99/Tc broke through the 30 m of sediment in about 5000 years. The resultant peak injection rates of 4.6 x 10/sup -5/ ..mu..Ci/year-m/sup 2/ for /sup 129/I and 1.6 x 10/sup -2/ ..mu..Ci/year-m/sup 2/ for /sup 99/Tc were less than the natural radioactive flux of /sup 226/Ra (3.5 to 8.8 x 10/sup -4/ ..mu..Ci/year-m/sup 2/) and /sup 222/Rn (0.26 to 0.88 ..mu..Ci/year-m/sup 2/).

  13. Investigating potential efficiency improvement for light-duty transportation applications through simulation of an organic Rankine cycle for waste-heat recovery

    SciTech Connect (OSTI)

    Edwards, Kevin Dean; Wagner, Robert M

    2010-01-01

    Modern diesel engines used in light-duty transportation applications have peak brake thermal efficiencies in the range of 40-42% for high-load operation with substantially lower efficiencies at realistic road-load conditions. Thermodynamic energy and exergy analysis reveals that the largest losses from these engines are due to heat loss and combustion irreversibility. Substantial improvement in overall engine efficiency requires reducing or recovering these losses. Unfortunately, much of the heat transfer either occurs at relatively low temperatures resulting in large entropy generation (such as in the air-charge cooler), is transferred to low-exergy flow streams (such as the oil and engine coolant), or is radiated or convected directly to the environment. While there are significant opportunities for recovery from the exhaust and EGR cooler for heavy-duty applications, the potential benefits of such a strategy for light-duty applications are unknown due to transient operation, low-load operation at typical driving conditions, and the added mass of the system. We have developed an organic Rankine cycle model using GT-Suite to investigate the potential for efficiency improvement through waste-heat recovery from the exhaust and EGR cooler of a light-duty diesel engine. Results from steady-state and drive-cycle simulations are presented, and we discuss strategies to address operational difficulties associated with transient drive cycles and competition between waste-heat recovery systems, turbochargers, aftertreatment devices, and other systems for the limited thermal resources.

  14. A record of uranium-series transport at Nopal I, Sierra Pena Blanca, Mexico: Implications for natural uranium deposits and radioactive waste repositories

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

    Denton, J. S.; Goldstein, S. J.; Paviet, P.; Nunn, A. J.; Amato, R. S.; Hinrichs, K. A.

    2016-04-10

    Studies of uranium-series (U-series) disequilibria within and around ore deposits provide valuable information on the extent and timing of actinide mobility, via mineral-fluid interaction, over a range of spatial and temporal scales. Such information is useful in studies of analogs of high-level nuclear-waste repositories, as well as for mining and mineral extraction sites, locations of previous nuclear weapons testing, and legacy nuclear waste contamination. In this study we present isotope dilution mass spectrometry U-series measurements for fracture-fill materials (hematite, goethite, kaolinite, calcite, dolomite and quartz) from one such analog; the Nopal I uranium ore deposit situated at Peña Blanca inmore » the Chihuahua region of northern Mexico. The ore deposit is located in fractured, unsaturated volcanic tuff and fracture-fill materials from surface fractures as well as fractures in a vertical drill core have been analyzed. High uranium concentrations in the fracture-fill materials (between 12 and 7700 ppm) indicate uranium mobility and transport from the deposit. Furthermore, uranium concentrations generally decrease with horizontal distance away from the deposit but in this deposit there is no trend with depth below the surface.« less

  15. DWPF COAL-CARBON WASTE ACCEPTANCE CRITERIA LIMIT EVALUATION BASED ON EXPERIMENTAL WORK (TANK 48 IMPACT STUDY)

    SciTech Connect (OSTI)

    Lambert, D.; Choi, A.

    2010-10-15

    This report summarizes the results of both experimental and modeling studies performed using Sludge Batch 10 (SB10) simulants and FBSR product from Tank 48 simulant testing in order to develop higher levels of coal-carbon that can be managed by DWPF. Once the Fluidized Bed Steam Reforming (FBSR) process starts up for treatment of Tank 48 legacy waste, the FBSR product stream will contribute higher levels of coal-carbon in the sludge batch for processing at DWPF. Coal-carbon is added into the FBSR process as a reductant and some of it will be present in the FBSR product as unreacted coal. The FBSR product will be slurried in water, transferred to Tank Farm and will be combined with sludge and washed to produce the sludge batch that DWPF will process. The FBSR product is high in both water soluble sodium carbonate and unreacted coal-carbon. Most of the sodium carbonate is removed during washing but all of the coal-carbon will remain and become part of the DWPF sludge batch. A paper study was performed earlier to assess the impact of FBSR coal-carbon on the DWPF Chemical Processing Cell (CPC) operation and melter off-gas flammability by combining it with SB10-SB13. The results of the paper study are documented in Ref. 7 and the key findings included that SB10 would be the most difficult batch to process with the FBSR coal present and up to 5,000 mg/kg of coal-carbon could be fed to the melter without exceeding the off-gas flammability safety basis limits. In the present study, a bench-scale demonstration of the DWPF CPC processing was performed using SB10 simulants spiked with varying amounts of coal, and the resulting seven CPC products were fed to the DWPF melter cold cap and off-gas dynamics models to determine the maximum coal that can be processed through the melter without exceeding the off-gas flammability safety basis limits. Based on the results of these experimental and modeling studies, the presence of coal-carbon in the sludge feed to DWPF is found to have

  16. Chernobyl Studies Project - working group 7.0 environmental transport and health effects. Progress report, October 1993--January 1994

    SciTech Connect (OSTI)

    Hendrickson, S.M.

    1994-03-01

    The DOE-funded Chernobyl Studies Project was begun as part of a cooperative agreement between the US and the former USSR, (quote) To develop jointly methods to project rapidly the health effects of any future reactor accident (quote). Most of the initial tasks for this project are completed or near completion. The focus has now turned primarily to the issue of health effects from the Chernobyl accident. Currently, we are extensively engaged in case-control and cohort studies of thyroid diseases among Belarussian children and in the Ukraine. A major part of the effort is providing methods and applications of dose reconstruction and providing support and equipment for the medical teams. This document contains reports on progress in the following task areas: Management; External Dose; Hydrological Transport; Chromosome Painting Dosimetry; Stochastic Effects; Thyroid Studies; and Leukemia Studies.

  17. Estimate of Hanford Waste Rheology and Settling Behavior

    SciTech Connect (OSTI)

    Poloski, Adam P.; Wells, Beric E.; Tingey, Joel M.; Mahoney, Lenna A.; Hall, Mark N.; Thomson, Scott L.; Smith, Gary Lynn; Johnson, Michael E.; Meacham, Joseph E.; Knight, Mark A.; Thien, Michael G.; Davis, Jim J.; Onishi, Yasuo

    2007-10-26

    The U.S. Department of Energy (DOE) Office of River Protection’s Waste Treatment and Immobilization Plant (WTP) will process and treat radioactive waste that is stored in tanks at the Hanford Site. Piping, pumps, and mixing vessels have been selected to transport, store, and mix the high-level waste slurries in the WTP. This report addresses the analyses performed by the Rheology Working Group (RWG) and Risk Assessment Working Group composed of Pacific Northwest National Laboratory (PNNL), Bechtel National Inc. (BNI), CH2M HILL, DOE Office of River Protection (ORP) and Yasuo Onishi Consulting, LLC staff on data obtained from documented Hanford waste analyses to determine a best-estimate of the rheology of the Hanford tank wastes and their settling behavior. The actual testing activities were performed and reported separately in referenced documentation. Because of this, many of the required topics below do not apply and are so noted.

  18. Disposal of Rocky Flats residues as waste

    SciTech Connect (OSTI)

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

    1993-01-01

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

  19. Disposal of Rocky Flats residues as waste

    SciTech Connect (OSTI)

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

    1993-03-01

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

  20. Chernobyl Studies Project. Working Group 7.0, environmental transport and health effects. Progress report, February 1994

    SciTech Connect (OSTI)

    Hendrickson, S.M.

    1994-04-01

    The focus of the Chernobyl Studies Project has now turned to the issue of health effects from the Chernobyl accident. Currently, we are involved in and making progress on the case-control and co-hort studies of thyroid diseases among Belarussian children. Dosimetric aspects are a fundamental part of these studies. We are working to implement similar studies in Ukraine. A major part of the effort of these projects is supporting these studies, both by providing methods and applications of dose reconstruction and by providing support and equipment for the medical teams.

  1. Canyon Disposal Initiative - Numerical Modeling of Contaminant Transport from Grouted Residual Waste in the 221-U Facility (U Plant)

    SciTech Connect (OSTI)

    Rockhold, Mark L.; White, Mark D.; Freeman, Eugene J.

    2004-10-12

    This letter report documents initial numerical analyses conducted by PNNL to provide support for a feasibility study on decommissioning of the canyon buildings at Hanford. The 221-U facility is the first of the major canyon buildings to be decommissioned. The specific objective of this modeling effort was to provide estimates of potential rates of migration of residual contaminants out of the 221-U facility during the first 40 years after decommissioning. If minimal contaminant migration is predicted to occur from the facility during this time period, then the structure may be deemed to provide a level of groundwater protection that is essentially equivalent to the liner and leachate collection systems that are required at conventional landfills. The STOMP code was used to simulate transport of selected radionuclides out of a canyon building, representative of the 221-U facility after decommissioning, for a period of 40 years. Simulation results indicate that none of the selected radionuclides that were modeled migrated beyond the concrete structure of the facility during the 40-year period of interest. Jacques (2001) identified other potential contaminants in the 221-U facility that were not modeled, however, including kerosene, phenol, and various metals. Modeling of these contaminants was beyond the scope of this preliminary effort due to increased complexity. Simulation results indicate that contaminant release from the canyon buildings will be diffusion controlled at early times. Advection is expected to become much more important at later times, after contaminants have diffused out of the facility and into the surrounding soil environment. After contaminants have diffused out of the facility, surface infiltration covers will become very important for mitigating further transport of contaminants in the underlying vadose zone and groundwater.

  2. Greening Transportation

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

    Transportation Goal 2: Greening Transportation LANL supports and encourages employees to reduce their personal greenhouse gas emissions by offering various commuting and work schedule options. Our goal is to reduce emissions related to employee travel and commuting to and from work by 13 percent. Energy Conservation» Efficient Water Use & Management» High Performance Sustainable Buildings» Greening Transportation» Green Purchasing & Green Technology» Pollution Prevention» Science

  3. file://\\Bellview\TeamWorks\TRUTeamWorks.PDF

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

    Total shipments received at WIPP as of 8-25-03: 1,956 | Shipments expected this week: Hanford A weekly e-newsletter for the Waste Isolation Pilot Plant team August 25, 2003 The Big Story INEEL drum fire and Senate Bill S. 1424: questions and answers Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here

  4. file://\\Bellview\TeamWorks\TRUTeamWorks.htm

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

    30/03 Shipments expected this week: RFETS (11), SRS (4), Hanford (2) A weekly e-newsletter for the Waste Isolation Pilot Plant team October 30, 2003 ARROW-PAK Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e- mail. WIPP Shipments (as of 10/30/03 at 6:59 a.m.) Shipments

  5. file://\\Bellview\TeamWorks\TRUTeamWorks.htm

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

    6/03 | Shipments expected this week: RFETS (13), SRS (6) | A weekly e-newsletter for the Waste Isolation Pilot Plant team November 6, 2003 The Big Story FY03 cleanup and disposal accomplishments Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of

  6. http://bellview/TeamWorks/TRUTeamWorks.PDF

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

    Thursday, 9/4/03 | Total shipments received at WIPP: 1,978 | Shipments expected this week: Hanford (2), LA A weekly e-newsletter for the Waste Isolation Pilot Plant team September 4, 2003 The Big Story Get ready, set, go for 100 Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e

  7. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    Thursday, 9/11/03 | Total shipments received at WIPP: 2003 | Shipments expected this A weekly e-newsletter for the Waste Isolation Pilot Plant team September 11, 2003 The Big Story 2003 in 2003 Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of

  8. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    A weekly e-newsletter for the Waste Isolation Pilot Plant team September 18, 2003 The Big Story Characterization Operations completed at ANL-E Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 9-18-03 at 7:17 a.m.) 21 Shipments scheduled to arrive

  9. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    /03 | Shipments expected this week: Hanford (1), RFETS (11), SRS (6) | A weekly e-newsletter for the Waste Isolation Pilot Plant team October 2, 2003 The Big Story Laboratory setup at CEMRC is teamwork in action Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP

  10. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    9/03 | Shipments expected this week: Hanford (1), RFETS (11), SRS (6) | A weekly e-newsletter for the Waste Isolation Pilot Plant team October 9, 2003 The Big Story It's a whole new "WIPP Experience" Topics Characterization News Transportation News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e- mail. WIPP Shipments (as of

  11. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    16/03 | Shipments expected this week: ANL-E (2) , RFETS (11), SRS (6) | A weekly e-newsletter for the Waste Isolation Pilot Plant team October 16, 2003 The Big Story EM-6 to review WIPP baseline Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of

  12. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    3/03 | Shipments expected this week: RFETS (11), SRS (4), Hanford (2) | A weekly e-newsletter for the Waste Isolation Pilot Plant team October 23, 2003 Sealed sources: questions and answers Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 10/23/03

  13. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    13/03 | Shipments expected this week: RFETS (11), SRS (6) | WIPP welcomes new CBFO Deputy Ma A weekly e-newsletter for the Waste Isolation Pilot Plant team November 13, 2003 The Big Story Farewell to a leader Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP

  14. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    20/03 | Shipments expected this week: Hanford (2), RFETS (14), SRS (6) | A weekly e-newsletter for the Waste Isolation Pilot Plant team November 20, 2003 The Big Story WIPP welcomes Lloyd Piper Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of

  15. Colloidal agglomerates in tank sludge: Impact on waste processing

    SciTech Connect (OSTI)

    Bunker, B.C.; Martin, J.E.

    1998-06-01

    'Insoluble colloidal sludges in hazardous waste streams such as tank wastes can pose serious problems for waste processing, interfering with retrieval, transport, separation, and solidification procedures. Properties of sediment layers and sludge suspensions such as slurry viscosities, sedimentation rates, and final sediment densities can vary by orders of magnitude depending on the particle types present, the degree to which the particles agglomerate or stick to each other, and on a wide range of processing parameters such as solution shear rates, pH, salt content, and temperature. The objectives of this work are to: (1) understand the factors controlling the nature and extent of colloidal agglomeration under expected waste processing conditions; (2) determine how agglomeration phenomena influence physical properties relevant to waste processing including rheology, sedimentation, and filtration; and (3) develop strategies for optimizing processing conditions via control of agglomeration phenomena. Insoluble colloidal sludges in hazardous waste streams such as tank wastes can pose serious problems for waste processing, interfering with retrieval, transport, separation, and solidification procedures. Properties of sediment layers and sludge suspensions such as slurry viscosities, sedimentation rates, and final sediment densities can vary by orders of magnitude depending on the particle types present, the degree to which the particles agglomerate or stick to each other, and on a wide range of processing parameters such as solution shear rates, pH, salt content, and temperature. The objectives of this work are to: (1) understand the factors controlling the nature and extent of colloidal agglomeration under expected waste processing conditions; (2) determine how agglomeration phenomena influence physical properties relevant to waste processing including rheology, sedimentation, and filtration; and (3) develop strategies for optimizing processing conditions via control

  16. Waste Isolation Pilot Plant Typifies Optimizing Resources to...

    Office of Environmental Management (EM)

    Typifies Optimizing Resources to Maximize Results Waste Isolation Pilot Plant Typifies ... HalfPACT transportation packages on a Waste Isolation Pilot Plant (WIPP) truck are ...

  17. A study on chemical interactions between waste fluid, formation...

    Office of Scientific and Technical Information (OSTI)

    The drilling activities provided an opportunity to assess the fate and transport of waste ... geochemical reaction-path model to simulate fresh waste reacting with the formation. ...

  18. Waste Isolation Pilot Plant Update | Department of Energy

    Office of Environmental Management (EM)

    Update Waste Isolation Pilot Plant Update Waste Isolation Pilot Plant Update (578.15 KB) More Documents & Publications Transuranic Package Transporter (TRUPACT-III) Content Codes ...

  19. Integrated Waste Management | Department of Energy

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

    Consent-Based Siting » Integrated Waste Management Integrated Waste Management The Department envisions an integrated waste management system with storage, transportation, and disposal capabilities in order to safely and effectively manage our nation's spent nuclear fuel and high-level radioactive waste. The Department envisions an integrated waste management system with storage, transportation, and disposal capabilities in order to safely and effectively manage our nation's spent nuclear fuel

  20. Transportation Security | Department of Energy

    Office of Environmental Management (EM)

    Transportation Security More Documents & Publications Overview for Newcomers West Valley Demonstration Project Low-Level Waste Shipment Indiana Department of Homeland...

  1. Mixed waste: Proceedings

    SciTech Connect (OSTI)

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

    1993-12-31

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

  2. Attachment 1 - Performance Work Statement

    National Nuclear Security Administration (NNSA)

    including TTR. Waste acceptance services will be performed at the NNSS and at waste generator sites. DE-SOL-0005982 Attachment 1 Page 1 2. Scope of Work 2.1 Requirement: The EPS...

  3. A NEW RUSSIAN WASTE MANAGEMENT INSTALLATION

    SciTech Connect (OSTI)

    Griffith, Andrew; Engxy, Thor; Endregard, Monica; Schwab, Patrick; Nazarian, Ashot; Krumrine, Paul; Backe, Steinar; Gorin, Stephen; Evans, Brent

    2003-02-27

    waste in various conditions, treat it, package it in standard 200-liter drums, and load these drums into the new transportation and storage containers. The MPF has been designed, fabricated, and assembled at the fabrication site, the Zvezdochka Shipyard. It passed a demonstration test in September 2002. The entire MPF has been disassembled into its transportable modules, which are currently stored at the Zvezdochka Shipyard. In the spring of 2003, the MPF modules will be transported to the Polyarninsky Shipyard, where they will be reassembled and the facility will be cold tested. The site preparation work is already under way for the installation at the Polyarninsky Shipyard. An automatic radiation monitoring system, PICASSO-AMEC, has been developed and will be installed at Polyarninsky Shipyard as one of the elements of the installation. The radiation monitoring system is based on the software package PICASSO-3, developed by the Institute for Energy Technology in Norway. Treated waste f rom the MPF will require safe and secure storage. The Waste Storage Facility will be connected to the MPF, and it will be large enough to store all 400 of the new containers. Incoming waste boxes in overpacks will enter one part of the storage facility on trucks. Then they will be inspected and transferred into the MPF through the receiving area. Drums of processed waste in containers will be removed from the MPF and stacked in another part of the storage facility via a bridge crane. This facility will be designed and construction will begin during the winter of 2002/2003.

  4. Nuclear waste management. Quarterly progress report, January-March 1980

    SciTech Connect (OSTI)

    Platt, A.M.; Powell, J.A.

    1980-06-01

    Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)

  5. Relevance of biotic pathways to the long-term regulation of nuclear-waste disposal. Topical report on reference western arid low-level sites

    SciTech Connect (OSTI)

    McKenzie, D.H.; Cadwell, L.L.; Eberhardt, L.E.; Kennedy, W.E. Jr.; Peloquin, R.A.; Simmons, M.A.

    1982-10-01

    The purpose of the work reported here was to develop an order of magnitude estimate for the potential dose to man resulting from biotic transport mechanisms at a reference western arid low-level waste site. A description of the reference site is presented that includes the waste inventories, site characteristics and biological communities. Parameter values for biotic transport processes are based on data reported in current literature. Transport and exposure scenarios are developed for assessing biotic transport during 100 years following site closure. Calculations of radionuclide decay and waste container decomposition are made to estimate the quantities available for biotic transport. Dose to a man occupying the reference site following the 100 years of biotic transport are calculated. These dose estimates are compared to dose estimates for the intruder-agricultural scenario reported in the DEIS for 10 CFR 61 (NRC). Dose to man estimates as a result of biotic transport are estimated to be of the same order of magnitude as the dose resulting from the more commonly evaluated human intrusion scenario. The reported lack of potential importance of biotic transport at low-level waste sites in earlier assessment studies is not confirmed by the findings presented in this report. These results indicate that biotic transport has the potential to influence low-level waste site performance. Through biotic transport, radionuclides may be moved to locations where they can enter exposure pathways to man.

  6. Radioactive Material Transportation Practices Manual

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

    2008-06-04

    This Manual establishes standard transportation practices for the Department of Energy, including National Nuclear Security Administration to use in planning and executing offsite shipments of radioactive materials and waste. The revision reflects ongoing collaboration of DOE and outside organizations on the transportation of radioactive material and waste. Supersedes DOE M 460.2-1.

  7. Drift-Scale Radionuclide Transport

    SciTech Connect (OSTI)

    P.R. Dixon

    2004-02-17

    The purpose of this Model Report is to document two models for drift-scale radionuclide transport. This has been developed in accordance with ''Technical Work Plan for: Performance Assessment Unsaturated Zone'' (Bechtel SAIC Company, LLC (BSC) 2002 [160819]), which includes planning documents for the technical work scope, content, and management of this Model Report in Section 1.15, Work Package AUZM11, ''Drift-Scale Radionuclide Transport.'' The technical work scope for this Model Report calls for development of a process-level model and an abstraction model representing diffusive release from the invert to the rocks, partitioned between fracture and matrix, as compared to the fracture-release approach used in the Site Recommendation. The invert is the structure constructed in a drift to provide the floor of that drift. The plan for validation of the models documented in this Model Report is given in Section I-5 of Attachment I in BSC (2002 [160819]). Note that the model validation presented in Section 7 deviates from the technical work plan (BSC 2002 [160819], Section I-5) in that an independent technical review specifically for model validation has not been conducted, nor publication in a peer-reviewed journal. Model validation presented in Section 7 is based on corroboration with alternative mathematical models, which is also called out by the technical work plan (BSC 2002 [160819], Section I-5), and is sufficient based on the requirements of AP-SIII.10Q for model validation. See Section 7 for additional discussion. The phenomenon of flow and transport in the vicinity of the waste emplacement drift are evaluated in this model report under ambient thermal, chemical, and mechanical conditions. This includes the effects of water diversion around an emplacement drift and the flow and transport behavior expected in a fractured rock below the drift. The reason for a separate assessment of drift-scale transport is that the effects of waste emplacement drifts on flow

  8. Office of Civilian Radioactive Waste Management fiscal year 1996 annual report to Congress

    SciTech Connect (OSTI)

    1997-05-01

    In Fiscal Year 1996 a revised program strategy was developed that reflects Administration policy and responds to sharply reduced funding and congressional guidance while maintaining progress toward long-term objectives. The program is on track, working toward an early, comprehensive assessment of the viability of the Yucca Mountain site; more closely determining what will be required to incorporate defense waste into the waste management system; pursuing a market-driven strategy for waste acceptance, storage, and transportation; and preserving the core capability to respond to an interim storage contingency. Overall, the elements of an integrated system for managing the Nation`s spent fuel and high-level radioactive waste are emerging, more soundly conceived, and more modestly designed, as the OCRWM works toward the physical reality of waste shipments to Federal facilities.

  9. http://www.wipp.ws/TeamWorks/truteamworks.htm

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

    26/04 Shipments expected for the week of 02/22/04 through 2/28/04: Hanford (2), RFETS (11), SRS (6) A weekly e-newsletter for the Waste Isolation Pilot Plant team February 26, 2004 The Big Story WIPP impacts international Waste Management Symposium Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates.

  10. Transportation (technology 86)

    SciTech Connect (OSTI)

    Caplan, G.

    1986-01-01

    As railroads strive to cut operating and maintenance costs in an increasingly competitive transportation industry, AC propulsion and microprocessors figure prominently in their plans. New generations of locomotives and cars incorporating AC propulsion and microprocessors entered service last year, and the trend is destined to continue. Electronics is also making possible freight trains that rely on a telemetry unit at the rear to monitor airbrake pressure, instead of a manned caboose. AC is gaining acceptance because it permits simpler motors with fewer parts to wear and replace, and it saves energy by allowing the traction motors to work as generators during braking. Microprocessors are being used in locomotives not only to reduce energy waste through better regulation of traction motor currents and auxiliary devices such as cooling fans, but also to control engine speed, braking, and other functions.

  11. Working with SRNL - Our Facilities - ACTL

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

    development in the fields of waste management, environmental sciences, and biotechnology. ... and Environmental Science & Biotechnology directorates work at ACTL, conducting ...

  12. NREL: Transportation Research - News

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

    News NREL provides a number of transportation and hydrogen news sources. Transportation News Find news stories that highlight NREL's transportation research, development, and deployment (RD&D) activities, including work on vehicles and fuels. Hydrogen and Fuel Cells News Find news stories that highlight NREL's hydrogen RD&D activities, including work on fuel cell electric vehicle technologies. Transportation and Hydrogen Newsletter Stay up to date on NREL's RD&D of transportation and

  13. Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC).

    SciTech Connect (OSTI)

    Schultz, Peter Andrew

    2011-12-01

    The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. Achieving the objective of modeling the performance of a disposal scenario requires describing processes involved in waste form degradation and radionuclide release at the subcontinuum scale, beginning with mechanistic descriptions of chemical reactions and chemical kinetics at the atomic scale, and upscaling into effective, validated constitutive models for input to high-fidelity continuum scale codes for coupled multiphysics simulations of release and transport. Verification and validation (V&V) is required throughout the system to establish evidence-based metrics for the level of confidence in M&S codes and capabilities, including at the subcontiunuum scale and the constitutive models they inform or generate. This Report outlines the nature of the V&V challenge at the subcontinuum scale, an approach to incorporate V&V concepts into subcontinuum scale modeling and simulation (M&S), and a plan to incrementally incorporate effective V&V into subcontinuum scale M&S destined for use in the NEAMS Waste IPSC work flow to meet requirements of quantitative confidence in the constitutive models informed by subcontinuum scale phenomena.

  14. Twelfth annual US DOE low-level waste management conference

    SciTech Connect (OSTI)

    Not Available

    1990-01-01

    The papers in this document comprise the proceedings of the Department of Energy's Twelfth Annual Low-Level Radioactive Waste Management Conference, which was held in Chicago, Illinois, on August 28 and 29, 1990. General subjects addressed during the conference included: mixed waste, low-level radioactive waste tracking and transportation, public involvement, performance assessment, waste stabilization, financial assurance, waste minimization, licensing and environmental documentation, below-regulatory-concern waste, low-level radioactive waste temporary storage, current challenges, and challenges beyond 1990.

  15. Final environmental assessment for off-site transportation of low-level waste from four California sites under the management of the U.S. Department of Energy Oakland Operations Office

    SciTech Connect (OSTI)

    NONE

    1997-10-01

    The Department of Energy Oakland Operations Office (DOE/OAK) manages sites within California that generate Low Level Waste (LLW) in the course or routine site operations. It is the preference of the DOE to dispose of LLW at federally owned and DOE-operated disposal facilities; however, in some circumstances DOE Headquarters has determined that disposal at commercial facilities is appropriate, as long as the facility meets all regulatory requirements for the acceptance and disposal of LLW, including the passage of a DOE audit to determine the adequacy of the disposal site. The DOE would like to ship LLW from four DOE/OAK sites in California which generate LLW, to NRC-licensed commercial nuclear waste disposal facilities such as Envirocare in Clive, Utah and Chem Nuclear in Barnwell, South Carolina. Transportation impacts for shipment of LLW and MLLW from DOE Oakland sites to other DOE sites was included in the impacts identified in the Department`s Waste Management Programmatic Environmental Impact Statement (WM-PEIS), published in May, 1997, and determined to be low. The low impacts for shipment to commercial sites identified herein is consistent with the WM-PEIS results.

  16. Site Specific Single Shell Tank (SST) phase 1 RFI and CMS Work Plan Addendum for Waste Management B-BX-BY

    SciTech Connect (OSTI)

    ROGERS, P.M.

    2000-05-19

    This site-specific work plan addendum for WMA B-BX-BY addresses vadose zone characterization plans for collecting and analyzing sediment samples.

  17. Consolidation process for producing ceramic waste forms

    DOE Patents [OSTI]

    Hash, Harry C.; Hash, Mark C.

    2000-01-01

    A process for the consolidation and containment of solid or semisolid hazardous waste, which process comprises closing an end of a circular hollow cylinder, filling the cylinder with the hazardous waste, and then cold working the cylinder to reduce its diameter while simultaneously compacting the waste. The open end of the cylinder can be sealed prior to or after the cold working process. The preferred method of cold working is to draw the sealed cylinder containing the hazardous waste through a plurality of dies to simultaneously reduce the diameter of the tube while compacting the waste. This process provides a quick continuous process for consolidating hazardous waste, including radioactive waste.

  18. On Going TRU Waste Disposition

    SciTech Connect (OSTI)

    Cody, Tom

    2010-01-01

    The ongoing effort to contain dangerous, radioactive TRU waste. Under the Recovery Act, the Savannah River Site is able to safely test and transport these items to WIPP in Carlsbad, New Mexico.

  19. On Going TRU Waste Disposition

    ScienceCinema (OSTI)

    Cody, Tom

    2012-06-14

    The ongoing effort to contain dangerous, radioactive TRU waste. Under the Recovery Act, the Savannah River Site is able to safely test and transport these items to WIPP in Carlsbad, New Mexico.

  20. Final environmental assessment: TRU waste drum staging building, Technical Area 55, Los Alamos National Laboratory

    SciTech Connect (OSTI)

    1996-02-09

    Much of the US Department of Energy`s (DOE`s) research on plutonium metallurgy and plutonium processing is performed at Los Alamos National Laboratory (LANL), in Los Alamos, New Mexico. LANL`s main facility for plutonium research is the Plutonium Facility, also referred to as Technical Area 55 (TA-55). The main laboratory building for plutonium work within the Plutonium Facility (TA-55) is the Plutonium Facility Building 4, or PF-4. This Environmental Assessment (EA) analyzes the potential environmental effects that would be expected to occur if DOE were to stage sealed containers of transuranic (TRU) and TRU mixed waste in a support building at the Plutonium Facility (TA-55) that is adjacent to PF-4. At present, the waste containers are staged in the basement of PF-4. The proposed project is to convert an existing support structure (Building 185), a prefabricated metal building on a concrete foundation, and operate it as a temporary staging facility for sealed containers of solid TRU and TRU mixed waste. The TRU and TRU mixed wastes would be contained in sealed 55-gallon drums and standard waste boxes as they await approval to be transported to TA-54. The containers would then be transported to a longer term TRU waste storage area at TA-54. The TRU wastes are generated from plutonium operations carried out in PF-4. The drum staging building would also be used to store and prepare for use new, empty TRU waste containers.

  1. Nohemi Brewer Transportation Program Manager U.S. Department of Energy (DOE), National Nuclear Security

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

    Transportation Working Group Meeting November 16, 2012 Welcome! Page 2 Page 2Title ID 411- 11/16/2012 - Page 2 Meeting Purpose Provide forum for information exchange related to the Site-Wide Environmental Impact Statement (SWEIS) analysis of low-level/mixed low-level radioactive waste (LLW/MLLW) transportation to the Nevada National Security Site (NNSS) Page 3 Page 3Title ID 411- 11/16/2012 - Page 3 Transportation Working Group Members * State of Nevada * Counties * Cities * Tribal * Nevada

  2. Assessment of gas flammability in transuranic waste container

    SciTech Connect (OSTI)

    Connolly, M.J.; Loehr, C.A.; Djordjevic, S.M.; Spangler, L.R.

    1995-12-01

    The Safety Analysis Report for the TRUPACT-II Shipping Package [Transuranic Package Transporter-II (TRUPACT-II) SARP] set limits for gas generation rates, wattage limits, and flammable volatile organic compound (VOC) concentrations in transuranic (TRU) waste containers that would be shipped to the Waste Isolation Pilot Plant (WIPP). Based on existing headspace gas data for drums stored at the Idaho National Engineering Laboratory (INEL) and the Rocky Flats Environmental Technology Site (RFETS), over 30 percent of the contact-handled TRU waste drums contain flammable VOC concentrations greater than the limit. Additional requirements may be imposed for emplacement of waste in the WIPP facility. The conditional no-migration determination (NMD) for the test phase of the facility required that flame tests be performed if significant levels of flammable VOCs were present in TRU waste containers. This paper describes an approach for investigating the potential flammability of TRU waste drums, which would increase the allowable concentrations of flammable VOCS. A flammability assessment methodology is presented that will allow more drums to be shipped to WIPP without treatment or repackaging and reduce the need for flame testing on drums. The approach includes experimental work to determine mixture lower explosive limits (MLEL) for the types of gas mixtures observed in TRU waste, a model for predicting the MLEL for mixtures of VOCS, hydrogen, and methane, and revised screening limits for total flammable VOCs concentrations and concentrations of hydrogen and methane using existing drum headspace gas data and the model predictions.

  3. U.S. Department of Energy Awards Contracts for Waste Storage...

    Energy Savers [EERE]

    Contracts for Waste Storage Canisters for Yucca Mountain U.S. Department of Energy Awards Contracts for Waste ... of the Transportation, Aging, and Disposal (TAD) canister system. ...

  4. Relevance of biotic pathways to the long-term regulation of nuclear waste disposal: Phase 2, Final report

    SciTech Connect (OSTI)

    McKenzie, D.H.; Cadwell, L.L.; Kennedy, W.E. Jr.; Prohammer, L.A.; Simmons, M.A.

    1986-11-01

    The results reported here establish the relevance and propose a method for including biotic transport in the assessment and licensing process for commercial low-level waste disposal sites. Earlier work identified the biotic transport mechanisms and process scenarios linking biotic transport with dose to man, and developed models for assessment of impacts. Model modification and improvement efforts in enhancing the ability to represent soil erosion and soil transport within the trench cover. Two alternative hypotheses on plant root uptake were incorporated into the model to represent transport of radionuclides by roots that penetrate the buried waste. Enhancements were also made to the scenario for future site intruder activities. Representation of waste package decomposition in the model was confirmed as the best available alternative. Results from sensitivity analyses indicate that additional information is needed to evaluate the alternative hypotheses for plant root uptake of buried wastes. Site-specific evaluations of the contribution from biotic transport to the potential dose to man establish the relevance in the assessment process. The BIOPORT/MAXI1 computer software package is proposed for dose assessments of commercial low-level waste disposal sites.

  5. Relevance of biotic pathways to the long-term regulation of nuclear waste disposal. Estimation of radiation dose to man resulting from biotic transport: the BIOPORT/MAXI1 software package. Volume 5

    SciTech Connect (OSTI)

    McKenzie, D.H.; Cadwell, L.L.; Gano, K.A.; Kennedy, W.E. Jr.; Napier, B.A.; Peloquin, R.A.; Prohammer, L.A.; Simmons, M.A.

    1985-10-01

    BIOPORT/MAXI1 is a collection of five computer codes designed to estimate the potential magnitude of the radiation dose to man resulting from biotic transport processes. Dose to man is calculated for ingestion of agricultural crops grown in contaminated soil, inhalation of resuspended radionuclides, and direct exposure to penetrating radiation resulting from the radionuclide concentrations established in the available soil surface by the biotic transport model. This document is designed as both an instructional and reference document for the BIOPORT/MAXI1 computer software package and has been written for two major audiences. The first audience includes persons concerned with the mathematical models of biological transport of commercial low-level radioactive wastes and the computer algorithms used to implement those models. The second audience includes persons concerned with exercising the computer program and exposure scenarios to obtain results for specific applications. The report contains sections describing the mathematical models, user operation of the computer programs, and program structure. Input and output for five sample problems are included. In addition, listings of the computer programs, data libraries, and dose conversion factors are provided in appendices.

  6. Hanford Site Secondary Waste Roadmap

    SciTech Connect (OSTI)

    Westsik, Joseph H.

    2009-01-29

    performance requirements, waste composition, preliminary waste form screening, waste form development, process design and support, and validation. The regulatory and performance requirements activity will provide the secondary waste-form performance requirements. The waste-composition activity will provide workable ranges of secondary waste compositions and formulations for simulants and surrogates. Preliminary waste form screening will identify candidate waste forms for immobilizing the secondary wastes. The waste form development activity will mature the waste forms, leading to a selected waste form(s) with a defensible understanding of the long-term release rate and input into the critical decision process for a secondary waste treatment process/facility. The process and design support activity will provide a reliable process flowsheet and input to support a robust facility design. The validation effort will confirm that the selected waste form meets regulatory requirements. The final outcome of the implementation of the secondary waste roadmap is the compliant, effective, timely, and cost-effective disposal of the secondary wastes. The work necessary to address the programmatic, regulatory, and technical risks and uncertainties identified through the Secondary Waste Roadmap Workshop are assembled into several program needs elements. Programmatic/Regulatory needs include: • Select and deploy Hanford tank waste supplemental treatment technology • Provide treatment capability for secondary waste streams from tank waste treatment • Develop consensus on secondary waste form acceptance. Technology needs include: • Define secondary waste composition ranges and uncertainties • Identify and develop waste forms for secondary waste immobilization and disposal • Develop test methods to characterize secondary waste form performance. Details for each of these program elements are provided.

  7. DuraLith Alkali-Aluminosilicate Geopolymer Waste Form Testing for Hanford Secondary Waste

    SciTech Connect (OSTI)

    Gong, W. L.; Lutz, Werner; Pegg, Ian L.

    2011-07-21

    The primary objective of the work reported here was to develop additional information regarding the DuraLith alkali aluminosilicate geopolymer as a waste form for liquid secondary waste to support selection of a final waste form for the Hanford Tank Waste Treatment and Immobilization Plant secondary liquid wastes to be disposed in the Integrated Disposal Facility on the Hanford Site. Testing focused on optimizing waste loading, improving waste form performance, and evaluating the robustness of the waste form with respect to waste variability.

  8. Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)

    SciTech Connect (OSTI)

    D'Amico, E. L; Edmiston, D. R.; O'Leary, G. A.; Rivera, M. A.; Steward, D. M.

    2006-07-01

    In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

  9. Mixed waste characterization reference document

    SciTech Connect (OSTI)

    1997-09-01

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

  10. Federal-Contractor Partnership Allows Continued Waste Processing...

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

    They soon finished the inventory of lower-level radioactive waste and began addressing waste streams with higher levels of radioactivity. However, to ensure a safe work ...

  11. Savannah River Site Liquid Waste Contractor Earns Excellent Performanc...

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

    on key deliverables directly tied to the startup and integration of the Salt Waste ... River Site SRR employees work through the Lean process. EM's Liquid Waste Contractor ...

  12. Independent Oversight Review, Waste Isolation Pilot Plant - April...

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

    April 2013 Independent Oversight Review, Waste Isolation Pilot Plant - April 2013 April 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control Activities The...

  13. Relevance of biotic pathways to the long-term regulation of nuclear waste disposal. Topical report on reference eastern humid low-level sites

    SciTech Connect (OSTI)

    McKenzie, D.H.; Cadwell, L.L.; Eberhardt, L.E.; Kennedy, W.E. Jr.; Peloquin, R.A.; Simmons, M.A.

    1983-01-01

    The purpose of the work reported here was to develop an order-of-magnitude estimate for the potential dose to man resulting from biotic transport mechanisms at a humid reference low-level waste site in the eastern US. A description of the reference site is presented that includes the waste inventories, site characteristics and biological communites. Parameter values for biotic transport processes are based on data reported in current literature. Transport and exposure scenarios are developed for assessing biotic transport during 500 years following site closure. Calculations of radionuclide decay and waste container decomposition are made to estimate the quantities available for biotic transport. Doses to man are calculated for the biological transport of radionucludes at the reference site after loss of institutional control. These dose estimates are compared to dose estimates we calculated for the intruder-agricultural scenarios reported in the DEIS for 10 CFR 61 (NRC). Dose to man estimates as a result of cumulative biotic transport are calculated to be of the same order-of-magnitude as the dose resulting from the more commonly evaluated human intrusion scenario. The reported lack of potential importance of biotic transport at low-level waste sites in earlier assessment studies is not confirmed by findings presented in this report. Through biotic transport, radionuclides can be moved to locations where they can enter exposure pathways to man.

  14. Tank Waste Committee Page 1

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

    ... Decisions on orphan waste around the DOE complex could trump work occurring at the Hanford Site. There is a large issue manager group that will work on refining the advice using ...

  15. Formulation and Analysis of Compliant Grouted Waste Forms for SHINE Waste Streams

    SciTech Connect (OSTI)

    Ebert, William; Pereira, Candido; Heltemes, Thad A.; Youker, Amanda; Makarashvili, Vakhtang; Vandegrift, George F.

    2014-01-01

    Optional grouted waste forms were formulated for waste streams generated during the production of 99Mo to be compliant with low-level radioactive waste regulations. The amounts and dose rates of the various waste form materials that would be generated annually were estimated and used to determine the effects of various waste processing options, such as the of number irradiation cycles between uranium recovery operations, different combinations of waste streams, and removal of Pu, Cs, and Sr from waste streams for separate disposition (which is not evaluated in this report). These calculations indicate that Class C-compliant grouted waste forms can be produced for all waste streams. More frequent uranium recovery results in the generation of more chemical waste, but this is balanced by the fact that waste forms for those waste streams can accommodate higher waste loadings, such that similar amounts of grouted waste forms are required regardless of the recovery schedule. Similar amounts of grouted waste form are likewise needed for the individual and combined waste streams. Removing Pu, Cs, and Sr from waste streams lowers the waste form dose significantly at times beyond about 1 year after irradiation, which may benefit handling and transport. Although these calculations should be revised after experimentally optimizing the grout formulations and waste loadings, they provide initial guidance for process development.

  16. TeamWorks 8-25-05

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

    ... Readying for RH One year to go before the first RH waste arrives at WIPP. September 2006 ... have a lot of work to do," says Randy Britain, manager of waste operations. "But, ...

  17. Optimisation of the Management of Higher Activity Waste in the UK - 13537

    SciTech Connect (OSTI)

    Walsh, Ciara; Buckley, Matthew

    2013-07-01

    The Upstream Optioneering project was created in the Nuclear Decommissioning Authority (UK) to support the development and implementation of significant opportunities to optimise activities across all the phases of the Higher Activity Waste management life cycle (i.e. retrieval, characterisation, conditioning, packaging, storage, transport and disposal). The objective of the Upstream Optioneering project is to work in conjunction with other functions within NDA and the waste producers to identify and deliver solutions to optimise the management of higher activity waste. Historically, optimisation may have occurred on aspects of the waste life cycle (considered here to include retrieval, conditioning, treatment, packaging, interim storage, transport to final end state, which may be geological disposal). By considering the waste life cycle as a whole, critical analysis of assumed constraints may lead to cost savings for the UK Tax Payer. For example, it may be possible to challenge the requirements for packaging wastes for disposal to deliver an optimised waste life cycle. It is likely that the challenges faced in the UK are shared in other countries. It is therefore likely that the opportunities identified may also apply elsewhere, with the potential for sharing information to enable value to be shared. (authors)

  18. Low-level-waste-form criteria

    SciTech Connect (OSTI)

    Barletta, R.E.; Davis, R.E.

    1982-01-01

    Efforts in five areas are reported: technical considerations for a high-integrity container for resin wastes; permissible radionuclide loadings for organic ion exchange resin wastes; technical factors affecting low-level waste form acceptance requirements of the proposed 10 CFR 61 and draft BTP; modeling of groundwater transport; and analysis of soils from low-level waste disposal sites (Barnwell, Hanford, and Sheffield). (DLC)

  19. Transportation Baseline Report

    SciTech Connect (OSTI)

    Fawcett, Ricky Lee; Kramer, George Leroy Jr.

    1999-12-01

    The National Transportation Program 1999 Transportation Baseline Report presents data that form a baseline to enable analysis and planning for future Department of Energy (DOE) Environmental Management (EM) waste and materials transportation. In addition, this Report provides a summary overview of DOEs projected quantities of waste and materials for transportation. Data presented in this report were gathered as a part of the IPABS Spring 1999 update of the EM Corporate Database and are current as of July 30, 1999. These data were input and compiled using the Analysis and Visualization System (AVS) which is used to update all stream-level components of the EM Corporate Database, as well as TSD System and programmatic risk (disposition barrier) information. Project (PBS) and site-level IPABS data are being collected through the Interim Data Management System (IDMS). The data are presented in appendices to this report.

  20. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-01

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In

  1. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-06

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In

  2. Transportation Storage Interface | Department of Energy

    Office of Environmental Management (EM)

    Storage Interface Transportation Storage Interface Regulation of Future Extended Storage and Transportation. Transportation Storage Interface (891.2 KB) More Documents & Publications Gap Analysis to Support Extended Storage of Used Nuclear Fuel Status Update: Extended Storage and Transportation Waste Confidence Activities Related to Storage of Spent Nuclear Fuel

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

    Office of Environmental Management (EM)

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

  4. Annual Report - FY 2000, Radioactive Waste Shipments to and from the Nevada Test Site, March 2001

    SciTech Connect (OSTI)

    U.S. Department of Energy, Nevada Operations Office

    2001-03-01

    This document reports the low-level radioactive waste, mixed low-level radioactive waste, and Polychlorinated Biphenyl contaminated low-level waste transported to or from the Nevada Test Site during fiscal year 2000.

  5. Improving D&D Planning and Waste Management with Cutting and Packaging Simulation

    SciTech Connect (OSTI)

    Richard H. Meservey; Jean-Louis Bouchet

    2005-08-01

    The increased amount of decontamination and decommissioning (D&D) being performed throughout the world not only strains nuclear cleanup budgets, but places severe demands on the capacities of nuclear waste disposal sites. Although budgets and waste disposal sites have been able to accommodate the demand thus far, the increasing number of large facilities being decommissioned will cause major impacts to the waste disposal process. It is thus imperative that new and innovative technologies are applied within the D&D industry to reduce costs and waste disposal requirements for the decommissioning of our inventory of large and aging nuclear facilities. One of the most significant problems reactor owner’s deal with is the accurate determination of the types and volumes of wastes that will be generated during decommissioning of their facilities. Waste disposal costs, restrictions, and transportation issues can account for as much as 30% of the total costs to decommission a facility and thus it is very important to have accurate waste volume estimates. The use of simulation technologies to estimate and reduce decommissioning waste volumes provides a new way to manage risks associated with this work. Simulation improves the process by allowing facility owners to obtain accurate estimates of the types and amounts of waste prior to starting the actual D&D work. This reduces risk by permitting earlier and better negotiations with the disposal sites, and more time to resolve transportation issues. While simulation is a tool to be used by the D&D contractors, its real value is in reducing risks and costs to the reactor owners.

  6. Tank Waste and Waste Processing | Department of Energy

    Office of Environmental Management (EM)

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

  7. Contents TRU Waste Celebration

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

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

  8. Isotope Program Transportation | Department of Energy

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

    Isotope Program Transportation Isotope Program Transportation Isotope Program Transportation (894.11 KB) More Documents & Publications Nuclear Fuel Storage and Transportation Planning Project Overview Section 180(c) Ad Hoc Working Group DOE Office of Nuclear Energy

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

    SciTech Connect (OSTI)

    Ramsey, William Gene

    2013-08-15

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

  10. Waste acceptance criteria for the Waste Isolation Pilot Plant. Revision 4

    SciTech Connect (OSTI)

    Not Available

    1991-12-01

    This Revision 4 of the Waste Acceptance Criteria (WAC), WIPP-DOE-069, identifies and consolidates existing criteria and requirements which regulate the safe handling and preparation of Transuranic (TRU) waste packages for transportation to and emplacement in the Waste Isolation Pilot Plant (WIPP). This consolidation does not invalidate any existing certification of TRU waste to the WIPP Operations and Safety Criteria (Revision 3 of WIPP-DOE--069) and/or Transportation: Waste Package Requirements (TRUPACT-II Safety Analysis Report for Packaging [SARP]). Those documents being consolidated, including Revision 3 of the WAC, currently support the Test Phase.

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

    SciTech Connect (OSTI)

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

    1996-02-01

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

  12. Working Group Report on - Space Nuclear Power Systems and Nuclear...

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

    Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D "Even ...

  13. Quality Assurance Plan for Transportation Management Division Transportation Training Programs

    SciTech Connect (OSTI)

    Not Available

    1994-10-01

    The U.S. Department of Transportation (DOT) implemented new rules requiring minimum levels of training for certain key individuals who handle, package, transport, or otherwise prepare hazardous materials for transportation. In response to these rules, the U.S. Department of Energy (DOE), Transportation Management Division (TMD), has developed a transportation safety training program. This program supplies designed instructional methodology and course materials to provide basic levels of DOT training to personnel for whom training has become mandatory. In addition, this program provides advanced hazardous waste and radioactive material packaging and transportation training to help personnel achieve proficiency and/or certification as hazardous waste and radioactive material shippers. This training program does not include site-specific or task-specific training beyond DOT requirements.

  14. NREL: Transportation Research - Transportation Deployment Support

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

    Transportation Deployment Support Photo of a car parked in front of a monument. A plug-in electric vehicle charges near the Thomas Jefferson Memorial in Washington, D.C. Photo from Julie Sutor, NREL NREL's transportation deployment team works with vehicle fleets, fuel providers, and other transportation stakeholders to help deploy alternative and renewable fuels, advanced vehicles, fuel economy improvements, and fleet-level efficiencies that reduce emissions and petroleum dependence. In

  15. Microsoft Word - FINAL Transportation Award.doc

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

    U.S. DEPARTMENT OF ENERGY AWARDS CONTRACT FOR TRANSURANIC WASTE TRANSPORTATION SERVICES Carlsbad, NM, March 14, 2007 - The U.S. Department of Energy (DOE) today awarded a contract to CAST Specialty Transportation of Henderson, Colorado valued at $96.7M to provide transportation services for the Waste Isolation Pilot Plant (WIPP). This notification is for the first of two contracts to be awarded for these services. The second award will be announced separately at a later date. "These

  16. TRUTeamWorks 08-05-04

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

    Waste Isolation Pilot Plant team Transportation and disposal ... engineer in the U.S. Naval Nuclear Propul- sion Program. ... To everyone else, thank you. John Gran The Safety Awareness ...

  17. Understanding radioactive waste (Technical Report) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear ...

  18. Mixing Processes in High-Level Waste Tanks (Technical Report...

    Office of Scientific and Technical Information (OSTI)

    with transport in free and wall jets modeled using standard integral techniques. ... of fuel and oxygen concentrations in DOE high-level waste tanks following loss of ...

  19. Y-12 National Security Complex's Waste Diversion Efforts, OAS...

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

    Energy, and Transportation Management, mandates that each Federal facility ... and a 50 percent rate for non-hazardous solid waste, by the end of Fiscal Year (FY) 2015. ...

  20. Hanford site transuranic waste certification plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-05-12

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of U.S. Department of Energy (DOE) Order 5820.2A, ''Radioactive Waste Management, and the Waste Acceptance Criteria for the Waste Isolation Pilot Plant' (DOE 1996d) (WIPP WAC). The WIPP WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WIPP WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their management of TRU waste and TRU waste shipments before transferring waste to WIPP. The Hanford Site must also ensure that its TRU waste destined for disposal at WIPP meets requirements for transport in the Transuranic Package Transporter41 (TRUPACT-11). The U.S. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-I1 requirements in the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (NRC 1997) (TRUPACT-I1 SARP).

  1. Physical Properties of Hanford Transuranic Waste

    SciTech Connect (OSTI)

    Berg, John C.

    2010-03-25

    The research described herein was undertaken to provide needed physical property descriptions of the Hanford transuranic tank sludges under conditions that might exist during retrieval, treatment, packaging and transportation for disposal. The work addressed the development of a fundamental understanding of the types of systems represented by these sludge suspensions through correlation of the macroscopic rheological properties with particle interactions occurring at the colloidal scale in the various liquid media. The results of the work have advanced existing understanding of the sedimentation and aggregation properties of complex colloidal suspensions. Bench scale models were investigated with respect to their structural, colloidal and rheological properties that should be useful for the development and optimization of techniques to process the wastes at various DOE sites.

  2. Slurry Retrieval, Pipeline Transport & Plugging and Mixing Workshop

    Office of Environmental Management (EM)

    Gary L. Smith - Office of Waste Processing (EM-21) Slurry Retrieval, Pipeline Transport & Plugging and Mixing Workshop 1 Dr. Gary L. Smith - Office of Waste Processing (EM-21) Dr. ...

  3. Packaging, Transportation and Recycling of NPP Condenser Modules - 12262

    SciTech Connect (OSTI)

    Polley, G.M.

    2012-07-01

    Perma-Fix was awarded contract from Energy Northwest for the packaging, transportation and disposition of the condenser modules, water boxes and miscellaneous metal, combustibles and water generated during the 2011 condenser replacement outage at the Columbia Generating Station. The work scope was to package the water boxes and condenser modules as they were removed from the facility and transfer them to the Perma-Fix Northwest facility for processing, recycle of metals and disposition. The condenser components were oversized and overweight (the condenser modules weighed ∼102,058 kg [225,000 lb]) which required special equipment for loading and transport. Additional debris waste was packaged in inter-modals and IP-1 boxes for transport. A waste management plan was developed to minimize the generation of virtually any waste requiring landfill disposal. The Perma-Fix Northwest facility was modified to accommodate the ∼15 m [50-ft] long condenser modules and equipment was designed and manufactured to complete the disassembly, decontamination and release survey. The condenser modules are currently undergoing processing for free release to a local metal recycler. Over three millions pounds of metal will be recycled and over 95% of the waste generated during this outage will not require land disposal. There were several elements of this project that needed to be addressed during the preparation for this outage and the subsequent packaging, transportation and processing. - Staffing the project to support 24/7 generation of large components and other wastes. - The design and manufacture of the soft-sided shipping containers for the condenser modules that measured ∼15 m X 4 m X 3 m [50 ft X 13 ft X 10 ft] and weighed ∼102,058 kg [225,000 lbs] - Developing a methodology for loading the modules into the shipping containers. - Obtaining a transport vehicle for the modules. - Designing and modifying the processing facility. - Movement of the modules at the processing

  4. The Integrated Waste Tracking System - A Flexible Waste Management Tool

    SciTech Connect (OSTI)

    Anderson, Robert Stephen

    2001-02-01

    The US Department of Energy (DOE) Idaho National Engineering and Environmental Laboratory (INEEL) has fully embraced a flexible, computer-based tool to help increase waste management efficiency and integrate multiple operational functions from waste generation through waste disposition while reducing cost. The Integrated Waste Tracking System (IWTS)provides comprehensive information management for containerized waste during generation,storage, treatment, transport, and disposal. The IWTS provides all information necessary for facilities to properly manage and demonstrate regulatory compliance. As a platformindependent, client-server and Web-based inventory and compliance system, the IWTS has proven to be a successful tracking, characterization, compliance, and reporting tool that meets the needs of both operations and management while providing a high level of management flexibility.

  5. Contact-Handled and Remote-Handled Transuranic Waste Packaging

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

    2011-08-09

    Provides specific instructions for packaging and/or repackaging contact-handled transuranic (CH-TRU) and remote-handled transuranic (RH-TRU) waste in a manner consistent with DOE O 435.1, Radioactive Waste Management, DOE M 435.1-1 Chg 1, Radioactive Waste Management Manual, CH-TRU and RH-TRU waste transportation requirements, and Waste Isolation Pilot Plant (WIPP) programmatic requirements. Does not cancel/supersede other directives.

  6. Nuclear waste management. Quarterly progress report, July-September 1980

    SciTech Connect (OSTI)

    Chikalla, T.D.

    1980-11-01

    Research is reported on: high-level waste immobilization, alternative waste forms, TRU waste immobilization and decontamination, krypton solidification, thermal outgassing, /sup 129/I fixation, unsaturated zone transport, well-logging instrumentation, waste management system and safety studies, effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, backfill material, spent fuel storage (criticality), barrier sealing and liners for U mill tailings, and revegetation of inactive U tailings sites. (DLC)

  7. The highly successful safe remediation of the Fernald waste pits undertaken under the privatization model

    SciTech Connect (OSTI)

    Cherry, Mark; Lojek, Dave; Murphy, Con

    2003-02-23

    Remediation of eight waste pits at the Department of Energy (DOE) Fernald site, located northwest of Cincinnati, Ohio, involves excavating approximately one million tonnes in-situ of low-level waste which were placed in pits during Fernald's production era. This unique project, one of the largest in the history of CERCLA/Superfund, includes uranium and thorium contaminated waste, soils and sludges. These wet soils and sludges are thermally dried in a processing facility to meet Department of Transportation (DOT) transportation and disposal facility waste acceptance criteria, loaded into railcars and shipped to the Envirocare waste disposal facility at Clive, Utah. This project is now approximately 60% complete with more than 415,000 tonnes (460,000 tons) of waste material safely shipped in 74 unit trains to Envirocare. Work is scheduled to be completed in early 2005. Success to date demonstrates that a major DOE site remediation project can be safely and successfully executed in partnership with private industry, utilizing proven commercial best practices, existing site labor resources and support of local stakeholders. In 1997 under the DOE's privatization initiative, Fluor Fernald, Inc. (Fluor Fernald) solicited the services of the remediation industry to design, engineer, procure, construct, own and operate a facility that would undertake the remediation of the waste pits. The resulting procurement was awarded to IT Corporation, currently Shaw Environmental and Infrastructure, Inc. (Shaw). The contractor was required to finance the procurement and construction of its facilities and infrastructure. The contract was performance-based and payment would be made on the successful loadout of the waste from the facility on a per-ton basis meeting the Envirocare waste acceptance criteria. This paper details the performance to date, the challenges encountered, and the seamless partnering between DOE, the Environmental Protection Agency (EPA), Fluor Fernald, Shaw, labor

  8. HYDROGEN GENERATION FROM SLUDGE SAMPLE BOTTLES CAUSED BY RADIOLYSIS AND CHEMISTRY WITH CONCETNRATION DETERMINATION IN A STANDARD WASTE BOX (SWB) OR DRUM FOR TRANSPORT

    SciTech Connect (OSTI)

    RILEY DL; BRIDGES AE; EDWARDS WS

    2010-03-30

    A volume of 600 mL of sludge, in 4.1 L sample bottles (Appendix 7.6), will be placed in either a Super Pig (Ref. 1) or Piglet (Ref. 2, 3) based on shielding requirements (Ref. 4). Two Super Pigs will be placed in a Standard Waste Box (SWB, Ref. 5), as their weight exceeds the capacity of a drum; two Piglets will be placed in a 55-gallon drum (shown in Appendix 7.2). The generation of hydrogen gas through oxidation/corrosion of uranium metal by its reaction with water will be determined and combined with the hydrogen produced by radiolysis. The hydrogen concentration in the 55-gallon drum and SWB will be calculated to show that the lower flammability limit of 5% hydrogen is not reached. The inner layers (i.e., sample bottle, bag and shielded pig) in the SWB and drum will be evaluated to assure no pressurization occurs as the hydrogen vents from the inner containers (e.g., shielded pigs, etc.). The reaction of uranium metal with anoxic liquid water is highly exothermic; the heat of reaction will be combined with the source term decay heat, calculated from Radcalc, to show that the drum and SWB package heat load limits are satisfied. This analysis does five things: (1) Estimates the H{sub 2} generation from the reaction of uranium metal with water; (2) Estimates the H{sub 2} generation from radiolysis (using Radcalc 4.1); (3) Combines both H{sub 2} generation amounts, from Items 1 and 2, and determines the percent concentration of H{sub 2} in the interior of an SWB with two Super Pigs, and the interior of a 55-gallon drum with two Piglets; (4) From the combined gas generation rate, shows that the pressure at internal layers is minimal; and (5) Calculates the maximum thermal load of the package, both from radioactive decay of the source and daughter products as calculated/reported by Radcalc 4.1, and from the exothermic reaction of uranium metal with water.

  9. Transmutation calculations for the accelerator transmutation of waste (ATW) program

    SciTech Connect (OSTI)

    Wilson, W.B.; Arthur, E.D.; Bowman, C.D.; Engel, L.N.; England, T.R.; Hughes, H.G.; Lisowski, P.W.; Perry, R.T.

    1991-01-01

    The disposal of radioactive waste by the transmutation of long-lived radionuclides is being considered; now using neutrons produced with an intense beam of 1.6-GeV protons on a Pb-Bi target. Study teams have been active in the areas of accelerator design, beam transport, radiation transport, transmutation, fluid flow and heat transfer, process chemistry and system analyses. Work is of a preliminary and developmental nature. Here we describe these preliminary efforts in transmutation calculations; the tools developed, status of basic nuclear data, and some early results. These calculations require the description of the intensity and spectrum of neutrons produced by the beam, the distribution of nuclides produced in the medium-energy reactions, the transport of particles produced by the beam, the transmutation of the target materials and transmutation products, and the decay properties of the inventory of radionuclides produced.

  10. Spring 2010 National Transportation Stakeholder Forum Meetings, Illinois |

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

    Department of Energy 0 National Transportation Stakeholder Forum Meetings, Illinois Spring 2010 National Transportation Stakeholder Forum Meetings, Illinois NTSF Spring 2010 Agenda Final Agenda NTSF Presentations Applying Risk Communication to the Transportation of Radioactive Materials Department of Energy Office of Science Transportation Overview Department of Transportation Pipeline and Hazardous Materials Safety Administration Activities EM Waste and Materials Disposition &

  11. Radioactive waste management treatments: A selection for the Italian scenario

    SciTech Connect (OSTI)

    Locatelli, G. [Univ. of Lincoln, Lincoln School of Engineering, Brayford Pool - Lincoln LN6 7TS (United Kingdom); Mancini, M. [Politecnico di Milano, Dept. of Management, Economics and Industrial Engineering, Via Lambruschini 4/B, Milano (Italy); Sardini, M. [Politecnico di Milano, Dept. of Energy, Via Lambruschini 4, Milano (Italy)

    2012-07-01

    The increased attention for radioactive waste management is one of the most peculiar aspects of the nuclear sector considering both reactors and not power sources. The aim of this paper is to present the state-of-art of treatments for radioactive waste management all over the world in order to derive guidelines for the radioactive waste management in the Italian scenario. Starting with an overview on the international situation, it analyses the different sources, amounts, treatments, social and economic impacts looking at countries with different industrial backgrounds, energetic policies, geography and population. It lists all these treatments and selects the most reasonable according to technical, economic and social criteria. In particular, a double scenario is discussed (to be considered in case of few quantities of nuclear waste): the use of regional, centralized, off site processing facilities, which accept waste from many nuclear plants, and the use of mobile systems, which can be transported among multiple nuclear sites for processing campaigns. At the end the treatments suitable for the Italian scenario are presented providing simplified work-flows and guidelines. (authors)

  12. Expert System for Building TRU Waste Payloads - 13554

    SciTech Connect (OSTI)

    Bruemmer, Heather; Slater, Bryant

    2013-07-01

    The process for grouping TRU waste drums into payloads for shipment to the Waste Isolation Pilot Plant (WIPP) for disposal is a very complex process. Transportation and regulatory requirements must be met, along with striving for the goals of shipment efficiency: maximize the number of waste drums in a shipment and minimize the use of empty drums which take up precious underground storage space. The restrictions on payloads range from weight restrictions, to limitations on flammable gas in the headspace, to minimum TRU alpha activity concentration requirements. The Overpack and Payload Assistant Tool (OPAT) has been developed as a mixed-initiative intelligent system within the WIPP Waste Data System (WDS) to guide the construction of multiple acceptable payloads. OPAT saves the user time while at the same time maximizes the efficiency of shipments for the given drum population. The tool provides the user with the flexibility to tune critical factors that guide OPAT's operation based on real-time feedback concerning the results of the execution. This feedback complements the user's external knowledge of the drum population (such as location of drums, known challenges, internal shipment goals). This work demonstrates how software can be utilized to complement the unique domain knowledge of the users. The mixed-initiative approach combines the insight and intuition of the human expert with the proficiency of automated computational algorithms. The result is the ability to thoroughly and efficiently explore the search space of possible solutions and derive the best waste management decision. (authors)

  13. Radioactive waste material melter apparatus

    DOE Patents [OSTI]

    Newman, D.F.; Ross, W.A.

    1990-04-24

    An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs.

  14. Radioactive waste material melter apparatus

    DOE Patents [OSTI]

    Newman, Darrell F.; Ross, Wayne A.

    1990-01-01

    An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another.

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

    Office of Environmental Management (EM)

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

  16. http://www.wipp.ws/TeamWorks/truteamworks.htm

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

    2/04 Shipments expected this week: RFETS (13), SRS (6) A weekly e-newsletter for the Waste Isolation Pilot Plant team February 12, 2004 The Big Story SEGA and MEGA exemplify science@wipp Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Tools Acronym List Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 02/12/04 at 9:24 a.m.)

  17. http://www.wipp.ws/TeamWorks/truteamworks.htm

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

    9/04 Shipments expected this week: SRS (6) A weekly e-newsletter for the Waste Isolation Pilot Plant team February 19, 2004 The Big Story WIPP public information meetings held Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Tools Acronym List Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 02/19/04 at 6:55 a.m.) Shipments scheduled

  18. http://www.wipp.ws/TeamWorks/truteamworks.htm

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

    5/04 | Shipments expected for the week of 03/14/04 through 3/20/04: INEEL (4), Hanford (2), RFETS (11), SR A weekly e-newsletter for the Waste Isolation Pilot Plant team March 15, 2004 Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 03/15/04 at 8:59 a.m.)

  19. http://www.wipp.ws/TeamWorks/truteamworks.htm

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

    8/04 | Shipments expected for the week 3/21/04 through 3/27/04: Hanford (2), INEEL (3), RFETS (11), SRS A weekly e-newsletter for the Waste Isolation Pilot Plant team March 18, 2004 The Big Story WIPP personnel overcome evacuation order Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to

  20. http://www.wipp.ws/TeamWorks/truteamworks.htm

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

    25/04 | Shipments expected for the week 3/28/04 through 4/3/04: INEEL (2), RFETS (11), SRS (6) A weekly e-newsletter for the Waste Isolation Pilot Plant team March 25, 2004 The Big Story AMWTP sends first shipment to WIPP Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP

  1. Cutting Wasteful Spending While Protecting Our Priorities

    Broader source: Energy.gov [DOE]

    Congress must work together on a budget that cuts wasteful spending while supporting jobs, the economy, and middle-class families.

  2. REGULATORY COOPERATION COUNCIL - WORK PLANNING FORMAT: Natural...

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

    COUNCIL - WORK PLANNING FORMAT: Natural Gas Use in Transportation PDF icon RCC Workplan NGV.PDF More Documents & Publications REGULATORY COOPERATION COUNCIL - WORK PLANNING ...

  3. Microsoft Word - Final FY14 WM Committee Work Plan 093013

    Office of Environmental Management (EM)

    4 Work Plan Approved September 25, 2013 1 Northern New Mexico Citizens' Advisory Board (NNMCAB) WASTE MANAGEMENT COMMITTEE 2014 Work Plan SECTION I. MISSION STATEMENT The Northern...

  4. Hazardous Materials Packaging and Transportation Safety - DOE...

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

    60.1D, Hazardous Materials Packaging and Transportation Safety by Ashok Kapoor Functional areas: Hazardous Materials, Packaging and Transportation, Safety and Security, Work...

  5. Intermediate-Scale Laboratory Experiments of Subsurface Flow and Transport Resulting from Tank Leaks

    SciTech Connect (OSTI)

    Oostrom, Martinus; Wietsma, Thomas W.

    2014-09-30

    Washington River Protection Solutions contracted with Pacific Northwest National Laboratory to conduct laboratory experiments and supporting numerical simulations to improve the understanding of water flow and contaminant transport in the subsurface between waste tanks and ancillary facilities at Waste Management Area C. The work scope included two separate sets of experiments: •Small flow cell experiments to investigate the occurrence of potential unstable fingering resulting from leaks and the limitations of the STOMP (Subsurface Transport Over Multiple Phases) simulator to predict flow patterns and solute transport behavior under these conditions. Unstable infiltration may, under certain conditions, create vertically elongated fingers potentially transporting contaminants rapidly through the unsaturated zone to groundwater. The types of leak that may create deeply penetrating fingers include slow release, long duration leaks in relatively permeable porous media. Such leaks may have occurred below waste tanks at the Hanford Site. •Large flow experiments to investigate the behavior of two types of tank leaks in a simple layered system mimicking the Waste Management Area C. The investigated leaks include a relatively large leak with a short duration from a tank and a long duration leak with a relatively small leakage rate from a cascade line.

  6. Management of offshore wastes in the United States.

    SciTech Connect (OSTI)

    Veil, J. A.

    1998-10-22

    During the process of finding and producing oil and gas in the offshore environment operators generate a variety of liquid and solid wastes. Some of these wastes are directly related to exploration and production activities (e.g., drilling wastes, produced water, treatment workover, and completion fluids) while other types of wastes are associated with human occupation of the offshore platforms (e.g., sanitary and domestic wastes, trash). Still other types of wastes can be considered generic industrial wastes (e.g., scrap metal and wood, wastes paints and chemicals, sand blasting residues). Finally, the offshore platforms themselves can be considered waste materials when their useful life span has been reached. Generally, offshore wastes are managed in one of three ways--onsite discharge, injection, or transportation to shore. This paper describes the regulatory requirements imposed by the government and the approaches used by offshore operators to manage and dispose of wastes in the US.

  7. Department of Energy Announces Selection of Transportation Contractors...

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

    Department of Energy Announces Selection of Transportation Contractors at the Waste ... TSMT, based in Joplin, MO, is a nationwide carrier with experience hauling hazardous and ...

  8. Waste acceptance criteria for the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    NONE

    1996-04-01

    The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies.

  9. Waste management plan for Hanford spent nuclear fuel characterization activities

    SciTech Connect (OSTI)

    Chastain, S.A. [Westinghouse Hanford Co., Richland, WA (United States); Spinks, R.L. [Pacific Northwest Lab., Richland, WA (United States)

    1994-10-17

    A joint project was initiated between Westinghouse Hanford Company (WHC) and Pacific Northwest Laboratory (PNL) to address critical issues associated with the Spent Nuclear Fuel (SNF) stored at the Hanford Site. Recently, particular attention has been given to remediation of the SNF stored in the K Basins. A waste management plan (WMP) acceptable to both parties is required prior to the movement of selected material to the PNL facilities for examination. N Reactor and Single Pass Reactor (SPR) fuel has been stored for an extended period of time in the N Reactor, PUREX, K-East, and K-West Basins. Characterization plans call for transport of fuel material form the K Basins to the 327 Building Postirradiation Testing Laboratory (PTL) in the 300 Area for examination. However, PNL received a directive stating that no examination work will be started in PNL hot cell laboratories without an approved disposal route for all waste generated related to the activity. Thus, as part of the Characterization Program Management Plan for Hanford Spent Nuclear Fuel, a waste management plan which will ensure that wastes generated as a result of characterization activities conducted at PNL will be accepted by WHC for disposition is required. This document contains the details of the waste handling plan that utilizes, to the greatest extent possible, established waste handling and disposal practices at Hanford between PNL and WHC. Standard practices are sufficient to provides for disposal of most of the waste materials, however, special consideration must be given to the remnants of spent nuclear fuel elements following examination. Fuel element remnants will be repackaged in an acceptable container such as the single element canister and returned to the K Basins for storage.

  10. Los Alamos shipments to Waste Control Specialists

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

    8, 2014 Los Alamos shipments to Waste Control Specialists To date, Waste Control Specialists (WCS), a facility in Andrews, Texas, has received and processed seven shipments of defense-generated transuranic waste from Los Alamos National Laboratory. Members of WIPP's Central Characterization Project mobile loading unit and crew went to WCS to safely unload the disposal containers. Plans include completing up to 10 shipments per week to WCS. All shipments are using WIPP's transportation protocols

  11. Plutonium-238 Transuranic Waste Decision Analysis

    SciTech Connect (OSTI)

    Brown, Mike; Lechel, David J.; Leigh, C.D.

    1999-06-29

    Five transuranic (TRU) waste sites in the Department of Energy (DOE) complex, collectively, have more than 2,100 cubic meters of Plutonium-238 (Pu-238) TRU waste that exceed the wattage restrictions of the Transuranic Package Transporter-II (TRUPACT-11). The Waste Isolation Pilot Plant (WIPP) is being developed by the DOE as a repository for TRU waste. With the Waste Isolation Pilot Plant (WIPP) opening in 1999, these sites are faced with a need to develop waste management practices that will enable the transportation of Pu-238 TRU waste to WIPP for disposal. This paper describes a decision analysis that provided a logical framework for addressing the Pu-238 TRU waste issue. The insights that can be gained by performing a formalized decision analysis are multifold. First and foremost, the very process. of formulating a decision tree forces the decision maker into structured, logical thinking where alternatives can be evaluated one against the other using a uniform set of criteria. In the process of developing the decision tree for transportation of Pu-238 TRU waste, several alternatives were eliminated and the logical order for decision making was discovered. Moreover, the key areas of uncertainty for proposed alternatives were identified and quantified. The decision analysis showed that the DOE can employ a combination approach where they will (1) use headspace gas analyses to show that a fraction of the Pu-238 TRU waste drums are no longer generating hydrogen gas and can be shipped to WIPP ''as-is'', (2) use drums and bags with advanced filter systems to repackage Pu-238 TRU waste drums that are still generating hydrogen, and (3) add hydrogen getter materials to the inner containment vessel of the TRUPACT-11to relieve the build-up of hydrogen gas during transportation of the Pu-238 TRU waste drums.

  12. Radioactive Waste Characterization Strategies; Comparisons Between AK/PK, Dose to Curie Modeling, Gamma Spectroscopy, and Laboratory Analysis Methods- 12194

    SciTech Connect (OSTI)

    Singledecker, Steven J.; Jones, Scotty W.; Dorries, Alison M.; Henckel, George; Gruetzmacher, Kathleen M. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States)

    2012-07-01

    In the coming fiscal years of potentially declining budgets, Department of Energy facilities such as the Los Alamos National Laboratory (LANL) will be looking to reduce the cost of radioactive waste characterization, management, and disposal processes. At the core of this cost reduction process will be choosing the most cost effective, efficient, and accurate methods of radioactive waste characterization. Central to every radioactive waste management program is an effective and accurate waste characterization program. Choosing between methods can determine what is classified as low level radioactive waste (LLRW), transuranic waste (TRU), waste that can be disposed of under an Authorized Release Limit (ARL), industrial waste, and waste that can be disposed of in municipal landfills. The cost benefits of an accurate radioactive waste characterization program cannot be overstated. In addition, inaccurate radioactive waste characterization of radioactive waste can result in the incorrect classification of radioactive waste leading to higher disposal costs, Department of Transportation (DOT) violations, Notice of Violations (NOVs) from Federal and State regulatory agencies, waste rejection from disposal facilities, loss of operational capabilities, and loss of disposal options. Any one of these events could result in the program that mischaracterized the waste losing its ability to perform it primary operational mission. Generators that produce radioactive waste have four characterization strategies at their disposal: - Acceptable Knowledge/Process Knowledge (AK/PK); - Indirect characterization using a software application or other dose to curie methodologies; - Non-Destructive Analysis (NDA) tools such as gamma spectroscopy; - Direct sampling (e.g. grab samples or Surface Contaminated Object smears) and laboratory analytical; Each method has specific advantages and disadvantages. This paper will evaluate each method detailing those advantages and disadvantages

  13. The U.S. Nuclear Waste Technical Review Board Status Update

    Office of Environmental Management (EM)

    The U S Nuclear Waste Technical Review Board The U.S. Nuclear Waste Technical Review Board Status Update Presented to: National Transportation Stakeholders Forum Presented By: National Transportation Stakeholders Forum Mark Abkowitz May 11, 2011 The Board's Statutory Mandate * The 1987 amendments to the Nuclear Waste Policy Act (NWPA) established the U S Nuclear Waste Technical Review Board established the U.S. Nuclear Waste Technical Review Board. * The Board evaluates the technical and

  14. CSNF WASTE FORM DEGRADATION: SUMMARY ABSTRACTION

    SciTech Connect (OSTI)

    J.C. CUNNANE

    2004-08-31

    The purpose of this model report is to describe the development and validation of models that can be used to calculate the release of radionuclides from commercial spent nuclear fuel (CSNF) following a hypothetical breach of the waste package and fuel cladding in the repository. The purpose also includes describing the uncertainties associated with modeling the radionuclide release for the range of CSNF types, exposure conditions, and durations for which the radionuclide release models are to be applied. This document was developed in accordance with Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package (BSC 2004 [DIRS 169944]). This document considers radionuclides to be released from CSNF when they are available for mobilization by gas-phase mass transport, or by dissolution or colloid formation in water that may contact the fuel. Because other reports address limitations on the dissolved and colloidal radionuclide concentrations (BSC 2004 [DIRS 169944], Table 2-1), this report does not address processes that control the extent to which the radionuclides released from CSNF are mobilized and transported away from the fuel either in the gas phase or in the aqueous phase as dissolved and colloidal species. The scope is limited to consideration of degradation of the CSNF rods following an initial breach of the cladding. It considers features of CSNF that limit the availability of individual radionuclides for release into the gaseous or aqueous phases that may contact the fuel and the processes and events expected to degrade these CSNF features. In short, the purpose is to describe the characteristics of breached fuel rods and the degradation processes expected to influence radionuclide release.

  15. Closure Report for Corrective Action Unit 537: Waste Sites, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Envirornmental Restoration

    2007-07-01

    Corrective Action Unit (CAU) 537 is identified in the ''Federal Facility Agreement and Consent Order'' (FFACO) of 1996 as Waste Sites. CAU 537 is located in Areas 3 and 19 of the Nevada Test Site, approximately 65 miles northwest of Las Vegas, Nevada, and consists of the following two Corrective Action Sites (CASs): CAS 03-23-06, Bucket; Yellow Tagged Bags; and CAS 19-19-01, Trash Pit. CAU 537 closure activities were conducted in April 2007 according to the FFACO and Revision 3 of the Sectored Clean-up Work Plan for Housekeeping Category Waste Sites (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2003). At CAS 03-23-06, closure activities included removal and disposal of a 15-foot (ft) by 15-ft by 8-ft tall wooden shed containing wood and metal debris and a 5-gallon plastic bucket containing deteriorated plastic bags with yellow radioactive contamination tape. The debris was transported to the Area 9 U10c Landfill for disposal after being screened for radiological contamination according to the ''NV/YMP Radiological Control Manual'' (NNSA/NSO, 2004). At CAS 19-19-01, closure activities included segregation, removal, and disposal of non-friable, non-regulated asbestos-containing material (ACM) and construction debris. The ACM was determined to be non-friable by waste characterization samples collected prior to closure activities. The ACM was removed and double-bagged by licensed, trained asbestos workers and transported to the Area 9 U10c Landfill for disposal. Construction debris was transported in end-dump trucks to the Area 9 U10c Landfill for disposal. Closure activities generated sanitary waste/construction debris and ACM. Waste generated during closure activities was appropriately managed and disposed. Waste characterization sample results are included as Appendix A of this report, and waste disposition documentation is included as Appendix B of this report. Copies of the Sectored Housekeeping Site Closure

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

    Office of Environmental Management (EM)

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

  17. Hazardous Waste Certification Plan: Hazardous Waste Handling Facility, Lawrence Berkeley Laboratory

    SciTech Connect (OSTI)

    Not Available

    1992-02-01

    The purpose of this plan is to describe the organization and methodology for the certification of hazardous waste (HW) handled in the Lawrence Berkeley Laboratory (LBL) Hazardous Waste Handling Facility (HWHF). The plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end- product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; and executive summary of the Quality Assurance Program Plan (QAPP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. The plan provides guidance from the HWHF to waste generators, waste handlers, and the Systems Group Manager to enable them to conduct their activities and carry out their responsibilities in a manner that complies with several requirements of the Federal Resource Conservation and Resource Recovery Act (RCRA), the Federal Department of Transportation (DOT), and the State of California, Code of Regulations (CCR), Title 22.

  18. Emergency Preparedness Working

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

    August 24, 2015 Emergency Preparedness Working Group (EPWG) Grant * Nevada Field Office funds the EPWG grant based on $.50 per cubic foot of low-level/mixed low-level waste disposed at the Nevada National Security Site * EPWG consists of six Nevada counties: Clark, Elko, Esmeralda, Lincoln, Nye, and White Pine * EPWG addresses grant administration issues and any cross-cutting emergency related questions that incorporate grant funding or are required to attain operations level emergency response

  19. Transportation Research

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

    transportation-research TRACC RESEARCH Computational Fluid Dynamics Computational Structural Mechanics Transportation Systems Modeling Transportation Research Current Research Overview The U.S. Department of Transportation (USDOT) has established its only high-performance computing and engineering analysis research facility at Argonne National Laboratory to provide applications support in key areas of applied research and development for the USDOT community. The Transportation Research and

  20. Experiences on a Regulatory Clearance of the Radioactive Wastes at KAERI

    SciTech Connect (OSTI)

    Hong, D.S.; Ji, Y.Y.; Shon, J.S.; Hong, S.B.

    2008-07-01

    At the Korea Atomic Energy Research Institute (KAERI) in Daejeon, about 4,500 drums of old radioactive soil and concrete wastes have been stored since their generation and transport to Daejeon in 1988. The wastes have been stored for more than 18 years. So, according to the analysis result for their radioactivity, some of them can be regularly cleared. In addition to that, about 2,200 tonnes of decommissioning wastes were generated during the dismantling of Korean research reactors no.1 and no.2 (KRR-1 and KRR-2) from 1997 to 2005. Among those, only 13% were classified as radioactive wastes and part of remains were cleared. In this paper, the experiences on a regulatory clearance of radioactive wastes at KAERI were discussed. First, for the old wastes, a working procedure for representative sampling of each drum and an analysis was developed. Also, as these old wastes are already in a storage facility, some equipment and tools for easy sampling and restricting a contamination of a storage facility were developed and applied. Following the working procedure, the old wastes with a surface dose rate less than 0.3 {mu}Sv/hr were selected for an analysis. Based on the analysis results of a sample, the waste with a radioactivity concentration less than 0.4 Bq/g was classified as an object for regulatory clearance. According to the radiological dose assessment result and the dose criteria regulated by Atomic Energy Act of Korea (individual dose<10 {mu}Sv/yr, collective dose<1 man.Sv/yr), about 2,800 drums of wastes were determined for a clearance and they are under process for a license. After a clearance, it is scheduled for the wastes to be disposed of at a public dumping ground. Second, for the recently generated decommissioning wastes, the analysis for their radioactive characteristics was simpler than that for the old wastes. The distribution of a radioactivity levels, a gross alpha/beta contamination and a surface dose rate was measured to assess the radiological

  1. Nuclear waste management. Quarterly progress report, April-June 1981

    SciTech Connect (OSTI)

    Chikalla, T.D.; Powell, J.A.

    1981-09-01

    Reports and summaries are presented for the following: high-level waste process development; alternative waste forms; TMI zeolite vitrification demonstration program; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton implantation; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclides in soils; handbook of methods to decrease the generation of low-level waste; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; and analysis of spent fuel policy implementation.

  2. Packaging and Transportation | Department of Energy

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

    Packaging and Transportation Packaging and Transportation Packaging and Transportation Radiological shipments are accomplished safely. Annually, about 400 million hazardous materials shipments occur in the United States by rail, air, sea, and land. Of these shipments, about three million are radiological shipments. Since Fiscal Year (FY) 2004, EM has completed over 150,000 shipments of radioactive material/waste. Please click here to see Office of Packaging and Transportation Fiscal Year 2012

  3. Waste Handeling Building Conceptual Study

    SciTech Connect (OSTI)

    G.W. Rowe

    2000-11-06

    The objective of the ''Waste Handling Building Conceptual Study'' is to develop proposed design requirements for the repository Waste Handling System in sufficient detail to allow the surface facility design to proceed to the License Application effort if the proposed requirements are approved by DOE. Proposed requirements were developed to further refine waste handling facility performance characteristics and design constraints with an emphasis on supporting modular construction, minimizing fuel inventory, and optimizing facility maintainability and dry handling operations. To meet this objective, this study attempts to provide an alternative design to the Site Recommendation design that is flexible, simple, reliable, and can be constructed in phases. The design concept will be input to the ''Modular Design/Construction and Operation Options Report'', which will address the overall program objectives and direction, including options and issues associated with transportation, the subsurface facility, and Total System Life Cycle Cost. This study (herein) is limited to the Waste Handling System and associated fuel staging system.

  4. Radium/Barium Waste Project

    SciTech Connect (OSTI)

    McDowell, Allen K.; Ellefson, Mark D.; McDonald, Kent M.

    2015-06-25

    The treatment, shipping, and disposal of a highly radioactive radium/barium waste stream have presented a complex set of challenges requiring several years of effort. The project illustrates the difficulty and high cost of managing even small quantities of highly radioactive Resource Conservation and Recovery Act (RCRA)-regulated waste. Pacific Northwest National Laboratory (PNNL) research activities produced a Type B quantity of radium chloride low-level mixed waste (LLMW) in a number of small vials in a facility hot cell. The resulting waste management project involved a mock-up RCRA stabilization treatment, a failed in-cell treatment, a second, alternative RCRA treatment approach, coordinated regulatory variances and authorizations, alternative transportation authorizations, additional disposal facility approvals, and a final radiological stabilization process.

  5. Work Plan

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

    Work Plan NSSAB Members Vote on Work Plan Tasks; The Nevada Site Specific Advisory Board operates on a fiscal year basis and conducts work according to a NSSAB generated and U.S. Department of Energy (DOE) approved work plan. FY 2016 Work Plan Work plan items focus on providing recommendations to the DOE regarding the following subjects: soil contamination from historic atmospheric nuclear testing, remediation of contaminated facilities used to support historic testing, groundwater studies

  6. Economic evaluation of volume reduction for Defense transuranic waste

    SciTech Connect (OSTI)

    Brown, C.M.

    1981-07-01

    This study evaluates the economics of volume reduction of retrievably stored and newly generated DOE transuranic waste by comparing the costs of reduction of the waste with the savings possible in transportation and disposal of the waste. The report develops a general approach to the comparison of TRU waste volume reduction costs and cost savings, establishes an initial set of cost data, and develops conclusions to support selecting technologies and facilities for the disposal of DOE transuranic waste. Section I outlines the analysis which considers seven types of volume reduction from incineration and compaction of combustibles to compaction, size reduction, shredding, melting, and decontamination of metals. The study considers the volume reduction of contact-handled newly generated, and retrievably stored DOE transuranic waste. Section II of this report describes the analytical approach, assumptions, and flow of waste material through sites. Section III presents the waste inventories, disposal, and transportation savings with volume reduction and the volume reduction techniques and savings.

  7. Radiation Transport

    SciTech Connect (OSTI)

    Urbatsch, Todd James

    2015-06-15

    We present an overview of radiation transport, covering terminology, blackbody raditation, opacities, Boltzmann transport theory, approximations to the transport equation. Next we introduce several transport methods. We present a section on Caseology, observing transport boundary layers. We briefly broach topics of software development, including verification and validation, and we close with a section on high energy-density experiments that highlight and support radiation transport.

  8. Mixed Waste Focus Area program management plan

    SciTech Connect (OSTI)

    Beitel, G.A.

    1996-10-01

    This plan describes the program management principles and functions to be implemented in the Mixed Waste Focus Area (MWFA). The mission of the MWFA is to provide acceptable technologies that enable implementation of mixed waste treatment systems developed in partnership with end-users, stakeholders, tribal governments and regulators. The MWFA will develop, demonstrate and deliver implementable technologies for treatment of mixed waste within the DOE Complex. Treatment refers to all post waste-generation activities including sampling and analysis, characterization, storage, processing, packaging, transportation and disposal.

  9. Railroad transportation of spent nuclear fuel

    SciTech Connect (OSTI)

    Wooden, D.G.

    1986-03-01

    This report documents a detailed analysis of rail operations that are important for assessing the risk of transporting high-level nuclear waste. The major emphasis of the discussion is towards ''general freight'' shipments of radioactive material. The purpose of this document is to provide a basis for selecting models and parameters that are appropriate for assessing the risk of rail transportation of nuclear waste.

  10. Annual Transportation Report for Radioactive Waste Shipments...

    National Nuclear Security Administration (NNSA)

    ... TN PF 15 PORTSMOUTH GASEOUS DIFFUSION PLANT, OH PO 16 PRINCETON PLASMA PHYSICS ... IT 19 UT-BATTELLE, TN OL 20 WASHINGTON SAVANNAH RIVER COMPANY, SC SR 21 WEST VALLEY ...

  11. EM Waste and Materials Disposition & Transportation

    Office of Environmental Management (EM)

    Department of Energy Updates Congress on Nuclear Cleanup Progress in 18th Annual Caucus EM Updates Congress on Nuclear Cleanup Progress in 18th Annual Caucus March 1, 2012 - 12:00pm Addthis WASHINGTON, D.C. - EM and its cleanup contractors present briefings each year to the U.S. House Nuclear Cleanup Caucus on remediation operations at its major sites across the DOE complex. The briefings are organized by Rep. Doc Hastings (R-Wash.), who chairs the bipartisan caucus. For nearly two decades,

  12. Waste Information Management System with 2012-13 Waste Streams - 13095

    SciTech Connect (OSTI)

    Upadhyay, H.; Quintero, W.; Lagos, L.; Shoffner, P.; Roelant, D. [Applied Research Center, Florida International University, 10555 West Flagler Street, Suite 2100, Miami, FL 33174 (United States)] [Applied Research Center, Florida International University, 10555 West Flagler Street, Suite 2100, Miami, FL 33174 (United States)

    2013-07-01

    The Waste Information Management System (WIMS) 2012-13 was updated to support the Department of Energy (DOE) accelerated cleanup program. The schedule compression required close coordination and a comprehensive review and prioritization of the barriers that impeded treatment and disposition of the waste streams at each site. Many issues related to waste treatment and disposal were potential critical path issues under the accelerated schedule. In order to facilitate accelerated cleanup initiatives, waste managers at DOE field sites and at DOE Headquarters in Washington, D.C., needed timely waste forecast and transportation information regarding the volumes and types of radioactive waste that would be generated by DOE sites over the next 40 years. Each local DOE site historically collected, organized, and displayed waste forecast information in separate and unique systems. In order for interested parties to understand and view the complete DOE complex-wide picture, the radioactive waste and shipment information of each DOE site needed to be entered into a common application. The WIMS application was therefore created to serve as a common application to improve stakeholder comprehension and improve DOE radioactive waste treatment and disposal planning and scheduling. WIMS allows identification of total forecasted waste volumes, material classes, disposition sites, choke points, technological or regulatory barriers to treatment and disposal, along with forecasted waste transportation information by rail, truck and inter-modal shipments. The Applied Research Center (ARC) at Florida International University (FIU) in Miami, Florida, developed and deployed the web-based forecast and transportation system and is responsible for updating the radioactive waste forecast and transportation data on a regular basis to ensure the long-term viability and value of this system. (authors)

  13. Method of preparing nuclear wastes for tansportation and interim storage

    DOE Patents [OSTI]

    Bandyopadhyay, Gautam (Naperville, IL); Galvin, Thomas M. (Darien, IL)

    1984-01-01

    Nuclear waste is formed into a substantially water-insoluble solid for temporary storage and transportation by mixing the calcined waste with at least 10 weight percent powdered anhydrous sodium silicate to form a mixture and subjecting the mixture to a high humidity environment for a period of time sufficient to form cementitious bonds by chemical reaction. The method is suitable for preparing an interim waste form from dried high level radioactive wastes.

  14. Waste-to-Energy Workshop | Department of Energy

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

    Waste-to-Energy Workshop Waste-to-Energy Workshop The Bioenergy Technologies Office (BETO) at the Department of Energy aims to identify and address key technical barriers to the commercial deployment of liquid transportation fuels from waste feedstocks. As part of this effort, BETO held a Waste-to-Energy Workshop on November 5, 2014. The participants discussed anaerobic digestion, hydrothermal liquefaction, and other processes that make productive use of wastewater residuals, biosolids,

  15. Chamber transport

    SciTech Connect (OSTI)

    OLSON,CRAIG L.

    2000-05-17

    Heavy ion beam transport through the containment chamber plays a crucial role in all heavy ion fusion (HIF) scenarios. Here, several parameters are used to characterize the operating space for HIF beams; transport modes are assessed in relation to evolving target/accelerator requirements; results of recent relevant experiments and simulations of HIF transport are summarized; and relevant instabilities are reviewed. All transport options still exist, including (1) vacuum ballistic transport, (2) neutralized ballistic transport, and (3) channel-like transport. Presently, the European HIF program favors vacuum ballistic transport, while the US HIF program favors neutralized ballistic transport with channel-like transport as an alternate approach. Further transport research is needed to clearly guide selection of the most attractive, integrated HIF system.

  16. RIVER PROTECTION PROJECT MISSION ANALYSIS WASTE BLENDING STUDY

    SciTech Connect (OSTI)

    SHUFORD DH; STEGEN G

    2010-04-19

    Preliminary evaluation for blending Hanford site waste with the objective of minimizing the amount of high-level waste (HLW) glass volumes without major changes to the overall waste retrieval and processing sequences currently planned. The evaluation utilizes simplified spreadsheet models developed to allow screening type comparisons of blending options without the need to use the Hanford Tank Waste Operations Simulator (HTWOS) model. The blending scenarios evaluated are expected to increase tank farm operation costs due to increased waste transfers. Benefit would be derived from shorter operating time period for tank waste processing facilities, reduced onsite storage of immobilized HLW, and reduced offsite transportation and disposal costs for the immobilized HLW.

  17. Secondary Waste Form Down-Selection Data Package—Fluidized Bed Steam Reforming Waste Form

    SciTech Connect (OSTI)

    Qafoku, Nikolla; Westsik, Joseph H.; Strachan, Denis M.; Valenta, Michelle M.; Pires, Richard P.

    2011-09-12

    The Hanford Site in southeast Washington State has 56 million gallons of radioactive and chemically hazardous wastes stored in 177 underground tanks (ORP 2010). The U.S. Department of Energy (DOE), Office of River Protection (ORP), through its contractors, is constructing the Hanford Tank Waste Treatment and Immobilization Plant (WTP) to convert the radioactive and hazardous wastes into stable glass waste forms for disposal. Within the WTP, the pretreatment facility will receive the retrieved waste from the tank farms and separate it into two treated process streams. These waste streams will be vitrified, and the resulting waste canisters will be sent to offsite (high-level waste [HLW]) and onsite (immobilized low-activity waste [ILAW]) repositories. As part of the pretreatment and ILAW processing, liquid secondary wastes will be generated that will be transferred to the Effluent Treatment Facility (ETF) on the Hanford Site for further treatment. These liquid secondary wastes will be converted to stable solid waste forms that will be disposed of in the Integrated Disposal Facility (IDF). To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions (WRPS) has initiated secondary waste form testing work at Pacific Northwest National Laboratory (PNNL). In anticipation of a down-selection process for a waste form for the Solidification Treatment Unit to be added to the ETF, PNNL is developing data packages to support that down-selection. The objective of the data packages is to identify, evaluate, and summarize the existing information on the four waste forms being considered for stabilizing and solidifying the liquid secondary wastes. At the Hanford Site, the FBSR process is being evaluated as a supplemental technology for treating and immobilizing Hanford LAW radioactive tank waste and for treating secondary wastes from the WTP pretreatment and LAW vitrification processes.

  18. Waste minimization in an autobody repair shop

    SciTech Connect (OSTI)

    Baria, D.N.; Dorland, D.; Bergeron, J.T.

    1994-12-31

    This work was done to document the waste minimization incorporated in a new autobody repair facility in Hermantown, Minnesota. Humes Collision Center incorporated new waste reduction techniques when it expanded its old facilities in 1992 and it was able to achieve the benefits of cost reduction and waste reduction. Humes Collision Center repairs an average of 500 cars annually and is a very small quantity generator (VSQG) of hazardous waste, as defined by the Minnesota Pollution Control Agency (MPCA). The hazardous waste consists of antifreeze, batteries, paint sludge, refrigerants, and used oil, while the nonhazardous waste consists of cardboard, glass, paint filters, plastic, sanding dust, scrap metal, and wastewater. The hazardous and nonhazardous waste output were decreased by 72%. In addition, there was a 63% reduction in the operating costs. The waste minimization includes antifreeze recovery and recycling, reduction in unused waste paint, reduction, recovery and recycle of waste lacquer thinner for cleaning spray guns and paint cups, elimination of used plastic car bags, recovery and recycle of refrigerant, reduction in waste sandpaper and elimination of sanding dust, and elimination of waste paint filters. The rate of return on the investment in waste minimization equipment is estimated from 37% per year for the distillation unit, 80% for vacuum sanding, 146% for computerized paint mixing, 211% for the refrigerant recycler, to 588% per year for the gun washer. The corresponding payback time varies from 3 years to 2 months.

  19. Transuranic waste disposal in the United State

    SciTech Connect (OSTI)

    Thompson, J.D.

    1986-01-01

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

  20. Waste Treatment Plant Overview

    Office of Environmental Management (EM)

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

  1. Hydrogen venting characteristics of commercial carbon-composite filters and applications to TRU waste

    SciTech Connect (OSTI)

    Callis, E.L.; Marshall, R.S.; Cappis, J.H.

    1997-04-01

    The generation of hydrogen (by radiolysis) and of other potentially flammable gases in radioactive wastes which are in contact with hydrogenous materials is a source of concern, both from transportation and on-site storage considerations. Because very little experimental data on the generation and accumulation of hydrogen was available in actual waste materials, work was initiated to experimentally determine factors affecting the concentration of hydrogen in the waste containers, such as the hydrogen generation rate, (G-values) and the rate of loss of hydrogen through packaging and commercial filter-vents, including a new design suitable for plastic bags. This report deals only with the venting aspect of the problem. Hydrogen venting characteristics of two types of commercial carbon-composite filter-vents, and two types of PVC bag closures (heat-sealed and twist-and-tape) were measured. Techniques and equipment were developed to permit measurement of the hydrogen concentration in various layers of actual transuranic (TRU) waste packages, both with and without filter-vents. A test barrel was assembled containing known configuration and amounts of TRU wastes. Measurements of the hydrogen in the headspace verified a hydrogen release model developed by Benchmark Environmental Corporation. These data were used to calculate revised wattage Emits for TRU waste packages incorporating the new bag filter-vent.

  2. HLW Glass Waste Loadings

    Office of Environmental Management (EM)

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

  3. Enhancements to System for Tracking Radioactive Waste Shipments Benefit

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

    Multiple Users | Department of Energy Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users January 30, 2013 - 12:00pm Addthis Transportation Tracking and Communication System users can now track shipments of radioactive materials and access transportation information on mobile devices. Transportation Tracking and Communication System users can now track shipments of

  4. Transportation and Program Management Services | Department of...

    Office of Environmental Management (EM)

    Documents & Publications Nuclear Transportation Management Services TEC Working Group Topic Groups Rail Key Documents TEC Working Group Topic Groups Manual Review Key Documents...

  5. River Corridor Cleanup Contract Fiscal Year 2006 Detailed Work Plan: D4 Project/Reactor ISS Closure Projects Field Remediation Project Waste Operations Project End State and Final Closure Project Mission/General Support, Volume 2

    SciTech Connect (OSTI)

    Project Integration

    2005-09-26

    The Hanford Site contains many surplus facilities and waste sites that remain from plutonium production activities. These contaminated facilities and sites must either be stabilized and maintained, or removed, to prevent the escape of potentially hazardous contaminants into the environment and exposure to workers and the public.

  6. Khazar Iodine Production Plant Site Remediation in Turkmenistan. NORM Contaminated Waste Repository Establishment - 12398

    SciTech Connect (OSTI)

    Gelbutovskiy, Alexander B.; Cheremisin, Peter I.; Troshev, Alexander V.; Egorov, Alexander J.; Boriskin, Mikhail M.; Bogod, Mikhail A.

    2012-07-01

    Radiation safety provisions for NORM contaminated areas are in use in a number of the former Soviet republics. Some of these areas were formed by absorbed radionuclides at the iodine and bromine extraction sites. As a rule, there are not any plant radiation monitoring systems nor appropriate services to ensure personnel, population and environmental radiation safety. The most hazardous sites are those which are situated in the Caspian Sea coastal zone. The bulk of the accumulated waste is represented by a loose mixture of sand and charcoal, which was basically used as the iodine extraction sorbent. The amounts of these wastes were estimated to be approximately 20,000 metric tons. The waste contamination is mainly composed of Ra-226 (U-238 decay series) and Ra-224, Ra-228 (Th-232 decay series). In 2009, the 'ECOMET-S', a Closed Joint-Stock Company from St. Petersburg, Russian Federation, was authorized by the Turkmenistan government to launch the rehabilitation project. The project includes D and D activities, contaminated areas remediation, collected wastes safe transportation to the repository and its disposal following repository closure. The work at the Khazar chemical plant started in September, 2010. Comprehensive radiological surveys to estimate the waste quantities were carried out in advance. In course of the rehabilitation work at the site of the Khazar chemical plant additional waste quantities (5,000 MT, 10,000 m{sup 3}) were discovered after the sludge was dumped and drained. Disposal volumes for this waste was not provided initially. The additional volume of the construction wastes was required in order to accommodate all the waste to be disposed. For the larger disposal volume the project design enterprise VNIPIET, offered to erect a second wall outside the existing one and this solution was adopted. As of May, 2011, 40,575 m{sup 3} of contaminated waste were collected and disposed safely. This volume represents 96.6% of the initial repository volume

  7. Negotiating equity for management of DOE wastes

    SciTech Connect (OSTI)

    Carnes, S.A.

    1994-09-01

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

  8. The effect of concentration on the structure and crystallinity of a cementitious waste form for caustic wastes

    SciTech Connect (OSTI)

    Chung, Chul-Woo; Turo, Laura A.; Ryan, Joseph V.; Johnson, Bradley R.; McCloy, John S.

    2013-06-01

    Cement-based waste forms have long been considered economical technologies for disposal of various types of waste. A solidified cementitious waste form, Cast Stone, was developed to immobilize the radioactive secondary waste from vitrification processes. In this work, Cast Stone was considered for a Na-based caustic liquid waste, and its physical properties were analyzed as a function of liquid waste loading up to 2 M Na. Differences in crystallinity (phase composition), microstructure, mesostructure (pore size distribution, surface area), and macrostructure (density, compressive strength) were investigated using various analytical techniques, in order to assess the suitability of Cast Stone as a chemically durable waste. It was found that the concentration of secondary waste simulant (caustic waste) had little effect on the relevant engineering properties of Cast Stone, showing that Cast Stone could be an effective and tolerant waste form for a wide range of concentrations of high sodium waste.

  9. Waste Isolation Pilot Plant Update

    Office of Environmental Management (EM)

    Update J. R. Stroble Director, National TRU Program U.S. Department of Energy Carlsbad Field Office National Transportation Stakeholder Forum May 11, 2011 Denver, Colorado 2 2 Shipments received at WIPP to date: 9,493 Contact-handled: 9,019 Remote-handled: 474 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 44 84 366 947 818 1,002 98 8 997 1,144 730 1,032 Total Shipments by Calendar Year (Including intersite shipments) 1,194 CH TRU waste shipments only CH and RH TRU waste

  10. Nuclear waste management. Quarterly progress report, April-June 1980

    SciTech Connect (OSTI)

    Platt, A.M.; Powell, J.A.

    1980-09-01

    The status of the following programs is reported: high-level waste immobilization; alternative waste forms; Nuclear Waste Materials Characterization Center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of fission products in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; systems study on engineered barriers; criteria for defining waste isolation; spent fuel and fuel pool component integrity program; analysis of spent fuel policy implementation; asphalt emulsion sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and development of backfill material.

  11. Nuclear waste management. Quarterly progress report, October through December 1980

    SciTech Connect (OSTI)

    Chikalla, T.D.; Powell, J.A.

    1981-03-01

    Progress reports and summaries are presented under the following headings: high-level waste process development; alternative waste forms; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of radionuclides in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; high level waste form preparation; development of backfill material; development of structural engineered barriers; ONWI disposal charge analysis; spent fuel and fuel component integrity program; analysis of spent fuel policy implementation; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; revegetation of inactive uranium tailing sites; verification instrument development.

  12. Saturated Zone Colloid Transport

    SciTech Connect (OSTI)

    H. S. Viswanathan

    2004-10-07

    This scientific analysis provides retardation factors for colloids transporting in the saturated zone (SZ) and the unsaturated zone (UZ). These retardation factors represent the reversible chemical and physical filtration of colloids in the SZ. The value of the colloid retardation factor, R{sub col} is dependent on several factors, such as colloid size, colloid type, and geochemical conditions (e.g., pH, Eh, and ionic strength). These factors are folded into the distributions of R{sub col} that have been developed from field and experimental data collected under varying geochemical conditions with different colloid types and sizes. Attachment rate constants, k{sub att}, and detachment rate constants, k{sub det}, of colloids to the fracture surface have been measured for the fractured volcanics, and separate R{sub col} uncertainty distributions have been developed for attachment and detachment to clastic material and mineral grains in the alluvium. Radionuclides such as plutonium and americium sorb mostly (90 to 99 percent) irreversibly to colloids (BSC 2004 [DIRS 170025], Section 6.3.3.2). The colloid retardation factors developed in this analysis are needed to simulate the transport of radionuclides that are irreversibly sorbed onto colloids; this transport is discussed in the model report ''Site-Scale Saturated Zone Transport'' (BSC 2004 [DIRS 170036]). Although it is not exclusive to any particular radionuclide release scenario, this scientific analysis especially addresses those scenarios pertaining to evidence from waste-degradation experiments, which indicate that plutonium and americium may be irreversibly attached to colloids for the time scales of interest. A section of this report will also discuss the validity of using microspheres as analogs to colloids in some of the lab and field experiments used to obtain the colloid retardation factors. In addition, a small fraction of colloids travels with the groundwater without any significant retardation

  13. Waste Hoist

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

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

  14. Waste Hoist

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

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

  15. The role of non-destructive assay in support of the exemption of solid waste from nuclear licensed sites

    SciTech Connect (OSTI)

    Fisher, Alan; Adsley, Ian; Green, Tommy

    2007-07-01

    Available in abstract form only. Full text of publication follows: Nuclear Site License Holders within the United Kingdom are increasingly re-examining the options available for disposal of solid waste produced during routine operations and decommissioning activities. The incentives to do so include: 'Compliance with the requirement to minimise radioactive waste, as stipulated in Disposal Authorisations issued by the Environment Agency' Reducing the burden on the UK Low Level Waste Repository (LLWR)' Achieving cost savings on waste management, by avoiding expensive conditioning, transport and disposal costs for certain wastes. Wastes may be exempted from regulation under the Radioactive Substances Act, 1993 (RSA 93) provided they comply with the conditions laid out in the relevant Exemption Orders. In effect, they may be legally disposed as if they were non-radioactive waste. A national Code of Practice on Clearance and Exemption Principles, Processes and Practices was introduced in 2005 to clarify the requirements of these Exemption Orders and provide guidance on their practical application. In order to demonstrate compliance with these Exemption Orders, it is essential to have good knowledge of the items' history and their potential for contamination. Monitoring is frequently used as definitive evidence that the radioactivity content of waste items does not exceed limits proscribed in the relevant Exemption Orders. The practicalities of monitoring require careful consideration in order to achieve meaningful results and be capable of achieving the low specific activity limits quoted in the Exemption Orders. The Cross Industry Assay Working Group is a national collection of non-destructive assay specialists from a range of companies, which meets regularly to discuss challenges relating to the assay of all categories of waste. In this paper, the Group presents examples of how NDA techniques are being used to support the exemption of waste items. (authors)

  16. Waste processing air cleaning

    SciTech Connect (OSTI)

    Kriskovich, J.R.

    1998-07-27

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

  17. Getting waste ready for shipment to the WIPP: integration of characterization and certification activities

    SciTech Connect (OSTI)

    Sinkule, B.; Knudsen, K.; Rogers, P.

    1996-06-01

    The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC) serve as the primary directive for assuring the safe handling, transportation, and disposal of transuranic (TRU) waste generated at Department of Energy (DOE) sites. The WIPP WAC address fulfillment of WIPP`s operational safety and performance assessment criteria, compliance with Resource Conservation and Recovery Act (RCRA) requirements, and preparation of waste packages that meet all transportation criteria. At individual generator sites, preparation of transuranic waste for final disposal at WIPP includes characterizing the waste to meet the requirements of the transuranic Waste Characterization Quality Assurance Program Plan (QAPP) and certifying waste containers to meet the WIPP WAC and the Transuranic Package Transporter-II Authorized Methods for Payload Control (TRAMPAC). This paper compares the quality assurance and quality control requirements specified in the WIPP WAC, QAPP, and TRAMPAC and discusses the potential to consolidate activities to comply with the TRU waste characterization and certification program requirements.

  18. Idaho Nuclear Technology and Engineering Center Newly Generated Liquid Waste Demonstration Project Feasibility Study

    SciTech Connect (OSTI)

    Herbst, A.K.

    2000-02-01

    A research, development, and demonstration project for the grouting of newly generated liquid waste (NGLW) at the Idaho Nuclear Technology and Engineering Center is considered feasible. NGLW is expected from process equipment waste, decontamination waste, analytical laboratory waste, fuel storage basin waste water, and high-level liquid waste evaporator condensate. The potential grouted waste would be classed as mixed low-level waste, stabilized and immobilized to meet RCRA LDR disposal in a grouting process in the CPP-604 facility, and then transported to the state.

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

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

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

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

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

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

  1. One System Integrated Project Team: Retrieval and Delivery of Hanford Tank Wastes for Vitrification in the Waste Treatment Plant - 13234

    SciTech Connect (OSTI)

    Harp, Benton J.; Kacich, Richard M.; Skwarek, Raymond J.

    2013-07-01

    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 of WTP. 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 and Controls, Front-End Design and Project Definition, Commissioning, Nuclear Safety and Engineering Systems Integration, and Environmental Safety and Health and Quality Assurance (ESH and 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{sup R} Foundation-Configuration Management System; and (5) preparation of the joint contract deliverable of the Operational Readiness Support Plan. (authors)

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

    SciTech Connect (OSTI)

    Harp, Benton J.; Kacich, Richard M.; Skwarek, Raymond J.

    2012-12-20

    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.

  3. DOE/NV Radioactive Waste Acceptance Program

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

    on the Proper Characterization and Disposal of Sealed Radioactive Sources Revision 2, October 1997 Revised by: DOE/NV Radioactive Waste Acceptance Program and The NTSWAC Working Group EXECUTIVE SUMMARY The "Position Paper on the Proper Characterization and Disposal of Sealed Radioactive Sources" was originally developed by the NVO-325 Work Group, Sealed Source Waste Characterization Subgroup. The NVO-325 Workgroup, now called the NTSWAC Working Group, is comprised of representatives

  4. Vadose Zone Transport Field Study: Summary Report

    SciTech Connect (OSTI)

    Ward, Andy L.; Conrad, Mark E.; Daily, William D.; Fink, James B.; Freedman, Vicky L.; Gee, Glendon W.; Hoversten, Gary M.; Keller, Jason M.; Majer, Ernest L.; Murray, Christopher J.; White, Mark D.; Yabusaki, Steven B.; Zhang, Z. F.

    2006-07-31

    (e.g. BC Cribs and Trenches). The improved models have been also coupled with inverse models and newly-developed parameter scaling techniques to allow estimation of field-scale and effective transport parameters for the vadose zone. The development and utility of pedotransfer functions for describing fine-scale hydrogeochemical heterogeneity and for incorporating this heterogeneity into reactive transport models was explored. An approach based on grain-size statistics appears feasible and has been used to describe heterogeneity in hydraulic properties and sorption properties, such as the cation exchange capacity and the specific surface area of Hanford sediments. This work has also led to the development of inverse modeling capabilities for time-dependent, subsurface, reactive transport with transient flow fields using an automated optimization algorithm. In addition, a number of geophysical techniques investigated for their potential to provide detailed information on the subtle changes in lithology and bedding surfaces; plume delineation, leak detection. High-resolution resistivity is now being used for detecting saline plumes at several waste sites at Hanford, including tank farms. Results from the field studies and associated analysis have appeared in more than 46 publications generated over the past 4 years. These publications include test plans and status reports, in addition to numerous technical notes and peer reviewed papers.

  5. Benchmarking NNWSI flow and transport codes: COVE 1 results

    SciTech Connect (OSTI)

    Hayden, N.K.

    1985-06-01

    The code verification (COVE) activity of the Nevada Nuclear Waste Storage Investigations (NNWSI) Project is the first step in certification of flow and transport codes used for NNWSI performance assessments of a geologic repository for disposing of high-level radioactive wastes. The goals of the COVE activity are (1) to demonstrate and compare the numerical accuracy and sensitivity of certain codes, (2) to identify and resolve problems in running typical NNWSI performance assessment calculations, and (3) to evaluate computer requirements for running the codes. This report describes the work done for COVE 1, the first step in benchmarking some of the codes. Isothermal calculations for the COVE 1 benchmarking have been completed using the hydrologic flow codes SAGUARO, TRUST, and GWVIP; the radionuclide transport codes FEMTRAN and TRUMP; and the coupled flow and transport code TRACR3D. This report presents the results of three cases of the benchmarking problem solved for COVE 1, a comparison of the results, questions raised regarding sensitivities to modeling techniques, and conclusions drawn regarding the status and numerical sensitivities of the codes. 30 refs.

  6. Radioactive Material Transportation Requirements for the Department of Energy

    SciTech Connect (OSTI)

    John, Mark Earl; Fawcett, Ricky Lee; Bolander, Thane Weston

    2000-07-01

    The Department of Energy (DOE) created the National Transportation Program (NTP) whose goal is to ensure the availability of safe, efficient, and timely transportation of DOE materials. The Integration and Planning Group of the NTP, assisted by Global Technologies Incorporated (GTI), was tasked to identify requirements associated with the transport of DOE Environmental Management (EM) radiological waste/material. A systems engineering approach was used to identify source documents, extract requirements, perform a functional analysis, and set up a transportation requirements management database in RDD-100. Functions and requirements for transporting the following DOE radioactive waste/material are contained in the database: high level radioactive waste (HLW), low-level radioactive waste (LLW), mixed low-level radioactive waste (MLLW), nuclear materials (NM), spent nuclear fuel (SNF), and transuranic waste (TRU waste). The requirements will be used in the development of standard transportation protocols for DOE shipping. The protocols will then be combined into a DOE Transportation Program Management Guide, which will be used to standardize DOE transportation processes.

  7. DOE Releases Final Request for Proposal for Waste Isolation Pilot Plant

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

    (WIPP) Transportation Services Procurement | Department of Energy Waste Isolation Pilot Plant (WIPP) Transportation Services Procurement DOE Releases Final Request for Proposal for Waste Isolation Pilot Plant (WIPP) Transportation Services Procurement July 14, 2016 - 1:00pm Addthis Media Contact: Bill Taylor, 575-234-7591 Cincinnati -- The U.S. Department of Energy (DOE) Environmental Management Consolidated Business Center (EMCBC) today issued a Final Request for Proposal (RFP) for Waste

  8. Working Copy

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

    At DOE Working At DOE Working At DOE Only Here...Will you Define the Future of Energy The people of DOE are engaged in a wide range of challenging and innovative work - from participating in groundbreaking international initiatives like the Global Nuclear Partnership, to solar power demonstration projects, to projects that convert captured carbon dioxide (CO2) emissions from industrial sources into fuel, plastics, and fertilizers. Only here can the diversity of activities throughout our

  9. Beam Transport

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

    Beam Transport A simplified drawing of the beam transport system from the linac to Target-1 (Lujan Center), Target-2 (Blue Room) and Target-4 is shown below. In usual operation ...

  10. Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing |

    Office of Environmental Management (EM)

    Multiple Users | Department of Energy Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users January 30, 2013 - 12:00pm Addthis Transportation Tracking and Communication System users can now track shipments of radioactive materials and access transportation information on mobile devices. Transportation Tracking and Communication System users can now track shipments of

  11. Environmental assessment for the Radioactive and Mixed Waste Management Facility: Sandia National Laboratories/New Mexico

    SciTech Connect (OSTI)

    Not Available

    1993-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-0466) under the National Environmental Policy Act (NEPA) of 1969 for the proposed completion of construction and subsequent operation of a central Radioactive and Mixed Waste Management Facility (RMWMF), in the southeastern portion of Technical Area III at Sandia National Laboratory, Albuquerque (SNLA). The RMWMF is designed to receive, store, characterize, conduct limited bench-scale treatment of, repackage, and certify low-level waste (LLW) and mixed waste (MW) (as necessary) for shipment to an offsite disposal or treatment facility. The RMWMF was partially constructed in 1989. Due to changing regulatory requirements, planned facility upgrades would be undertaken as part of the proposed action. These upgrades would include paving of road surfaces and work areas, installation of pumping equipment and lines for surface impoundment, and design and construction of air locks and truck decontamination and water treatment systems. The proposed action also includes an adjacent corrosive and reactive metals storage area, and associated roads and paving. LLW and MW generated at SNLA would be transported from the technical areas to the RMWMF in containers approved by the Department of Transportation. The RMWMF would not handle nonradioactive hazardous waste. Based on the analysis in the EA, the proposed completion of construction and operation of the RMWMF does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of NEPA. Therefore, preparation of an environmental impact statement for the proposed action is not required.

  12. TRANSPORTATION CASK RECEIPT AND RETURN FACILITY WORKER DOSE ASSESSMENT

    SciTech Connect (OSTI)

    V. Arakali

    2005-02-24

    The purpose of this design calculation is to estimate radiation doses received by personnel working in the Transportation Cask Receipt and Return Facility (TCRRF) of the repository including the personnel at the security gate and cask staging areas. This calculation is required to support the preclosure safety analysis (PCSA) to ensure that the predicted doses are within the regulatory limits prescribed by the U.S. Nuclear Regulatory Commission (NRC). The Cask Receipt and Return Facility receives NRC licensed transportation casks loaded with spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The TCRRF operation starts with the receipt, inspection, and survey of the casks at the security gate and the staging areas, and proceeds to the process facilities. The transportation casks arrive at the site via rail cars or trucks under the guidance of the national transportation system. This calculation was developed by the Environmental and Nuclear Engineering organization and is intended solely for the use of Design and Engineering in work regarding facility design. Environmental and Nuclear Engineering personnel should be consulted before using this calculation for purposes other than those stated herein or for use by individuals other than authorized personnel in the Environmental and Nuclear Engineering organization.

  13. Arrival condition of spent fuel after storage, handling, and transportation

    SciTech Connect (OSTI)

    Bailey, W.J.; Pankaskie, P.J.; Langstaff, D.C.; Gilbert, E.R.; Rising, K.H.; Schreiber, R.E.

    1982-11-01

    This report presents the results of a study conducted to determine the probable arrival condition of spent light-water reactor (LWR) fuel after handling and interim storage in spent fuel storage pools and subsequent handling and accident-free transport operations under normal or slightly abnormal conditions. The objective of this study was to provide information on the expected condition of spent LWR fuel upon arrival at interim storage or fuel reprocessing facilities or at disposal facilities if the fuel is declared a waste. Results of a literature survey and data evaluation effort are discussed. Preliminary threshold limits for storing, handling, and transporting unconsolidated spent LWR fuel are presented. The difficulty in trying to anticipate the amount of corrosion products (crud) that may be on spent fuel in future shipments is also discussed, and potential areas for future work are listed. 95 references, 3 figures, 17 tables.

  14. TRANSPORT THROUGH CRACKED CONCRETE: LITERATURE REVIEW

    SciTech Connect (OSTI)

    Langton, C.

    2012-05-11

    Concrete containment structures and cement-based fills and waste forms are used at the Savannah River Site to enhance the performance of shallow land disposal systems designed for containment of low-level radioactive waste. Understanding and measuring transport through cracked concrete is important for describing the initial condition of radioactive waste containment structures at the Savannah River Site (SRS) and for predicting performance of these structures over time. This report transmits the results of a literature review on transport through cracked concrete which was performed by Professor Jason Weiss, Purdue University per SRR0000678 (RFP-RQ00001029-WY). This review complements the NRC-sponsored literature review and assessment of factors relevant to performance of grouted systems for radioactive waste disposal. This review was performed by The Center for Nuclear Waste Regulatory Analyses, San Antonio, TX, and The University of Aberdeen, Aberdeen Scotland and was focused on tank closure. The objective of the literature review on transport through cracked concrete was to identify information in the open literature which can be applied to SRS transport models for cementitious containment structures, fills, and waste forms. In addition, the literature review was intended to: (1) Provide a framework for describing and classifying cracks in containment structures and cementitious materials used in radioactive waste disposal, (2) Document the state of knowledge and research related to transport through cracks in concrete for various exposure conditions, (3) Provide information or methodology for answering several specific questions related to cracking and transport in concrete, and (4) Provide information that can be used to design experiments on transport through cracked samples and actual structures.

  15. Glassy slags as novel waste forms for remediating mixed wastes with high metal contents

    SciTech Connect (OSTI)

    Feng, X.; Wronkiewicz, D.J.; Bates, J.K.; Brown, N.R.; Buck, E.C.; Gong, M.; Ebert, W.L.

    1994-03-01

    Argonne National Laboratory (ANL) is developing a glassy slag final waste form for the remediation of low-level radioactive and mixed wastes with high metal contents. This waste form is composed of various crystalline and metal oxide phases embedded in a silicate glass phase. This work indicates that glassy slag shows promise as final waste form because (1) it has similar or better chemical durability than high-level nuclear waste (HLW) glasses, (2) it can incorporate large amounts of metal wastes, (3) it can incorporate waste streams having low contents of flux components (boron and alkalis), (4) it has less stringent processing requirements (e.g., viscosity and electric conductivity) than glass waste forms, (5) its production can require little or no purchased additives, which can result in greater reduction in waste volume and overall treatment costs. By using glassy slag waste forms, minimum additive waste stabilization approach can be applied to a much wider range of waste streams than those amenable only to glass waste forms.

  16. Waste Information Management System-2012 - 12114

    SciTech Connect (OSTI)

    Upadhyay, H.; Quintero, W.; Shoffner, P.; Lagos, L.; Roelant, D.

    2012-07-01

    The Waste Information Management System (WIMS) -2012 was updated to support the Department of Energy (DOE) accelerated cleanup program. The schedule compression required close coordination and a comprehensive review and prioritization of the barriers that impeded treatment and disposition of the waste streams at each site. Many issues related to waste treatment and disposal were potential critical path issues under the accelerated schedule. In order to facilitate accelerated cleanup initiatives, waste managers at DOE field sites and at DOE Headquarters in Washington, D.C., needed timely waste forecast and transportation information regarding the volumes and types of radioactive waste that would be generated by DOE sites over the next 40 years. Each local DOE site historically collected, organized, and displayed waste forecast information in separate and unique systems. In order for interested parties to understand and view the complete DOE complex-wide picture, the radioactive waste and shipment information of each DOE site needed to be entered into a common application. The WIMS application was therefore created to serve as a common application to improve stakeholder comprehension and improve DOE radioactive waste treatment and disposal planning and scheduling. WIMS allows identification of total forecasted waste volumes, material classes, disposition sites, choke points, technological or regulatory barriers to treatment and disposal, along with forecasted waste transportation information by rail, truck and inter-modal shipments. The Applied Research Center (ARC) at Florida International University (FIU) in Miami, Florida, developed and deployed the web-based forecast and transportation system and is responsible for updating the radioactive waste forecast and transportation data on a regular basis to ensure the long-term viability and value of this system. WIMS continues to successfully accomplish the goals and objectives set forth by DOE for this project. It has

  17. Robust Solution to Difficult Hydrogen Issues When Shipping Transuranic Waste to the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    Countiss, S. S.; Basabilvazo, G. T.; Moody, D. C. III; Lott, S. A.; Pickerell, M.; Baca, T.; CH2M Hill; Tujague, S.; Svetlik, H.; Hannah, T.

    2003-02-27

    The Waste Isolation Pilot Plant (WIPP) has been open, receiving, and disposing of transuranic (TRU) waste since March 26, 1999. The majority of the waste has a path forward for shipment to and disposal at the WIPP, but there are about two percent (2%) or approximately 3,020 cubic meters (m{sup 3}) of the volume of TRU waste (high wattage TRU waste) that is not shippable because of gas generation limits set by the U.S. Nuclear Regulatory Commission (NRC). This waste includes plutonium-238 waste, solidified organic waste, and other high plutonium-239 wastes. Flammable gases are potentially generated during transport of TRU waste by the radiolysis of hydrogenous materials and therefore, the concentration at the end of the shipping period must be predicted. Two options are currently available to TRU waste sites for solving this problem: (1) gas generation testing on each drum, and (2) waste form modification by repackaging and/or treatment. Repackaging some of the high wattage waste may require up to 20:1 drum increase to meet the gas generation limits of less than five percent (5%) hydrogen in the inner most layer of confinement (the layer closest to the waste). (This is the limit set by the NRC.) These options increase waste handling and transportation risks and there are high costs and potential worker exposure associated with repackaging this high-wattage TRU waste. The U.S. Department of Energy (DOE)'s Carlsbad Field Office (CBFO) is pursuing a twofold approach to develop a shipping path for these wastes. They are: regulatory change and technology development. For the regulatory change, a more detailed knowledge of the high wattage waste (e.g., void volumes, gas generation potential of specific chemical constituents) may allow refinement of the current assumptions in the gas generation model for Safety Analysis Reports for Packaging for Contact-Handled (CH) TRU waste. For technology development, one of the options being pursued is the use of a robust container

  18. Project Plan, Status, and Lessons Learned for the LANL 3,706 m{sup 3} TRU Waste Campaign - 13085

    SciTech Connect (OSTI)

    Johns-Hughes, K.W.; Clemmons, J.S.; Cox, D.R.; Hargis, K.M.; Bishop, M.L.

    2013-07-01

    The Los Alamos National Laboratory (LANL) is currently engaged in a campaign to disposition 3,706 m{sup 3} of transuranic (TRU) waste stored above grade at its Technical Area 54 (TA-54) Area G waste management facility before June 30, 2014. This campaign includes complete removal of all non-cemented above-grade TRU waste that was in storage on October 1, 2011, and is defined as 3,706 m{sup 3} of material. TRU waste containers were placed into storage up to 40 years ago, and most of the older containers must be remediated to address compliance issues before the waste can be characterized, certified as meeting the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), and shipped for disposition. More than half of the remaining TRU waste volume stored above grade is contained within oversize boxes that contain waste items that must be repackaged or size reduced. Facilities and major types of equipment needed to remediate and characterize the TRU waste inventory include two additional oversize box processing lines that are being brought into service as Nuclear Hazard Category III facilities in fiscal year (FY) 2013. Multiple work shifts are scheduled for most remediation lines in FY 2013. An integrated risk-based project management schedule for all disposition activities has been developed that is based on a 'Solution Package' approach. Inventories of containers that have issues in common were compiled into about 15 waste categories and about 75 'Solution Packages' that identify all of the activities needed to disposition the inventory of TRU waste in storage. Scheduled activities include all precursor activities to begin remediation, remediation processing, characterization and certification to the WIPP WAC, and shipping of containers to WIPP. Other industrial processing practices that have been adopted to improve efficiency include staging of containers for remediation, characterization, and shipping; establishment of a transportation center; and load

  19. Thermoelectrics: From Space Power Systems to Terrestrial Waste Heat Recovery Applications

    Broader source: Energy.gov [DOE]

    Progress in reliable high temperature segmented thermoelectric devices and potential for producing electricity from waste heat from energy intensive industrial processes and transportation vehicles exhaust are discussed

  20. Y-12 completes waste removal project two years ahead of schedule...

    National Nuclear Security Administration (NNSA)

    to meet Department of Transportation shipping requirements for uranium content. ... These wastes were split among containers to reduce the uranium content and then "rocked ...

  1. OSS 19.5 Hazardous Waste Operations and Emergency Response 3/21/95

    Broader source: Energy.gov [DOE]

     The objective of this surveillance is to ensure that workers who are performing activities associated with characterizing, handling, processing, storing or transporting hazardous wastes are...

  2. Transportation for Lab Employees

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

    Transportation Transportation for Lab Employees Choose the transportation option that works best for you: car, rail, taxi or public transit Contact Us Email Getting to the Lab Whether it be for an interview or a day on the job, using the right map and directions will make your travel to the Lab much easier. Visit our Maps webpage for maps and directions on how to get to Los Alamos from various communities in Northern New Mexico. Commuting options Sixty-six percent of the Los Alamos workforce

  3. EERE Success Story-Oregon: Clean Energy Works Coordinates Energy...

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

    ... Positive Impact EERE-funded program is reducing energy waste, which is slowing the effects of climate change. Locations Oregon Partners Clean Energy Works Oregon EERE Investment ...

  4. LANL highlights explosives work | National Nuclear Security Administra...

    National Nuclear Security Administration (NNSA)

    leader in explosives applications. It will feature LANL's work with explosives, from synthesis of new molecules to waste treatment. The exhibit also examines a variety of...

  5. Optimization of Waste Disposal - 13338

    SciTech Connect (OSTI)

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

    2013-07-01

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

  6. Glass-Ceramic Waste Forms for Uranium and Plutonium Residues Wastes - 13164

    SciTech Connect (OSTI)

    Stewart, Martin W.A.; Moricca, Sam A.; Zhang, Yingjie; Day, R. Arthur; Begg, Bruce D.; Scales, Charlie R.; Maddrell, Ewan R.; Hobbs, Jeff

    2013-07-01

    A program of work has been undertaken to treat plutonium-residues wastes at Sellafield. These have arisen from past fuel development work and are highly variable in both physical and chemical composition. The principal radiological elements present are U and Pu, with small amounts of Th. The waste packages contain Pu in amounts that are too low to be economically recycled as fuel and too high to be disposed of as lower level Pu contaminated material. NNL and ANSTO have developed full-ceramic and glass-ceramic waste forms in which hot-isostatic pressing is used as the consolidation step to safely immobilize the waste into a form suitable for long-term disposition. We discuss development work on the glass-ceramic developed for impure waste streams, in particular the effect of variations in the waste feed chemistry glass-ceramic. The waste chemistry was categorized into actinides, impurity cations, glass formers and anions. Variations of the relative amounts of these on the properties and chemistry of the waste form were investigated and the waste form was found to be largely unaffected by these changes. This work mainly discusses the initial trials with Th and U. Later trials with larger variations and work with Pu-doped samples further confirmed the flexibility of the glass-ceramic. (authors)

  7. file://\\\\troi2\\wwwroot\\TeamWorks\\index.htm

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

    the East 140 drift will continue to be the primary waste transport route. The WIPP Blood Drive was held June 14-15 and it was a great success. The two-day blood drive resulted...

  8. DOE Selects Two Small Businesses to Truck Transuranic Waste to New Mexico

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

    Waste Isolation Pilot Plant | Department of Energy Selects Two Small Businesses to Truck Transuranic Waste to New Mexico Waste Isolation Pilot Plant DOE Selects Two Small Businesses to Truck Transuranic Waste to New Mexico Waste Isolation Pilot Plant January 9, 2012 - 12:00pm Addthis Media Contact Bill Taylor 803-952-8564 bill.taylor@srs.gov Cincinnati - The Department of Energy (DOE) today awarded two small-business contracts to CAST Specialty Transportation, Inc. and Visionary Solutions,

  9. STATEMENT OF WORK (SOW)

    National Nuclear Security Administration (NNSA)

    including TTR. Waste acceptance services will be performed at the NNSS and at waste generator sites across the DOE Complex. 1.4 Performance Requirements: Performance requirements...

  10. How NIF Works

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

    How Much Do You Spend on Energy? How Much Do You Spend on Energy? U.S.A. Energy Expenditure per person Click on a state Energy Expenditure $3724 per person in 2012 Transportation ▀▀▀▀▀ Residential ▀▀▀▀▀ Data: EIA State Energy Data System View All Maps Addthis

    works How NIF Works A weak laser pulse-about 1 billionth of a joule-is created, split, and carried on optical fibers to 48 preamplifiers that increase the pulse's energy by a factor of 10 billion, to a few joules. The

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

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

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

  13. Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-06

    The Quality Assurance Project Plan (QAPjP) has been prepared for waste characterization activities to be conducted by the Transuranic (TRU) Project at the Hanford Site to meet requirements set forth in the Waste Isolation Pilot Plan (WIPP) Hazardous Waste Facility Permit, 4890139088-TSDF, Attachment B, including Attachments B1 through B6 (WAP) (DOE, 1999a). The QAPjP describes the waste characterization requirements and includes test methods, details of planned waste sampling and analysis, and a description of the waste characterization and verification process. In addition, the QAPjP includes a description of the quality assurance/quality control (QA/QC) requirements for the waste characterization program. Before TRU waste is shipped to the WIPP site by the TRU Project, all applicable requirements of the QAPjP shall be implemented. Additional requirements necessary for transportation to waste disposal at WIPP can be found in the ''Quality Assurance Program Document'' (DOE 1999b) and HNF-2600, ''Hanford Site Transuranic Waste Certification Plan.'' TRU mixed waste contains both TRU radioactive and hazardous components, as defined in the WLPP-WAP. The waste is designated and separately packaged as either contact-handled (CH) or remote-handled (RH), based on the radiological dose rate at the surface of the waste container. RH TRU wastes are not currently shipped to the WIPP facility.

  14. Truck and rail charges for shipping spent fuel and nuclear waste

    SciTech Connect (OSTI)

    McNair, G.W.; Cole, B.M.; Cross, R.E.; Votaw, E.F.

    1986-06-01

    The Pacific Northwest Laboratory developed techniques for calculating estimates of nuclear-waste shipping costs and compiled a listing of representative data that facilitate incorporation of reference shipping costs into varius logistics analyses. The formulas that were developed can be used to estimate costs that will be incurred for shipping spent fuel or nuclear waste by either legal-weight truck or general-freight rail. The basic data for this study were obtained from tariffs of a truck carrier licensed to serve the 48 contiguous states and from various rail freight tariff guides. Also, current transportation regulations as issued by the US Department of Transportation and the Nuclear Regulatory Commission were investigated. The costs that will be incurred for shipping spent fuel and/or nuclear waste, as addressed by the tariff guides, are based on a complex set of conditions involving the shipment origin, route, destination, weight, size, and volume and the frequency of shipments, existing competition, and the length of contracts. While the complexity of these conditions is an important factor in arriving at a ''correct'' cost, deregulation of the transportation industry means that costs are much more subject to negotiation and, thus, the actual fee that will be charged will not be determined until a shipping contract is actually signed. This study is designed to provide the baseline data necessary for making comparisons of the estimated costs of shipping spent fuel and/or nuclear wastes by truck and rail transportation modes. The scope of the work presented in this document is limited to the costs incurred for shipping, and does not include packaging, cask purchase/lease costs, or local fees placed on shipments of radioactive materials.

  15. Power, Optimization, Waste Estimating, Resourcing Tool

    Energy Science and Technology Software Center (OSTI)

    2009-08-13

    Planning, Optimization, Waste Estimating, Resourcing tool (POWERtool) is a comprehensive relational database software tool that can be used to develop and organize a detailed project scope, plan work tasks, develop bottoms-up field cost and waste estimates for facility Deactivation and Decommissioning (D&D), equipment, and environmental restoration (ER) projects and produces resource-loaded schedules.

  16. Hanford Dangerous Waste Permit

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

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

  17. Assessing waste management systems using reginalt software

    SciTech Connect (OSTI)

    Meshkov, N.K.; Camasta, S.F.; Gilbert, T.L.

    1988-03-01

    A method for assessing management systems for low-level radioactive waste is being developed for US Department of Energy. The method is based on benefit-cost-risk analysis. Waste management is broken down into its component steps, which are generation, treatment, packaging, storage, transportation, and disposal. Several different alternatives available for each waste management step are described. A particular waste management system consists of a feasible combination of alternatives for each step. Selecting an optimal waste management system would generally proceed as follows: (1) qualitative considerations are used to narrow down the choice of waste management system alternatives to a manageable number; (2) the costs and risks for each of these system alternatives are evaluated; (3) the number of alternatives is further reduced by eliminating alternatives with similar risks but higher costs, or those with similar costs but higher risks; (4) a trade-off factor between cost and risk is chosen and used to compute the objective function (sum of the cost and risk); and (5) the selection of the optimal waste management system among the remaining alternatives is made by choosing the alternative with the smallest value for the objective function. The authors propose that the REGINALT software system, developed by EG and G Idaho, Inc., as an acid for managers of low-level commerical waste, be augmented for application to the managment of DOE-generated waste. Specific recommendations for modification of the REGINALT system are made. 51 refs., 3 figs., 2 tabs.

  18. Cementitious waste option scoping study report

    SciTech Connect (OSTI)

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

    1998-02-01

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

  19. WM Committee FY'16 Work Plan

    Office of Environmental Management (EM)

    AT WORK WIPP AT WORK February 1, 2010 - 12:00pm Addthis Carlsbad, NM - Transuranic (TRU) waste cleanup efforts are underway across the DOE complex, as the Waste Isolation Pilot Plant (WIPP) wraps up its 11th year of disposal operations. The Carlsbad Field Office (CBFO) manages the DOE's National TRU Program (NTP) Office and WIPP facility operations. TRU waste temporarily stored at DOE generator sites around the country is shipped to WIPP and disposed in rooms mined out of an ancient salt

  20. Low-level waste management alternatives and analysis in DOE`s programmatic environmental impact statement

    SciTech Connect (OSTI)

    Gerstein, J.S.

    1993-03-01

    The Department of Energy is preparing a Programmatic Environmental Impact Statement (PEIS) for the Environmental Restoration and Waste Management Program. The PEIS has been divided into an Environmental Restoration section and a Waste Management section. Each section has a unique set of alternatives. This paper will focus on the waste management alternatives and analysis. The set of alternatives for waste management has been divided into waste categories. These categories are: high-level waste, transuranic waste, low-level waste, low-level mixed waste, greater-than-class C and low-level waste from commercial sources, hazardous waste, and spent nuclear fuel. This paper will discuss the alternatives and analytical approach that will be used to evaluate these alternatives for the low-level waste section. Although the same alternatives will be considered for all waste types, the analysis will be performed separately for each waste type. In the sections that follow, information will be provided on waste management configurations, the analysis of waste management alternatives, waste types and locations, facility and transportation activities, the facility and transportation impacts assessment, and the compilation of impacts.

  1. Evaluation and compilation of DOE waste package test data: Biannual report, August 1987--January 1988

    SciTech Connect (OSTI)

    Interrante, C.; Escalante, E.; Fraker, A.; Ondik, H.; Plante, E.; Ricker, R.; Ruspi, J.

    1988-08-01

    This report summarizes results of the National Bureau of Standards (NBS) evaluations on waste packages designed for containment of radioactive high-level nuclear waste (HLW). The waste package is a proposed engineered barrier that is part of a permanent repository for HLW. Metal alloys are the principal barriers within the engineered system. Since enactment of the Budget Reconciliation Act for Fiscal Year 1988, the Yucca Mountain, Nevada, site (in which tuff is the geologic medium) is the only site that will be characterized for use as high-level nuclear waste repository. During the reporting period of August 1987 to January 1988, five reviews were completed for tuff, and these were grouped into the categories: ferrous alloys, copper, groundwater chemistry, and glass. Two issues are identified for the Yucca Mountain site: the approach used to calculate corrosion rates for ferrous alloys, and crevice corrosion was observed in a copper-nickel alloy. Plutonium can form pseudo-colloids that may facilitate transport. NBS work related to the vitrification of HLW borosilicate glass at the West Valley Demonstration Project (WVDP) and the Defense Waste Processing Facility (DWPF) and activities of the DOE Materials Characterization Center (MCC) for the 6-month reporting period are also included. 27 refs., 3 figs.

  2. Solid waste recycling programs at Rocky Flats

    SciTech Connect (OSTI)

    Millette, R.L.; Blackman, T.E.; Shepard, M.D.

    1994-12-31

    The Rocky Flats (RFP) recycling programs for solid waste materials have been in place for over ten years. Within the last three years, the programs were centralized under the direction of the Rocky Flats Waste Minimization department, with the assistance of various plant organizations (e.g., Trucking, Building Services, Regulated Waste Operations, property Utilization and Disposal and Security). Waste Minimization designs collection and transportation systems for recyclable materials and evaluates recycling markets for opportunities to add new commodities to the existing programs. The Waste Minimization department also promotes employee participation in the Rocky Flats Recycling Programs, and collects all recycling data for publication. A description of the program status as of January 1994 is given.

  3. TRU TeamWorks

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

    , 2004 By the Numbers WIPP marks five-year anniversary Shipments scheduled to arrive at WIPP for the week of 4/4/04 - 4/10/04: 18 Total shipments received at WIPP: 2,456 Total volume disposed at WIPP: 19,042 m 3 FY04 Performance Metrics D E P A R T M E N T O F E N E R G Y U N I T E D S T A T ES O F A M E R I C A TeamWorks TeamWorks TRU A weekly e-newsletter for the Waste Isolation Pilot Plant team For those who endured the early morning cold of March 26, 1999, to witness WIPP's first shipment,

  4. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

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

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

  5. Legacy Waste | Department of Energy

    Office of Environmental Management (EM)

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

  6. Transportation System Concept of Operations

    SciTech Connect (OSTI)

    N. Slater-Thompson

    2006-08-16

    The Nuclear Waste Policy Act of 1982 (NWPA), as amended, authorized the DOE to develop and manage a Federal system for the disposal of SNF and HLW. OCRWM was created to manage acceptance and disposal of SNF and HLW in a manner that protects public health, safety, and the environment; enhances national and energy security; and merits public confidence. This responsibility includes managing the transportation of SNF and HLW from origin sites to the Repository for disposal. The Transportation System Concept of Operations is the core high-level OCRWM document written to describe the Transportation System integrated design and present the vision, mission, and goals for Transportation System operations. By defining the functions, processes, and critical interfaces of this system early in the system development phase, programmatic risks are minimized, system costs are contained, and system operations are better managed, safer, and more secure. This document also facilitates discussions and understanding among parties responsible for the design, development, and operation of the Transportation System. Such understanding is important for the timely development of system requirements and identification of system interfaces. Information provided in the Transportation System Concept of Operations includes: the functions and key components of the Transportation System; system component interactions; flows of information within the system; the general operating sequences; and the internal and external factors affecting transportation operations. The Transportation System Concept of Operations reflects OCRWM's overall waste management system policies and mission objectives, and as such provides a description of the preferred state of system operation. The description of general Transportation System operating functions in the Transportation System Concept of Operations is the first step in the OCRWM systems engineering process, establishing the starting point for the lower level

  7. ORNL measurements at Hanford Waste Tank TX-118

    SciTech Connect (OSTI)

    Koehler, P.E.; Mihalczo, J.T.

    1995-02-01

    A program of measurements and calculations to develop a method of measuring the fissionable material content of the large waste storage tanks at the Hanford, Washington, site is described in this report. These tanks contain radioactive waste from the processing of irradiated fuel elements from the plutonium-producing nuclear reactors at the Hanford site. Time correlation and noise analysis techniques, similar to those developed for and used in the Nuclear Weapons Identification System at the Y-12 Plant in Oak Ridge, Tennessee, will be used at the Hanford site. Both ``passive`` techniques to detect the neutrons emitted spontaneously from the waste in the tank and ``active`` techniques using AmBe and {sup 252}Cf neutron sources to induce fissions will be used. This work is divided into three major tasks: (1) development of high-sensitivity neutron detectors that can selectively count only neutrons in the high {gamma} radiation fields in the tanks, (2) Monte Carlo neutron transport calculations using both the KENO and MCNP codes to plan and analyze the measurements, and (3) the measurement of time-correlated neutrons by time and frequency analysis to distinguish spontaneous fission from sources inside the tanks. This report describes the development of the detector and its testing in radiation fields at the Radiation Calibration Facility at Oak Ridge National Laboratory and in tank TX-118 at the 200 W area at Westinghouse Hanford Company.

  8. Electrical and Thermal Transport Optimization of High Efficient...

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

    Electrical and Thermal Transport Optimization of High Efficient n-type Skutterudites Electrical and Thermal Transport Optimization of High Efficient n-type Skutterudites Work on ...

  9. The Hazardous Waste/Mixed Waste Disposal Facility

    SciTech Connect (OSTI)

    Bailey, L.L.

    1991-01-01

    The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy's (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency's (EPA's) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996.

  10. The Hazardous Waste/Mixed Waste Disposal Facility

    SciTech Connect (OSTI)

    Bailey, L.L.

    1991-12-31

    The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy`s (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency`s (EPA`s) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996.

  11. Microsoft Word - NR WIPP TRANSPORT RFP MARCH 30 2011f2

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

    Shipments Cincinnati -- The Department of Energy (DOE) today will issue a Request for Proposals for the continuation of carrier services to transport transuranic waste (TRU) ...

  12. Sustainable Transportation

    SciTech Connect (OSTI)

    2012-09-01

    This document highlights DOE's Office of Energy Efficiency and Renewable Energy's advancements in transportation technologies, alternative fuels, and fuel cell technologies.

  13. Tank Waste Committee

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

    3/15 Tank Waste Committee Priorities for advice on FY17 budget Not in priority order, numbering refers to last year's related advice points, per DOE response  (#1) The Board strongly urges DOE-Headquarters (HQ) to request full funding from Congress to meet all legal requirements of the ongoing cleanup work in FY 2016 and 2017 in addition to the following specific requests.  (#2) The Board advises DOE-ORP continue to request funding to proceed to empty leaking tanks (particularly AY-102 and

  14. Waste Generated from LMR-AMTEC Reactor Concept

    SciTech Connect (OSTI)

    Hasan, Ahmed; Mohamed, Yasser, T.; Mohammaden, Tarek, F.

    2003-02-25

    The candidate Liquid Metal Reactor-Alkali Metal Thermal -to- Electric Converter (LMR-AMTEC) is considered to be the first reactor that would use pure liquid potassium as a secondary coolant, in which potassium vapor aids in the conversion of thermal energy to electric energy. As with all energy production, the thermal generation of electricity produces wastes. These wastes must be managed in ways which safeguard human health and minimize their impact on the environment. Nuclear power is the only energy industry, which takes full responsibility for all its wastes. Based on the candidate design of the LMR-AMTEC components and the coolant types, different wastes will be generated from LMR. These wastes must be classified and characterized according to the U.S. Code of Federal Regulation, CFR. This paper defines the waste generation and waste characterization from LMR-AMTEC and reviews the applicable U.S. regulations that govern waste transportation, treatment, storage and final disposition. The wastes generated from LMR-AMTEC are characterized as: (1) mixed waste which is generated from liquid sodium contaminated by fission products and activated corrosion products; (2) hazardous waste which is generated from liquid potassium contaminated by corrosion products; (3) spent nuclear fuel; and (4) low-level radioactive waste which is generated from the packing materials (e.g. activated carbon in cold trap and purification units). The regulations and management of these wastes are summarized in this paper.

  15. Waste remediation

    SciTech Connect (OSTI)

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

    2015-12-29

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

  16. Transportation needs assessment: Emergency response section

    SciTech Connect (OSTI)

    1989-05-01

    The transportation impacts of moving high level nuclear waste (HLNW) to a repository at Yucca Mountain in Nevada are of concern to the residents of the State as well as to the residents of other states through which the nuclear wastes might be transported. The projected volume of the waste suggests that shipments will occur on a daily basis for some period of time. This will increase the risk of accidents, including a catastrophic incident. Furthermore, as the likelihood of repository construction and operation and waste shipments increase, so will the attention given by the national media. This document is not to be construed as a willingness to accept the HLNW repository on the part of the State. Rather it is an initial step in ensuring that the safety and well-being of Nevada residents and visitors and the State`s economy will be adequately addressed in federal decision-making pertaining to the transportation of HLNW into and across Nevada for disposal in the proposed repository. The Preferred Transportation System Needs Assessment identifies critical system design elements and technical and social issues that must be considered in conducting a comprehensive transportation impact analysis. Development of the needs assessment and the impact analysis is especially complex because of the absence of information and experience with shipping HLNW and because of the ``low probability, high consequence`` aspect of the transportation risk.

  17. NREL: Transportation Research - Subscribe to the Transportation and

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

    Hydrogen Newsletter Subscribe to the Transportation and Hydrogen Newsletter To subscribe to or unsubscribe from the Transportation and Hydrogen Newsletter, complete one of the forms below. Subscribe To subscribe to the newsletter, submit your email address. Email: Submit Unsubscribe To unsubscribe from the newsletter, submit your email address. Email: Submit Printable Version Transportation Research Home Capabilities Projects Success Stories Facilities Working with Us Publications Data &

  18. SRS Liquid Waste Program Partnering Agreement | Department of Energy

    Office of Environmental Management (EM)

    Liquid Waste Program Partnering Agreement SRS Liquid Waste Program Partnering Agreement We the members of the SRS Liquid Waste Partnering Team do hereby mutually agree to work in a collaborative and cooperative manner through open communication and coordination with team members, and consistent and complimentary existing defined policies and practices, to develop and reinforce the partnering process, which will result in accomplishing the mission and realizing the vision of the SRS Liquid Waste

  19. Draft Advice for the Hanford Facility Dangerous Waste Permit

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

    Issue Managers Working Draft Page 1 of 19 Draft Advice for the Hanford Facility Dangerous Waste Permit (Site-Wide Permit) Background: The Draft Hanford Facility Dangerous Waste Permit for the Treatment, Storage, and Disposal of Dangerous Waste (Permit) is the Washington State Department of Ecology's (Ecology) tool for regulating hazardous waste at Hanford. The Permit(s) establish conditions that the U.S. Department of Energy (DOE) and its contractors must meet to protect human health and the

  20. Transportation Energy

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

    Energy Home/Transportation Energy CRF_climatechange Permalink Gallery Understanding Hazardous Combustion Byproducts Reduces Factors Impacting Climate Change CRF, Global Climate & Energy, News, News & Events, Transportation Energy Understanding Hazardous Combustion Byproducts Reduces Factors Impacting Climate Change By Micheal Padilla Researchers at Sandia's Combustion Research Facility are developing the understanding necessary to build cleaner combustion technologies that will in turn

  1. Working Group Presentation for Discussion

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

    1, 2016 MEMORANDUM FOR: IAN MEAD ASSISTANT ADMINISTRATOR FOR ENERGY ANALYSIS PAUL HOLTBERG TEAM LEADER ANALYSIS INTEGRATION TEAM JIM TURNURE DIRECTOR OFFICE OF ENERGY CONSUMPTION AND EFFICIENCY ANALYSIS FROM: TRANSPORTATION CONSUMPTION AND EFFICIENCY ANALYSIS TEAM SUBJECT: Annual Energy Outlook (AEO)2017 Transportation Working Group Meeting Summary (presented on 08-31-2016) Attendees: David Daniels (EIA) Mindi Farber-DeAnda (EIA) Devi Mishra (EIA) Alicia Birky (Energetics) Sarah Garman (DOE)

  2. EIS-0250-S2: Supplemental EIS for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada- Nevada Rail Transportation Corridor

    Broader source: Energy.gov [DOE]

    This SEIS is to evaluate the potential environmental impacts of constructing and operating a railroad for shipments of spent nuclear fuel and high-level radioactive waste from an existing rail line in Nevada to a geologic repository at Yucca Mountain. The purpose of the evaluation is to assist the Department in deciding whether to construct and operate a railroad in Nevada, and if so, in which corridor and along which specific alignment within the selected corridor.

  3. Waste Segregation Based on Derived Clearance Levels

    SciTech Connect (OSTI)

    Garisto, N.C.; Parhizgari, Z.

    2008-07-01

    This paper describes the methodology and results of a radiological modeling in support of an application to release very low level radiologically contaminated waste from regulatory control and allow its haulage and disposal in a hazardous waste landfill. The Canadian regulatory body responsible for licensing operations involving nuclear materials (the Canadian Nuclear Safety Commission), has not yet formally defined clearance levels for free release of low level radiologically contaminated waste. The IAEA clearance levels have been derived for certain situations and receptor characteristics, which might be too conservative for an actual case. A site-specific pathways analysis was therefore completed to define conditional clearance levels using the concept of de minimis dose limit. Derived Conditional Clearance Levels were calculated for each radionuclide based on the maximally exposed hypothetical individuals to determine whether each waste stream can be 'cleared' from regulatory controls. The results showed that haulage of the waste from the station to the haulage/processing facility and transportation of waste or sludge from the haulage/processing facility to the disposal facility, handling of the waste or sludge at the haulage/processing facility, and incineration and/or disposal of waste or sludge at the disposal facility would not expose the workers to doses above 0.1 {mu}Sv/yr., which is less than the de minimis dose limit of 10 {mu}Sv/yr. (authors)

  4. Hanford Waste Vitrification Plant applied technology plan

    SciTech Connect (OSTI)

    Kruger, O.L.

    1990-09-01

    This Applied Technology Plan describes the process development, verification testing, equipment adaptation, and waste form qualification technical issues and plans for resolution to support the design, permitting, and operation of the Hanford Waste Vitrification Plant. The scope of this Plan includes work to be performed by the research and development contractor, Pacific Northwest Laboratory, other organizations within Westinghouse Hanford Company, universities and companies with glass technology expertise, and other US Department of Energy sites. All work described in this Plan is funded by the Hanford Waste Vitrification Plant Project and the relationship of this Plan to other waste management documents and issues is provided for background information. Work to performed under this Plan is divided into major areas that establish a reference process, develop an acceptable glass composition envelope, and demonstrate feed processing and glass production for the range of Hanford Waste Vitrification Plant feeds. Included in this work is the evaluation and verification testing of equipment and technology obtained from the Defense Waste Processing Facility, the West Valley Demonstration Project, foreign countries, and the Hanford Site. Development and verification of product and process models and other data needed for waste form qualification documentation are also included in this Plan. 21 refs., 4 figs., 33 tabs.

  5. Update on EM Transportation Program Activities

    Office of Environmental Management (EM)

    to: 2012 National Transportation Stakeholders Forum Knoxville, TN May 16, 2012 1  Continue to manage waste inventories in a safe and compliant manner.  Address high risk waste in a cost- effective manner.  Maintain and optimize current disposal capability for future generations.  Develop future disposal capacity in a complex environment.  Promote the development of treatment and disposal alternatives in the commercial sector.  Review current policies and directives and provide

  6. Transuranic Waste Requirements

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

    1999-07-09

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

  7. Radioactive Waste Management

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

    1984-02-06

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

  8. Salt Waste Processing Initiatives

    Office of Environmental Management (EM)

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

  9. Hanford Tank Waste Retrieval,

    Office of Environmental Management (EM)

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

  10. Tank Waste Strategy Update

    Office of Environmental Management (EM)

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

  11. Waste Heat Recovery

    Office of Environmental Management (EM)

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

  12. Working Copy

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

    1 Effective Date: 02/03/14 WP 12-IS.01-6 Revision 11 Industrial Safety Program - Visitor, Vendor, User, Tenant, and Subcontractor Safety Controls Cognizant Section: Industrial Safety/Industrial Hygiene Approved By: Tom Ferguson Working Copy Industrial Safety Program - Visitor, Vendor, User, Tenant, and Subcontractor Safety Controls WP 12-IS.01-6, Rev. 11 2 TABLE OF CONTENTS CHANGE HISTORY SUMMARY ..................................................................................... 7 ACRONYMS AND

  13. Safety evaluation for packaging (onsite) for concrete-shielded RHTRU waste drum for the 327 postirradiation testing laboratory

    SciTech Connect (OSTI)

    Adkins, H.E.

    1996-10-29

    This safety evaluation for packaging authorizes onsite transport of Type B quantities of radioactive material in the Concrete- Shielded Remote-Handled Transuranic Waste (RH TRU) Drum per WHC-CM-2-14, Hazardous Material Packaging and Shipping. The drum will be used for transport of 327 Building legacy waste from the 300 Area to the Transuranic Waste Storage and Assay Facility in the 200 West Area and on to a Solid Waste Storage Facility, also in the 200 Area.

  14. Development of polyphase ceramics for the immobilization of high-level Defense nuclear waste

    SciTech Connect (OSTI)

    Morgan, P.E.D.; Harker, A.B.; Clarke, D.R.; Flintoff, J.J.; Shaw, T.M.

    1983-02-25

    The report contains two major sections: Section I - An Improved Polyphase Ceramic for High-Level Defense Nucleation Waste reports the work conducted on titanium-silica based ceramics for immobilizing Savannah River Plant waste. Section II - Formulation and Processing of Alumina Based Ceramic Nuclear Waste Forms describes the work conducted on developing a generic alumina and alumina-silica based ceramic waste form capable of immobilizing any nuclear waste with a high aluminum content. Such wastes include the Savannah River Plant wastes, Hanford neutralized purex wastes, and Hanford N-Reactor acid wastes. The design approach and process technology in the two reports demonstrate how the generic high waste loaded ceramic form can be applied to a broad range of nuclear waste compositions. The individual sections are abstracted and indexed separately.

  15. Sodium-Bearing Waste Treatment Alternatives Implementation Study

    SciTech Connect (OSTI)

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

    2004-07-01

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

  16. Feasibility study for a transportation operations system cask maintenance facility

    SciTech Connect (OSTI)

    Rennich, M.J.; Medley, L.G.; Attaway, C.R.

    1991-01-01

    The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a waste management program for the disposition of spent nuclear fuel (SNF) and high-level waste (HLW). The program will include a transportation system for moving the nuclear waste from the sources to a geologic repository for permanent disposal. Specially designed casks will be used to safely transport the waste. The cask systems must be operated within limits imposed by DOE, the Nuclear Regulatory Commission (NRC), and the Department of Transportation (DOT). A dedicated facility for inspecting, testing, and maintaining the cask systems was recommended by the General Accounting Office (in 1979) as the best means of assuring their operational effectiveness and safety, as well as regulatory compliance. In November of 1987, OCRWM requested a feasibility study be made of a Cask Maintenance Facility (CMF) that would perform the required functions. 46 refs., 16 figs., 13 tabs.

  17. HYDROGEN AND VOC RETENTION IN WASTE BOXES

    SciTech Connect (OSTI)

    PACE ME; MARUSICH RM

    2008-11-21

    The Hanford Waste Management Project Master Documented Safety Analysis (MDSA) (HNF-14741, 2003) identifies derived safety controls to prevent or mitigate the risks of a single-container deflagration during operations requiring moving, venting or opening transuranic (TRU)-waste containers. The issue is whether these safety controls are necessary for operations involving TRU-waste boxes that are being retrieved from burial at the Hanford Site. This paper investigates the potential for a deflagration hazard within these boxes and whether safety controls identified for drum deflagration hazards should be applied to operations involving these boxes. The study evaluates the accumulation of hydrogen and VOCs within the waste box and the transport of these gases and vapors out of the waste box. To perform the analysis, there were numerous and major assumptions made regarding the generation rate and the transport pathway dimensions and their number. Since there is little actual data with regards to these assumptions, analyses of three potential configurations were performed to obtain some indication of the bounds of the issue (the concentration of hydrogen or flammable VOCs within a waste box). A brief description of each of the three cases along with the results of the analysis is summarized.

  18. Microbial Transformation of TRU and Mixed Waste: Actinide Speciation and Waste Volume

    SciTech Connect (OSTI)

    Halada, Gary P

    2008-04-10

    In order to understand the susceptibility of transuranic and mixed waste to microbial degradation (as well as any mechanism which depends upon either complexation and/or redox of metal ions), it is essential to understand the association of metal ions with organic ligands present in mixed wastes. These ligands have been found in our previous EMSP study to limit electron transfer reactions and strongly affect transport and the eventual fate of radionuclides in the environment. As transuranic waste (and especially mixed waste) will be retained in burial sites and in legacy containment for (potentially) many years while awaiting treatment and removal (or remaining in place under stewardship agreements at government subsurface waste sites), it is also essential to understand the aging of mixed wastes and its implications for remediation and fate of radionuclides. Mixed waste containing actinides and organic materials are especially complex and require extensive study. The EMSP program described in this report is part of a joint program with the Environmental Sciences Department at Brookhaven National Laboratory. The Stony Brook University portion of this award has focused on the association of uranium (U(VI)) and transuranic analogs (Ce(III) and Eu(III)) with cellulosic materials and related compounds, with development of implications for microbial transformation of mixed wastes. The elucidation of the chemical nature of mixed waste is essential for the formulation of remediation and encapsulation technologies, for understanding the fate of contaminant exposed to the environment, and for development of meaningful models for contaminant storage and recovery.

  19. Waste Management's LNG Truck Fleet: Final Results

    SciTech Connect (OSTI)

    Chandler, K.; Norton, P.; Clark, N.

    2001-01-25

    Waste Management, Inc., began operating a fleet of heavy-duty LNG refuse trucks at its Washington, Pennsylvania, facility. The objective of the project was to provide transportation professionals with quantitative, unbiased information on the cost, maintenance, operational, and emissions characteristics of LNG as one alternative to conventional diesel for heavy-duty trucking applications.

  20. Microsoft Word - WIPP Transportation Exhibit.doc

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

    immediate release New WIPP Transportation Exhibit Opens at the National Museum of Nuclear Science & History ALBUQUERQUE, N.M., November 2, 2011 - The National Museum of Nuclear Science & History will debut an exhibit on November 5, 2011, that features the transportation system used by the U.S. Department of Energy (DOE) to ship transuranic (TRU) waste from generator sites nationwide to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, N.M. The exhibit includes a cut-away of the

  1. Calcium spray dryer waste management: Design guidelines: Final report

    SciTech Connect (OSTI)

    Not Available

    1987-09-01

    Calcium spray drying is a commercially available and applied technology used to control SO/sub 2/ emissions. This process is rapidly gaining utility acceptance. Because physical and chemical properties of wastes generated by calcium spray drying differ from those of conventional coal combustion by-products (fly ash and scrubber sludge) typical waste management practices may need to be altered. This report presents technical guidelines for designing and operating a calcium spray drying waste management system. Waste transfer, storage, pretreatment/conditioning, transport and disposal are addressed. The report briefly describes eighteen existing or planned calcium spray drying waste management systems. Results of waste property tests conducted as part of this study, and test data from other studies are reported and compared. Conceptual designs of both new and retrofit calcium spray drying waste management systems also are presented to demonstrate the economic impact of spray drying on waste management. Parametric cost sensitivity analyses illustrate the impact of significant design parameters on waste management costs. Existing calcium spray drying waste management experiences, as well as spray drying waste property data provided the basis for guideline development. Because existing calcium spray drying facilities burn low sulfur coal, this report is considered applicable only to calcium spray drying wastes produced from low sulfur coal. At this time, calcium spray drying is not expected to be feasible for high sulfur coal applications.

  2. A multi-echelon supply chain model for municipal solid waste management system

    SciTech Connect (OSTI)

    Zhang, Yimei; Huang, Guo He; He, Li

    2014-02-15

    In this paper, a multi-echelon multi-period solid waste management system (MSWM) was developed by inoculating with multi-echelon supply chain. Waste managers, suppliers, industries and distributors could be engaged in joint strategic planning and operational execution. The principal of MSWM system is interactive planning of transportation and inventory for each organization in waste collection, delivery and disposal. An efficient inventory management plan for MSWM would lead to optimized productivity levels under available capacities (e.g., transportation and operational capacities). The applicability of the proposed system was illustrated by a case with three cities, one distribution and two waste disposal facilities. Solutions of the decision variable values under different significant levels indicate a consistent trend. With an increased significant level, the total generated waste would be decreased, and the total transported waste through distribution center to waste to energy and landfill would be decreased as well.

  3. Recent Improvement Of The Institutional Radioactive Waste Management System In Slovenia

    SciTech Connect (OSTI)

    Sueiae, S.; Fabjan, M.; Hrastar, U.; Mali, T.; Steinkuhler, C.; Lenie, K.

    2008-07-01

    The task of managing institutional radioactive waste was assigned to the Slovenian National Agency for Radwaste Management by the Governmental Decree of May 1999. This task ranges from the collection of waste at users' premises to the storage in the Central Storage Facility in (CSF) and afterwards to the planned Low and Intermediate Level Waste (LILW) repository. By this Decree ARAO also became the operator of the CSF. The CSF has been in operation since 1986. Recent improvements of the institutional radioactive waste management system in Slovenia are presented in this paper. ARAO has been working on the reestablishment of institutional radioactive waste management since 1999. The Agency has managed to prepare the most important documents and carry out the basic activities required by the legislation to assure a safe and environmentally acceptable management of the institutional radioactive waste. With the aim to achieve a better organized operational system, ARAO took the advantage of the European Union Transition Facility (EU TF) financing support and applied for the project named 'Improvement of the management of institutional radioactive waste in Slovenia via the design and implementation of an Information Business System'. Through a public invitation for tenders one of the Slovenian largest software company gained the contract. Two international radwaste experts from Belgium were part of their project team. The optimization of the operational system has been carried out in 2007. The project was executed in ten months and it was divided into two phases. The first phase of the project was related with the detection of weaknesses and implementation of the necessary improvements in the current ARAO operational system. With the evaluation of the existing system, possible improvements were identified. In the second phase of the project the software system Information Business System (IBS) was developed and implemented by the group of IT experts. As a software

  4. Working with SRNL - Technology Transfer

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

    01/2015 SEARCH SRNL GO Tech Briefs Contacts Ombudsman Tech Home SRNL Home Working with SRNL Technology Transfer 2015 SRNL Research and Technology Recognition Reception Click to view the 2015 SRNL Research and Technology Recognition Reception Savannah River National Laboratory scientists and engineers develop technologies designed to improve environmental quality, support international nonproliferation, dispose of legacy wastes, and provide clean energy sources. SRNL is responsible for

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

    SciTech Connect (OSTI)

    1994-12-31

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

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

    SciTech Connect (OSTI)

    1994-12-31

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

  7. Transportation | NREL

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

    Transportation NREL's transportation infrastructure and programs are designed to significantly reduce petroleum use campus-wide. This infographic shows NREL's FY2015 fleet performance and fleet vehicle history compared to baseline FY 2005 and FY 2014. Petroleum fuel use decreased 28% from 2014 and increased 17% from baseline 2005. Alternative fuel use increased 53% from 2014 and increased 127% from baseline 2005. In baseline 2005, the fleet used 6,521 gasoline gallon equivalent (GGE) of E-85, in

  8. TRANSPORTATION OPTIONS

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

    TRANSPORTATION OPTIONS The Pittsburgh Airport Marriott provides complimentary shuttle service. The hotel asks all guests arriving at the Pittsburgh International Airport to collect luggage in the baggage claim area of the airport and then call for the shuttle at 412-788- 8800. Let the Hotel Operator know that you have collected your luggage and have a reservation at the Marriott and need transportation from the airport. The Hotel Operator will instruct the guest which door to exit, which curb to

  9. Waste Isolation Pilot Plant

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

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

  10. Nuclear Fuel Storage and Transportation Planning Project Overview |

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

    Department of Energy Fuel Storage and Transportation Planning Project Overview Nuclear Fuel Storage and Transportation Planning Project Overview Nuclear Fuel Storage and Transportation Planning Project Overview (956.77 KB) More Documents & Publications Section 180(c) Ad Hoc Working Group DOE Office of Nuclear Energy Transportation Plan Ad Hoc Working Group

  11. Waste Package Lifting Calculation

    SciTech Connect (OSTI)

    H. Marr

    2000-05-11

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

  12. Infectious waste feed system

    DOE Patents [OSTI]

    Coulthard, E. James

    1994-01-01

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

  13. TRU waste from the Superblock

    SciTech Connect (OSTI)

    Coburn, T.T.

    1997-05-27

    This data analysis is to show that weapons grade plutonium is of uniform composition to the standards set by the Waste-Isolation Pilot Plant (WIPP) Transuranic Waste Characterization Quality Assurance Program Plan (TRUW Characterization QAPP, Rev. 2, DOE, Carlsbad Area Office, November 15, 1996). The major portion of Superblock transuranic (TRU) waste is glove-box trash contaminated with weapons grade plutonium. This waste originates in the Building 332 (B332) radioactive-materials area (RMA). Because each plutonium batch brought into the B332 RMA is well characterized with regard to nature and quantity of transuranic nuclides present, waste also will be well characterized without further analytical work, provided the batches are quite similar. A sample data set was created by examining the 41 incoming samples analyzed by Ken Raschke (using a {gamma}-ray spectrometer) for isotopic distribution and by Ted Midtaune (using a calorimeter) for mass of radionuclides. The 41 samples were from separate batches analyzed May 1993 through January 1997. All available weapons grade plutonium data in Midtaune's files were used. Alloys having greater than 50% transuranic material were included. The intention of this study is to use this sample data set to judge ''similarity.''

  14. Robotic Arm Back to Work at Hanford | Department of Energy

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

    Robotic Arm Back to Work at Hanford Robotic Arm Back to Work at Hanford June 1, 2012 - 12:00pm Addthis The Mobile Arm Retrieval System (MARS), the largest robotic arm ever inserted into a Department of Energy waste storage tank, is back at work in one of Hanford’s underground storage tanks where it has removed nearly 133,000 gallons of waste The Mobile Arm Retrieval System (MARS), the largest robotic arm ever inserted into a Department of Energy waste storage tank, is back at work in one of

  15. Effectiveness of interim remedial actions at a radioactive waste facility

    SciTech Connect (OSTI)

    Devgun, J.S.; Beskid, N.J.; Peterson, J.M.; Seay, W.M.; McNamee, E.; USDOE Oak Ridge Operations Office, TN; Bechtel National, Inc., Oak Ridge, TN )

    1989-01-01

    Over the past eight years, several interim remedial actions have been taken at the Niagara Falls Storage Site (NFSS), primarily to reduce radon and gamma radiation exposures and to consolidate radioactive waste into a waste containment facility. Interim remedial actions have included capping of vents, sealing of pipes, relocation of the perimeter fence (to limit radon risk), transfer and consolidation of waste, upgrading of storage buildings, construction of a clay cutoff wall (to limit the potential groundwater transport of contaminants), treatment and release of contaminated water, interim use of a synthetic liner, and emplacement of an interim clay cap. An interim waste containment facility was completed in 1986. 6 refs., 3 figs.

  16. Waste-to-Energy Workshop | Department of Energy

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

    Waste-to-Energy Workshop Waste-to-Energy Workshop November 5, 2014 9:00AM EST to November 6, 2014 12:00PM EST DoubleTree Hotel Crystal City 300 Army Navy Drive Arlington, VA 22202 The Bioenergy Technologies Office (BETO) at the Department of Energy aims to identify and address key technical barriers to the commercial deployment of liquid transportation fuels from waste feedstocks. As a part of this effort, BETO is organizing a Waste-to-Energy workshop. Workshop participants will join facilitated

  17. Transportation Safety

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

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

  18. Radioactive Waste Management Manual

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

    1999-07-09

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

  19. Hanford Dangerous Waste Permit

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

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

  20. Nuclear waste solidification

    DOE Patents [OSTI]

    Bjorklund, William J.

    1977-01-01

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

  1. CRYSTALLINE CERAMIC WASTE FORMS: REFERENCE FORMULATION REPORT

    SciTech Connect (OSTI)

    Brinkman, K.; Fox, K.; Marra, J.

    2012-05-15

    The research conducted in this work package is aimed at taking advantage of the long term thermodynamic stability of crystalline ceramics to create more durable waste forms (as compared to high level waste glass) in order to reduce the reliance on engineered and natural barrier systems. Durable ceramic waste forms that incorporate a wide range of radionuclides have the potential to broaden the available disposal options and to lower the storage and disposal costs associated with advanced fuel cycles. Assemblages of several titanate phases have been successfully demonstrated to incorporate radioactive waste elements, and the multiphase nature of these materials allows them to accommodate variation in the waste composition. Recent work has shown that they can be successfully produced from a melting and crystallization process. The objective of this report is to explain the design of ceramic host systems culminating in a reference ceramic formulation for use in subsequent studies on process optimization and melt property data assessment in support of FY13 melter demonstration testing. The waste stream used as the basis for the development and testing is a combination of the projected Cs/Sr separated stream, the Trivalent Actinide - Lanthanide Separation by Phosphorous reagent Extraction from Aqueous Komplexes (TALSPEAK) waste stream consisting of lanthanide fission products, the transition metal fission product waste stream resulting from the transuranic extraction (TRUEX) process, and a high molybdenum concentration with relatively low noble metal concentrations. In addition to the combined CS/LN/TM High Mo waste stream, variants without Mo and without Mo and Zr were also evaluated. Based on the results of fabricating and characterizing several simulated ceramic waste forms, two reference ceramic waste form compositions are recommended in this report. The first composition targets the CS/LN/TM combined waste stream with and without Mo. The second composition targets

  2. Management of hazardous medical waste in Croatia

    SciTech Connect (OSTI)

    Marinkovic, Natalija Vitale, Ksenija; Holcer, Natasa Janev; Dzakula, Aleksandar; Pavic, Tomo

    2008-07-01

    This article provides a review of hazardous medical waste production and its management in Croatia. Even though Croatian regulations define all steps in the waste management chain, implementation of those steps is one of the country's greatest issues. Improper practice is evident from the point of waste production to final disposal. The biggest producers of hazardous medical waste are hospitals that do not implement existing legislation, due to the lack of education and funds. Information on quantities, type and flow of medical waste are inadequate, as is sanitary control. We propose an integrated approach to medical waste management based on a hierarchical structure from the point of generation to its disposal. Priority is given to the reduction of the amounts and potential for harm. Where this is not possible, management includes reduction by sorting and separating, pretreatment on site, safe transportation, final treatment and sanitary disposal. Preferred methods should be the least harmful for human health and the environment. Integrated medical waste management could greatly reduce quantities and consequently financial strains. Landfilling is the predominant route of disposal in Croatia, although the authors believe that incineration is the most appropriate method. In a country such as Croatia, a number of small incinerators would be the most economical solution.

  3. Radioactive waste management in the former USSR

    SciTech Connect (OSTI)

    Bradley, D.J.

    1992-06-01

    Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

  4. Simple Waste Solutions for Complex Facilities - 12433

    SciTech Connect (OSTI)

    King, Terry I.; Stephan, Clifford J.

    2012-07-01

    The buildings in the 300 Area, including several Category 3 nuclear facilities are undergoing deactivation, decommissioning, decontamination and demolition (D4) by Washington Closure Hanford (WCH) as part of the River Corridor Closure Contract (RCCC). The D4 process has generated a wide variety of low-level radioactive and low-level radioactive mixed waste as well as TRU. The Hanford Site-wide Transportation Safety Document (TSD) has been successfully utilized to transport waste streams that otherwise would not be able to be shipped. The TSD accomplished this by establishing a comprehensive set of onsite transportation and packaging performance standards and risk-based standards. The requirements and standards presented are equivalent to DOT and NRC standards (10 CFR 71). (authors)

  5. NREL: Transportation Research - Transportation News

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

    Transportation News The following news stories highlight transportation research at NREL. August 25, 2016 NREL and NASA Receive Regional FLC Award for Notable Technology NASA Johnson Space Center (JSC) and the National Renewable Energy Laboratory (NREL) were selected as 2016 recipients of a Federal Laboratory Consortium (FLC) Mid-Continent Regional Award, for their notable technology development of the patented Battery Internal Short-Circuit (ISC) Device. August 25, 2016 NREL Helps the National

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

    Office of Environmental Management (EM)

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

  7. Code System to Solve for Release and Transport of Contaminants through Saturated/Unsaturated Media.

    Energy Science and Technology Software Center (OSTI)

    1996-03-07

    The BLT code solves for release and transport of contaminants from containerized wastes. Each container may have unique properties (i.e., time to failure or localized failure, e.g. pitting) and each waste form may have unique release properties. Release from the waste form is limited by one of four physical or chemical constraints: solubility, diffusion, dissolution, and surface wash-off with partitioning. The release from the waste form acts as a source for transport in the advection/dispersionmore » equation. Transport is modeled in two-dimensions through the groundwater pathway from subsurface disposal.« less

  8. High Performance Zero-Bleed CLSM/Grout Mixes for High-Level Waste Tank Closures Strategic Research and Development - FY99 Report

    SciTech Connect (OSTI)

    Langton, C.A.

    2000-08-11

    The overall objective of this program, SRD-99-08, was to design and test suitable materials, which can be used to close high-level waste tanks at SRS. Fill materials can be designed to perform several functions including chemical stabilization and/or physical encapsulation of incidental waste so that the potential for transport of contaminants into the environment is reduced. Also they are needed to physically stabilize the void volume in the tanks to prevent/minimize future subsidence and inadvertent intrusion. The intent of this work was to develop a zero-bleed soil CLSM (ZBS-CLSM) and a zero-bleed concrete mix (ZBC) which meet the unique placement and stabilization/encapsulation requirements for high-level waste tank closures. These mixes in addition to the zero-bleed CLSM mixes formulated for closure of Tanks 17-F and 20-F provide design engineers with a suite of options for specifying materials for future tank closures.

  9. Thirteenth annual U.S. DOE low-level radioactive waste management conference: Proceedings

    SciTech Connect (OSTI)

    1991-12-31

    The 40 papers in this document comprise the proceedings of the Department of Energy`s Thirteenth Annual Low-Level Radioactive Waste Management Conference that was held in Atlanta, Georgia, on November 19--21, 1991. General subjects addressed during the conference included: disposal facility design; greater-than-class C low-level waste; public acceptance considerations; waste certification; site characterization; performance assessment; licensing and documentation; emerging low-level waste technologies; waste minimization; mixed waste; tracking and transportation; storage; and regulatory changes. Papers have been processed separately for inclusion on the data base.

  10. Characterization of the BVEST waste tanks located at ORNL

    SciTech Connect (OSTI)

    Keller, J.M.; Giaquinto, J.M.; Meeks, A.M.

    1997-01-01

    During the fall of 1996 there was a major effort to sample and analyze the Active Liquid Low-Level Waste (LLLW) tanks at ORNL which include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The characterization data summarized in this report was needed to address waste processing options, address concerns dealing with the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the waste characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and meet DOT requirements for transporting the waste. This report discusses the analytical characterization data for the supernatant and sludge in the BVEST waste tanks W-21, W-22, and W-23. The isotopic data presented in this report supports the position that fissile isotopes of uranium and plutonium were denatured as required by the administrative controls stated in the ORNL LLLW waste acceptance criteria (WAC). In general, the BVEST sludge was found to be hazardous based on RCRA characteristics and the transuranic alpha activity was well above the 100 nCi/g limit for TRU waste. The characteristics of the BVEST sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste (RH-TRU) requirements for disposal of the waste in WIPP.

  11. Waste Shipment Approval - Hanford Site

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

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

  12. Waste Processing | Department of Energy

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

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

  13. Weather and the Transport of Hazardous Materials | Department...

    Office of Environmental Management (EM)

    Ad Hoc Working Group Transportation Plan Ad Hoc Working Group Guide to Federal Funding, Financing, and Technical Assistance for Plug-in Electric Vehicles and Charging Stations

  14. Transportation Energy

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

    Energy admin 2015-05-14T22:34:50+00:00 Transportation Energy The national-level objective for the future is to create a carbon-neutral fleet that is powered by low-carbon US sources. Sandia delivers advanced technologies and design tools to the broad transportation sector in the following areas: Predictive Simulation of Engines Fuel sprays and their transition from the liquid to gas phase and computationally tractable models that capture the physics of combustion. Convergence of Biofuels and

  15. Bioprocessing of a stored mixed liquid waste

    SciTech Connect (OSTI)

    Wolfram, J.H.; Rogers, R.D.; Finney, R.

    1995-12-31

    This paper describes the development and results of a demonstration for a continuous bioprocess for mixed waste treatment. A key element of the process is an unique microbial strain which tolerates high levels of aromatic solvents and surfactants. This microorganism is the biocatalysis of the continuous flow system designed for the processing of stored liquid scintillation wastes. During the past year a process demonstration has been conducted on commercial formulation of liquid scintillation cocktails (LSC). Based on data obtained from this demonstration, the Ohio EPA granted the Mound Applied Technologies Lab a treatability permit allowing the limited processing of actual mixed waste. Since August 1994, the system has been successfully processing stored, {open_quotes}hot{close_quotes} LSC waste. The initial LSC waste fed into the system contained 11% pseudocumene and detectable quantities of plutonium. Another treated waste stream contained pseudocumene and tritium. Data from this initial work shows that the hazardous organic solvent, and pseudocumene have been removed due to processing, leaving the aqueous low level radioactive waste. Results to date have shown that living cells are not affected by the dissolved plutonium and that 95% of the plutonium was sorbed to the biomass. This paper discusses the bioprocess, rates of processing, effluent, and the implications of bioprocessing for mixed waste management.

  16. Heat transport system

    DOE Patents [OSTI]

    Pierce, Bill L.

    1978-01-01

    A heat transport system of small size which can be operated in any orientation consists of a coolant loop containing a vaporizable liquid as working fluid and includes in series a vaporizer, a condenser and two one-way valves and a pressurizer connected to the loop between the two valves. The pressurizer may be divided into two chambers by a flexible diaphragm, an inert gas in one chamber acting as a pneumatic spring for the system.

  17. Glass Ceramic Waste Forms for Combined CS+LN+TM Fission Products Waste Streams

    SciTech Connect (OSTI)

    Crum, Jarrod V.; Turo, Laura A.; Riley, Brian J.; Tang, Ming; Kossoy, Anna; Sickafus, Kurt E.

    2010-09-23

    In this study, glass ceramics were explored as an alternative waste form for glass, the current baseline, to be used for immobilizing alkaline/alkaline earth + lanthanide (CS+LN) or CS+LN+transition metal (TM) fission-product waste streams generated by a uranium extraction (UREX+) aqueous separations type process. Results from past work on a glass waste form for the combined CS+LN waste streams showed that as waste loading increased, large fractions of crystalline phases precipitated upon slow cooling.[1] The crystalline phases had no noticeable impact on the waste form performance by the 7-day product consistency test (PCT). These results point towards the development of a glass ceramic waste form for treating CS+LN or CS+LN+TM combined waste streams. Three main benefits for exploring glass ceramics are: (1) Glass ceramics offer increased solubility of troublesome components in crystalline phases as compared to glass, leading to increased waste loading; (2) The crystalline network formed in the glass ceramic results in higher heat tolerance than glass; and (3) These glass ceramics are designed to be processed by the same melter technology as the current baseline glass waste form. It will only require adding controlled canister cooling for crystallization into a glass ceramic waste form. Highly annealed waste form (essentially crack free) with up to 50X lower surface area than a typical High-Level Waste (HLW) glass canister. Lower surface area translates directly into increased durability. This was the first full year of exploring glass ceramics for the Option 1 and 2 combined waste stream options. This work has shown that dramatic increases in waste loading are achievable by designing a glass ceramic waste form as an alternative to glass. Table S1 shows the upper limits for heat, waste loading (based on solubility), and the decay time needed before treatment can occur for glass and glass ceramic waste forms. The improvements are significant for both combined waste

  18. Radioactive Waste Management Manual

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

    1999-07-09

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

  19. Waste Isolation Pilot Plant

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

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

  20. Waste management progress report

    SciTech Connect (OSTI)

    1997-06-01

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